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{{#Wiki_filter:APPENDIX C TURKEY POINT UNIT 7 INSPECTIONS, TESTS, ANALYSES, AND ACCEPTANCE CRITERIA Table of Contents 1.0    Introduction ................................................................................................................ C-32 1.1    Definitions ............................................................................................................... C-32 1.2    General Provisions.................................................................................................. C-35 1.3    Figure Legend......................................................................................................... C-38 1.4    List of Acronyms and Abbreviations ........................................................................ C-42 2.0    System Based Design Descriptions and ITAAC.......................................................... C-48 2.1    Reactor....................................................................................................................... C-48 2.1.1    Fuel Handling and Refueling System................................................................... C-48 2.1.01.01........................................................................................................................ C-49 2.1.01.02........................................................................................................................ C-49 2.1.01.03........................................................................................................................ C-49 2.1.01.04........................................................................................................................ C-49 2.1.01.05........................................................................................................................ C-49 2.1.01.06.i ...................................................................................................................... C-49 2.1.01.06.ii ..................................................................................................................... C-49 2.1.01.07.i ...................................................................................................................... C-49 2.1.01.07.ii ..................................................................................................................... C-49 2.1.01.07.iii .................................................................................................................... C-50 2.1.01.07.iv .................................................................................................................... C-50 2.1.2    Reactor Coolant System...................................................................................... C-52 2.1.02.01........................................................................................................................ C-63 2.1.02.02a...................................................................................................................... C-63 2.1.02.02b...................................................................................................................... C-63 2.1.02.03a...................................................................................................................... C-63 2.1.02.03b...................................................................................................................... C-63 2.1.02.04a...................................................................................................................... C-64 2.1.02.04b...................................................................................................................... C-64 2.1.02.05a.i .................................................................................................................... C-64 C-1
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2.1.02.05a.ii ................................................................................................................... C-64 2.1.02.05a.iii .................................................................................................................. C-64 2.1.02.05b...................................................................................................................... C-64 2.1.02.06........................................................................................................................ C-65 2.1.02.07a.i .................................................................................................................... C-65 2.1.02.07a.ii ................................................................................................................... C-65 2.1.02.07b...................................................................................................................... C-65 2.1.02.07c ...................................................................................................................... C-66 2.1.02.08a.i .................................................................................................................... C-66 2.1.02.08a.ii ................................................................................................................... C-66 2.1.02.08b...................................................................................................................... C-66 2.1.02.08c ...................................................................................................................... C-66 2.1.02.08d.i .................................................................................................................... C-67 2.1.02.08d.ii ................................................................................................................... C-67 2.1.02.08d.iii .................................................................................................................. C-67 2.1.02.08d.iv .................................................................................................................. C-68 2.1.02.08d.v ................................................................................................................... C-68 2.1.02.08d.vi .................................................................................................................. C-68 2.1.02.08d.vii ................................................................................................................. C-68 2.1.02.08d.viii................................................................................................................. C-68 2.1.02.08e...................................................................................................................... C-68 2.1.02.09a...................................................................................................................... C-68 2.1.02.09b.i .................................................................................................................... C-69 2.1.02.09b.ii ................................................................................................................... C-69 2.1.02.09c ...................................................................................................................... C-69 2.1.02.10........................................................................................................................ C-69 2.1.02.11a.i .................................................................................................................... C-69 2.1.02.11a.ii ................................................................................................................... C-69 2.1.02.11b.i .................................................................................................................... C-69 2.1.02.11b.ii ................................................................................................................... C-69 2.1.02.11b.iii .................................................................................................................. C-70 2.1.02.11c.i .................................................................................................................... C-70 2.1.02.11c.ii ................................................................................................................... C-70 2.1.02.12a.i .................................................................................................................... C-70 C-2
 
2.1.02.12a.ii ................................................................................................................... C-70 2.1.02.12a.iii .................................................................................................................. C-70 2.1.02.12a.iv .................................................................................................................. C-71 2.1.02.12a.v ................................................................................................................... C-71 2.1.02.12a.vi .................................................................................................................. C-71 2.1.02.12a.vii ................................................................................................................. C-71 2.1.02.12a.viii................................................................................................................. C-71 2.1.02.12a.ix .................................................................................................................. C-71 2.1.02.12b...................................................................................................................... C-71 2.1.02.13a...................................................................................................................... C-71 2.1.02.13b...................................................................................................................... C-72 2.1.02.13c ...................................................................................................................... C-72 2.1.02.14........................................................................................................................ C-72 2.1.02.15........................................................................................................................ C-72 2.1.3    Reactor System ................................................................................................... C-76 2.1.03.01........................................................................................................................ C-80 2.1.03.02a...................................................................................................................... C-80 2.1.03.02b...................................................................................................................... C-80 2.1.03.02c ...................................................................................................................... C-80 2.1.03.03........................................................................................................................ C-80 2.1.03.04........................................................................................................................ C-80 2.1.03.05........................................................................................................................ C-80 2.1.03.06.i ...................................................................................................................... C-81 2.1.03.06.ii ..................................................................................................................... C-81 2.1.03.06.iii .................................................................................................................... C-81 2.1.03.07.i ...................................................................................................................... C-81 2.1.03.07.ii ..................................................................................................................... C-81 2.1.03.08........................................................................................................................ C-81 2.1.03.09a.i .................................................................................................................... C-82 2.1.03.09a.ii ................................................................................................................... C-82 2.1.03.09b...................................................................................................................... C-82 2.1.03.09c ...................................................................................................................... C-82 2.1.03.10........................................................................................................................ C-82 2.1.03.11........................................................................................................................ C-82 C-3
 
2.1.03.12........................................................................................................................ C-83 2.1.03.13........................................................................................................................ C-83 2.1.03.14........................................................................................................................ C-83 2.2    Nuclear Safety Systems ............................................................................................. C-90 2.2.1    Containment System ........................................................................................... C-90 2.2.01.01...................................................................................................................... C-100 2.2.01.02a.................................................................................................................... C-100 2.2.01.02b.................................................................................................................... C-100 2.2.01.03a.................................................................................................................... C-100 2.2.01.03b.................................................................................................................... C-100 2.2.01.04a.i .................................................................................................................. C-100 2.2.01.04a.ii ................................................................................................................. C-100 2.2.01.04b.................................................................................................................... C-101 2.2.01.05.i .................................................................................................................... C-101 2.2.01.05.ii ................................................................................................................... C-101 2.2.01.05.iii .................................................................................................................. C-101 2.2.01.06a.i .................................................................................................................. C-101 2.2.01.06a.ii ................................................................................................................. C-102 2.2.01.06b.................................................................................................................... C-102 2.2.01.06c .................................................................................................................... C-102 2.2.01.06d.i .................................................................................................................. C-102 2.2.01.06d.ii ................................................................................................................. C-102 2.2.01.07.i .................................................................................................................... C-103 2.2.01.07.ii ................................................................................................................... C-103 2.2.01.08...................................................................................................................... C-103 2.2.01.09...................................................................................................................... C-104 2.2.01.10a.................................................................................................................... C-104 2.2.01.10b.................................................................................................................... C-104 2.2.01.10c .................................................................................................................... C-104 2.2.01.11a.i .................................................................................................................. C-104 2.2.01.11a.ii ................................................................................................................. C-104 2.2.01.11a.iii ................................................................................................................ C-104 2.2.01.11a.iv ................................................................................................................ C-105 2.2.01.11b.................................................................................................................... C-105 C-4
 
2.2.2    Passive Containment Cooling System ............................................................... C-107 2.2.02.01...................................................................................................................... C-113 2.2.02.02a.................................................................................................................... C-113 2.2.02.02b.................................................................................................................... C-113 2.2.02.03a.................................................................................................................... C-113 2.2.02.03b.................................................................................................................... C-113 2.2.02.04a.................................................................................................................... C-113 2.2.02.04b.................................................................................................................... C-113 2.2.02.05a.i .................................................................................................................. C-114 2.2.02.05a.ii ................................................................................................................. C-114 2.2.02.05a.iii ................................................................................................................ C-114 2.2.02.05b.................................................................................................................... C-114 2.2.02.05c .................................................................................................................... C-114 2.2.02.06a.i .................................................................................................................. C-114 2.2.02.06a.ii ................................................................................................................. C-115 2.2.02.06b.................................................................................................................... C-115 2.2.02.06c .................................................................................................................... C-115 2.2.02.07a.i .................................................................................................................. C-115 2.2.02.07a.ii ................................................................................................................. C-115 2.2.02.07a.iii ................................................................................................................ C-116 2.2.02.07b.i .................................................................................................................. C-116 2.2.02.07b.ii ................................................................................................................. C-116 2.2.02.07b.iii ................................................................................................................ C-116 2.2.02.07c .................................................................................................................... C-117 2.2.02.07d.................................................................................................................... C-117 2.2.02.07e.i .................................................................................................................. C-117 2.2.02.07e.ii ................................................................................................................. C-117 2.2.02.07f.i ................................................................................................................... C-117 2.2.02.07f.ii .................................................................................................................. C-117 2.2.02.08a.................................................................................................................... C-117 2.2.02.08b.................................................................................................................... C-117 2.2.02.08c .................................................................................................................... C-118 2.2.02.09...................................................................................................................... C-118 2.2.02.10a.................................................................................................................... C-118 C-5
 
2.2.02.10b.................................................................................................................... C-118 2.2.02.10c .................................................................................................................... C-118 2.2.02.11a.i .................................................................................................................. C-118 2.2.02.11a.ii ................................................................................................................. C-118 2.2.02.11a.iii ................................................................................................................ C-118 2.2.02.11b.................................................................................................................... C-119 2.2.3    Passive Core Cooling System ........................................................................... C-121 2.2.03.01...................................................................................................................... C-134 2.2.03.02a.................................................................................................................... C-134 2.2.03.02b.................................................................................................................... C-134 2.2.03.03a.................................................................................................................... C-134 2.2.03.03b.................................................................................................................... C-134 2.2.03.04a.................................................................................................................... C-134 2.2.03.04b.................................................................................................................... C-134 2.2.03.05a.i .................................................................................................................. C-135 2.2.03.05a.ii ................................................................................................................. C-135 2.2.03.05a.iii ................................................................................................................ C-135 2.2.03.05b.................................................................................................................... C-135 2.2.03.06...................................................................................................................... C-136 2.2.03.07a.i .................................................................................................................. C-136 2.2.03.07a.ii ................................................................................................................. C-136 2.2.03.07b.................................................................................................................... C-136 2.2.03.07c .................................................................................................................... C-136 2.2.03.08a.................................................................................................................... C-137 2.2.03.08b.01 ............................................................................................................... C-137 2.2.03.08b.02 ............................................................................................................... C-137 2.2.03.08c.i.01 ............................................................................................................. C-137 2.2.03.08c.i.02 ............................................................................................................. C-138 2.2.03.08c.i.03 ............................................................................................................. C-138 2.2.03.08c.i.04 ............................................................................................................. C-139 2.2.03.08c.ii ................................................................................................................. C-139 2.2.03.08c.iii ................................................................................................................ C-139 2.2.03.08c.iv.01 ........................................................................................................... C-139 2.2.03.08c.iv.02 ........................................................................................................... C-139 C-6
 
2.2.03.08c.iv.03 ........................................................................................................... C-140 2.2.03.08c.iv.04 ........................................................................................................... C-140 2.2.03.08c.v.01 ............................................................................................................ C-140 2.2.03.08c.v.02 ............................................................................................................ C-140 2.2.03.08c.vi.01 ........................................................................................................... C-140 2.2.03.08c.vi.02 ........................................................................................................... C-140 2.2.03.08c.vi.03 ........................................................................................................... C-140 2.2.03.08c.vii................................................................................................................ C-141 2.2.03.08c.viii ............................................................................................................... C-141 2.2.03.08c.ix ................................................................................................................ C-142 2.2.03.08c.x ................................................................................................................. C-143 2.2.03.08c.xi ................................................................................................................ C-144 2.2.03.08c.xii................................................................................................................ C-144 2.2.03.08c.xiii ............................................................................................................... C-144 2.2.03.08c.xiv............................................................................................................... C-144 2.2.03.08d.................................................................................................................... C-144 2.2.03.09a.i .................................................................................................................. C-144 2.2.03.09a.ii ................................................................................................................. C-145 2.2.03.09a.iii ................................................................................................................ C-145 2.2.03.09b.................................................................................................................... C-145 2.2.03.09c .................................................................................................................... C-145 2.2.03.10...................................................................................................................... C-145 2.2.03.11a.i .................................................................................................................. C-145 2.2.03.11a.ii ................................................................................................................. C-145 2.2.03.11b.i .................................................................................................................. C-146 2.2.03.11b.ii ................................................................................................................. C-146 2.2.03.11b.iii ................................................................................................................ C-146 2.2.03.11c.i .................................................................................................................. C-146 2.2.03.11c.ii ................................................................................................................. C-146 2.2.03.12a.i .................................................................................................................. C-146 2.2.03.12a.ii ................................................................................................................. C-146 2.2.03.12a.iv ................................................................................................................ C-146 2.2.03.12b.................................................................................................................... C-147 2.2.03.13...................................................................................................................... C-147 C-7
 
2.2.4    Steam Generator System .................................................................................. C-151 2.2.04.01...................................................................................................................... C-164 2.2.04.02a.................................................................................................................... C-164 2.2.04.02b.................................................................................................................... C-164 2.2.04.03a.................................................................................................................... C-164 2.2.04.03b.................................................................................................................... C-164 2.2.04.04a.................................................................................................................... C-164 2.2.04.04b.................................................................................................................... C-164 2.2.04.05a.i .................................................................................................................. C-165 2.2.04.05a.ii ................................................................................................................. C-165 2.2.04.05a.iii ................................................................................................................ C-165 2.2.04.05b.................................................................................................................... C-165 2.2.04.06...................................................................................................................... C-165 2.2.04.07a.i .................................................................................................................. C-166 2.2.04.07a.ii ................................................................................................................. C-166 2.2.04.07b.................................................................................................................... C-166 2.2.04.07c .................................................................................................................... C-166 2.2.04.08a.i .................................................................................................................. C-166 2.2.04.08a.ii ................................................................................................................. C-166 2.2.04.08b.i .................................................................................................................. C-167 2.2.04.08b.ii ................................................................................................................. C-167 2.2.04.08c .................................................................................................................... C-167 2.2.04.09a.i .................................................................................................................. C-167 2.2.04.09a.ii ................................................................................................................. C-167 2.2.04.09b.i .................................................................................................................. C-167 2.2.04.09b.ii ................................................................................................................. C-167 2.2.04.10...................................................................................................................... C-167 2.2.04.11a.................................................................................................................... C-168 2.2.04.11b.i .................................................................................................................. C-168 2.2.04.11b.ii ................................................................................................................. C-168 2.2.04.12a.i .................................................................................................................. C-168 2.2.04.12a.ii ................................................................................................................. C-168 2.2.04.12a.iii ................................................................................................................ C-168 2.2.04.12b.................................................................................................................... C-168 C-8
 
2.2.5    Main Control Room Emergency Habitability System .......................................... C-173 2.2.05.01...................................................................................................................... C-181 2.2.05.02a.................................................................................................................... C-182 2.2.05.02b.................................................................................................................... C-182 2.2.05.03a.................................................................................................................... C-182 2.2.05.03b.................................................................................................................... C-182 2.2.05.04a.................................................................................................................... C-182 2.2.05.04b.................................................................................................................... C-182 2.2.05.05a.i .................................................................................................................. C-182 2.2.05.05a.ii ................................................................................................................. C-183 2.2.05.05a.iii ................................................................................................................ C-183 2.2.05.05b.................................................................................................................... C-183 2.2.05.06a.................................................................................................................... C-183 2.2.05.06b.................................................................................................................... C-183 2.2.05.07a.i .................................................................................................................. C-183 2.2.05.07a.ii ................................................................................................................. C-183 2.2.05.07a.iii ................................................................................................................ C-183 2.2.05.07b.i .................................................................................................................. C-184 2.2.05.07b.ii ................................................................................................................. C-184 2.2.05.07c .................................................................................................................... C-184 2.2.05.07d.................................................................................................................... C-184 C.2.2.05.07e ................................................................................................................ C-184 2.2.05.08...................................................................................................................... C-185 2.2.05.09a.................................................................................................................... C-185 2.2.05.09b.................................................................................................................... C-185 2.2.05.10...................................................................................................................... C-185 2.2.05.11...................................................................................................................... C-185 2.2.05.12...................................................................................................................... C-185 2.3    Auxiliary Systems ..................................................................................................... C-188 2.3.1    Component Cooling Water System.................................................................... C-188 2.3.01.01...................................................................................................................... C-190 2.3.01.02...................................................................................................................... C-190 2.3.01.03.i .................................................................................................................... C-190 2.3.01.03.ii ................................................................................................................... C-190 C-9
 
2.3.01.04...................................................................................................................... C-190 2.3.01.05...................................................................................................................... C-190 2.3.2    Chemical and Volume Control System .............................................................. C-192 2.3.02.01...................................................................................................................... C-199 2.3.02.02a.................................................................................................................... C-199 2.3.02.02b.................................................................................................................... C-200 2.3.02.03a.................................................................................................................... C-200 2.3.02.03b.................................................................................................................... C-200 2.3.02.04a.................................................................................................................... C-200 2.3.02.04b.................................................................................................................... C-200 2.3.02.05.i .................................................................................................................... C-200 2.3.02.05.ii ................................................................................................................... C-200 2.3.02.05.iii .................................................................................................................. C-201 2.3.02.06a.i .................................................................................................................. C-201 2.3.02.06a.ii ................................................................................................................. C-201 2.3.02.06b.................................................................................................................... C-201 2.3.02.06c .................................................................................................................... C-201 2.3.02.07a.................................................................................................................... C-201 2.3.02.07b.................................................................................................................... C-202 2.3.02.07c .................................................................................................................... C-202 2.3.02.08a.i .................................................................................................................. C-202 2.3.02.08a.ii ................................................................................................................. C-202 2.3.02.08a.iii ................................................................................................................ C-202 2.3.02.08b.................................................................................................................... C-202 2.3.02.09...................................................................................................................... C-202 2.3.02.10a.................................................................................................................... C-203 2.3.02.10b.i .................................................................................................................. C-203 2.3.02.10b.ii ................................................................................................................. C-203 2.3.02.11a.i .................................................................................................................. C-203 2.3.02.11a.ii ................................................................................................................. C-203 2.3.02.11a.iii ................................................................................................................ C-203 2.3.02.11a.iv ................................................................................................................ C-203 2.3.02.11b.................................................................................................................... C-204 2.3.02.12a.................................................................................................................... C-204 C-10
 
2.3.02.12b.................................................................................................................... C-204 2.3.02.13...................................................................................................................... C-204 2.3.02.14...................................................................................................................... C-204 2.3.3    Standby Diesel Fuel Oil System ........................................................................ C-207 2.3.03.01...................................................................................................................... C-208 2.3.03.02...................................................................................................................... C-208 2.3.03.03a.................................................................................................................... C-208 2.3.03.03b.................................................................................................................... C-208 2.3.03.03c .................................................................................................................... C-208 2.3.03.03d.................................................................................................................... C-208 2.3.03.04...................................................................................................................... C-208 2.3.03.05...................................................................................................................... C-208 2.3.4    Fire Protection System ...................................................................................... C-211 2.3.04.01...................................................................................................................... C-212 2.3.04.02.i .................................................................................................................... C-212 2.3.04.02.ii ................................................................................................................... C-212 2.3.04.03...................................................................................................................... C-212 2.3.04.04.i .................................................................................................................... C-212 2.3.04.04.ii ................................................................................................................... C-212 2.3.04.05...................................................................................................................... C-212 2.3.04.06...................................................................................................................... C-212 2.3.04.07...................................................................................................................... C-212 2.3.04.08...................................................................................................................... C-213 2.3.04.09...................................................................................................................... C-213 2.3.04.10...................................................................................................................... C-213 2.3.04.11...................................................................................................................... C-213 2.3.5    Mechanical Handling System ............................................................................ C-217 2.3.05.01...................................................................................................................... C-218 2.3.05.02.i .................................................................................................................... C-218 2.3.05.02.ii ................................................................................................................... C-218 2.3.05.02.iii .................................................................................................................. C-218 2.3.05.03a.i .................................................................................................................. C-218 2.3.05.03a.ii ................................................................................................................. C-218 2.3.05.03a.iii ................................................................................................................ C-218 C-11
 
2.3.05.03b.i .................................................................................................................. C-219 2.3.05.03b.ii ................................................................................................................. C-219 2.3.05.03b.iii ................................................................................................................ C-219 2.3.05.03c.i .................................................................................................................. C-219 2.3.05.03c.ii ................................................................................................................. C-219 2.3.05.03d.i .................................................................................................................. C-219 2.3.05.03d.ii ................................................................................................................. C-220 2.3.05.04...................................................................................................................... C-220 2.3.6    Normal Residual Heat Removal System ............................................................ C-221 2.3.06.01...................................................................................................................... C-229 2.3.06.02a.................................................................................................................... C-229 2.3.06.02b.................................................................................................................... C-229 2.3.06.03a.................................................................................................................... C-229 2.3.06.03b.................................................................................................................... C-230 2.3.06.04a.................................................................................................................... C-230 2.3.06.04b.................................................................................................................... C-230 2.3.06.05a.i .................................................................................................................. C-230 2.3.06.05a.ii ................................................................................................................. C-230 2.3.06.05a.iii ................................................................................................................ C-230 2.3.06.05b.................................................................................................................... C-231 2.3.06.06...................................................................................................................... C-231 2.3.06.07a.i .................................................................................................................. C-231 2.3.06.07a.ii ................................................................................................................. C-231 2.3.06.07b.................................................................................................................... C-231 2.3.06.07c .................................................................................................................... C-232 2.3.06.08a.................................................................................................................... C-232 2.3.06.08b.................................................................................................................... C-232 2.3.06.09a.i .................................................................................................................. C-232 2.3.06.09a.ii ................................................................................................................. C-232 2.3.06.09b.i .................................................................................................................. C-232 2.3.06.09b.ii ................................................................................................................. C-233 2.3.06.09b.iii ................................................................................................................ C-233 2.3.06.09b.iv ................................................................................................................ C-233 2.3.06.09b.v ................................................................................................................. C-233 C-12
 
2.3.06.09c .................................................................................................................... C-233 2.3.06.09d.................................................................................................................... C-233 2.3.06.10...................................................................................................................... C-233 2.3.06.11a.................................................................................................................... C-234 2.3.06.11b.................................................................................................................... C-234 2.3.06.12a.i .................................................................................................................. C-234 2.3.06.12a.ii ................................................................................................................. C-234 2.3.06.12a.iii ................................................................................................................ C-234 2.3.06.12a.iv ................................................................................................................ C-234 2.3.06.12b.................................................................................................................... C-234 2.3.06.13...................................................................................................................... C-234 2.3.06.14...................................................................................................................... C-235 2.3.7    Spent Fuel Pool Cooling System ....................................................................... C-237 2.3.07.01...................................................................................................................... C-242 2.3.07.02a.................................................................................................................... C-242 2.3.07.02b.................................................................................................................... C-242 2.3.07.03...................................................................................................................... C-242 2.3.07.04...................................................................................................................... C-242 2.3.07.05.i .................................................................................................................... C-242 2.3.07.05.ii ................................................................................................................... C-242 2.3.07.05.iii .................................................................................................................. C-243 2.3.07.06a.................................................................................................................... C-243 2.3.07.06b.................................................................................................................... C-243 2.3.07.07a.................................................................................................................... C-243 2.3.07.07b.i .................................................................................................................. C-243 2.3.07.07b.ii ................................................................................................................. C-243 2.3.07.07b.iii ................................................................................................................ C-243 2.3.07.07b.iv ................................................................................................................ C-243 2.3.07.07b.v ................................................................................................................. C-244 2.3.07.07b.vi ................................................................................................................ C-244 2.3.07.07c .................................................................................................................... C-244 2.3.07.08.i .................................................................................................................... C-244 2.3.07.08.ii ................................................................................................................... C-244 2.3.07.09...................................................................................................................... C-244 C-13
 
2.3.07.10...................................................................................................................... C-244 2.3.07.11...................................................................................................................... C-244 2.3.8    Service Water System ....................................................................................... C-247 2.3.08.01...................................................................................................................... C-248 2.3.08.02.i .................................................................................................................... C-248 2.3.08.02.ii ................................................................................................................... C-249 2.3.08.02.iii .................................................................................................................. C-249 2.3.08.03...................................................................................................................... C-249 2.3.08.04...................................................................................................................... C-249 2.3.9    Containment Hydrogen Control System ............................................................ C-251 2.3.09.01...................................................................................................................... C-254 2.3.09.02a.................................................................................................................... C-254 2.3.09.02b.................................................................................................................... C-255 2.3.09.03.i .................................................................................................................... C-255 2.3.09.03.ii ................................................................................................................... C-255 C.2.3.09.03.iii ............................................................................................................... C-255 2.3.09.03.iv .................................................................................................................. C-255 2.3.09.04a.................................................................................................................... C-255 2.3.09.04b.................................................................................................................... C-256 2.3.09.05...................................................................................................................... C-256 2.3.10  Liquid Radwaste System ................................................................................... C-257 2.3.10.01...................................................................................................................... C-260 2.3.10.02a.................................................................................................................... C-260 2.3.10.02b.................................................................................................................... C-260 2.3.10.03a.................................................................................................................... C-261 2.3.10.03b.................................................................................................................... C-261 2.3.10.04a.................................................................................................................... C-261 2.3.10.04b.................................................................................................................... C-261 2.3.10.05a.i .................................................................................................................. C-261 2.3.10.05a.ii ................................................................................................................. C-261 2.3.10.05a.iii ................................................................................................................ C-261 2.3.10.05b.................................................................................................................... C-262 2.3.10.06a.................................................................................................................... C-262 2.3.10.06b.................................................................................................................... C-262 C-14
 
2.3.10.07a.i .................................................................................................................. C-262 2.3.10.07a.ii ................................................................................................................. C-262 2.3.10.07b.................................................................................................................... C-262 2.3.10.08...................................................................................................................... C-262 2.3.10.09...................................................................................................................... C-262 2.3.10.10...................................................................................................................... C-263 2.3.11  Gaseous Radwaste System .............................................................................. C-265 2.3.11.01...................................................................................................................... C-265 2.3.11.02.i .................................................................................................................... C-266 2.3.11.02.ii ................................................................................................................... C-266 2.3.11.02.iii .................................................................................................................. C-266 2.3.11.03a.................................................................................................................... C-266 2.3.11.03b.................................................................................................................... C-266 2.3.11.03c .................................................................................................................... C-266 2.3.12  Solid Radwaste System..................................................................................... C-269 2.3.12.01...................................................................................................................... C-269 2.3.12.02...................................................................................................................... C-269 2.3.13  Primary Sampling System ................................................................................. C-270 2.3.13.01...................................................................................................................... C-273 2.3.13.02...................................................................................................................... C-273 2.3.13.03...................................................................................................................... C-273 2.3.13.04...................................................................................................................... C-273 2.3.13.05.i .................................................................................................................... C-273 2.3.13.05.ii ................................................................................................................... C-273 2.3.13.05.iii .................................................................................................................. C-274 2.3.13.06a.i .................................................................................................................. C-274 2.3.13.06a.ii ................................................................................................................. C-274 2.3.13.06b.................................................................................................................... C-274 2.3.13.06c .................................................................................................................... C-274 2.3.13.07...................................................................................................................... C-274 2.3.13.08...................................................................................................................... C-275 2.3.13.09...................................................................................................................... C-275 2.3.13.10a.................................................................................................................... C-275 2.3.13.10b.................................................................................................................... C-275 C-15
 
2.3.13.11a.................................................................................................................... C-275 2.3.13.11b.................................................................................................................... C-275 2.3.13.12...................................................................................................................... C-275 2.3.14  Demineralized Water Transfer and Storage System .......................................... C-277 2.3.14.01...................................................................................................................... C-278 2.3.14.02...................................................................................................................... C-278 2.3.14.03...................................................................................................................... C-278 2.3.14.04...................................................................................................................... C-278 2.3.15  Compressed and Instrument Air System ........................................................... C-279 2.3.15.01...................................................................................................................... C-280 2.3.15.02...................................................................................................................... C-280 2.3.15.03...................................................................................................................... C-280 2.3.16  Potable Water System ....................................................................................... C-281 2.3.17  Waste Water System ......................................................................................... C-281 2.3.18  Plant Gas System.............................................................................................. C-281 2.3.19  Communication System..................................................................................... C-281 2.3.19.01a.................................................................................................................... C-282 2.3.19.01b.................................................................................................................... C-282 2.3.19.02a.................................................................................................................... C-282 2.3.19.02b.................................................................................................................... C-282 2.3.20  Turbine Building Closed Cooling Water System ................................................ C-283 2.3.21  Secondary Sampling System............................................................................. C-283 2.3.22  Containment Leak Rate Test System ................................................................ C-283 2.3.23  This section intentionally blank .......................................................................... C-283 2.3.24  Demineralized Water Treatment System ........................................................... C-283 2.3.25  Gravity and Roof Drain Collection System ......................................................... C-283 2.3.26  This section intentionally blank .......................................................................... C-283 2.3.27  Sanitary Drainage System ................................................................................. C-283 2.3.28  Turbine Island Vents, Drains, and Relief System ............................................... C-283 2.3.29  Radioactive Waste Drain System ...................................................................... C-284 2.3.29.01...................................................................................................................... C-285 2.3.29.02...................................................................................................................... C-285 2.3.29.03...................................................................................................................... C-285 2.3.29.04...................................................................................................................... C-285 C-16
 
2.3.30  Storm Drain System .......................................................................................... C-287 2.3.31  Raw Water System ............................................................................................ C-287 2.3.32  Yard Fire Water System .................................................................................... C-287 2.4    Steam and Power Conversion Systems.................................................................... C-288 2.4.1    Main and Startup Feedwater System................................................................. C-288 2.4.01.01...................................................................................................................... C-289 2.4.01.02...................................................................................................................... C-289 2.4.01.03...................................................................................................................... C-289 2.4.01.04...................................................................................................................... C-289 2.4.2    Main Turbine System......................................................................................... C-291 2.4.02.01...................................................................................................................... C-291 2.4.02.02a.................................................................................................................... C-291 2.4.02.02b.................................................................................................................... C-291 2.4.02.02c .................................................................................................................... C-291 2.4.02.03.i .................................................................................................................... C-291 2.4.02.03.ii ................................................................................................................... C-292 2.4.02.03.iii .................................................................................................................. C-292 2.4.3    Main Steam System .......................................................................................... C-293 2.4.4    Steam Generator Blowdown System ................................................................. C-293 2.4.5    Condenser Air Removal System ........................................................................ C-293 2.4.6    Condensate System .......................................................................................... C-294 2.4.06.01...................................................................................................................... C-294 2.4.06.02...................................................................................................................... C-294 2.4.7    Circulating Water System .................................................................................. C-296 2.4.8    Auxiliary Steam Supply System ......................................................................... C-296 2.4.9    Condenser Tube Cleaning System .................................................................... C-296 2.4.10  Turbine Island Chemical Feed System .............................................................. C-296 2.4.11  Condensate Polishing System ........................................................................... C-296 2.4.12  Gland Seal System............................................................................................ C-296 2.4.13  Generator Hydrogen and CO2 System .............................................................. C-296 2.4.14  Heater Drain System ......................................................................................... C-296 2.4.15  Hydrogen Seal Oil System ................................................................................ C-296 2.4.16  Main Turbine and Generator Lube Oil System ................................................... C-296 C-17
 
2.5    Instrumentation and Control Systems ....................................................................... C-297 2.5.1    Diverse Actuation System ................................................................................. C-297 2.5.01.01...................................................................................................................... C-300 2.5.01.02a.................................................................................................................... C-300 2.5.01.02b.................................................................................................................... C-300 2.5.01.02c.i .................................................................................................................. C-300 2.5.01.02c.ii ................................................................................................................. C-300 2.5.01.02d.................................................................................................................... C-300 2.5.01.03a.................................................................................................................... C-301 2.5.01.03b.................................................................................................................... C-301 2.5.01.03c .................................................................................................................... C-301 2.5.01.03d.................................................................................................................... C-301 2.5.01.03e.................................................................................................................... C-301 2.5.01.03f..................................................................................................................... C-301 2.5.01.03g .................................................................................................................... C-302 2.5.01.03h.................................................................................................................... C-302 2.5.01.04...................................................................................................................... C-302 2.5.01.05...................................................................................................................... C-302 2.5.2    Protection and Safety Monitoring System .......................................................... C-304 2.5.02.01...................................................................................................................... C-311 2.5.02.02.i .................................................................................................................... C-312 2.5.02.02.ii ................................................................................................................... C-312 2.5.02.02.iii .................................................................................................................. C-312 2.5.02.03...................................................................................................................... C-312 2.5.02.04...................................................................................................................... C-312 2.5.02.05a.................................................................................................................... C-313 2.5.02.05b.................................................................................................................... C-313 2.5.02.06a.i .................................................................................................................. C-313 2.5.02.06a.ii ................................................................................................................. C-313 2.5.02.06b.................................................................................................................... C-313 2.5.02.06c.i .................................................................................................................. C-313 2.5.02.06c.ii ................................................................................................................. C-314 2.5.02.07a.................................................................................................................... C-314 2.5.02.07b.................................................................................................................... C-314 C-18
 
2.5.02.07c .................................................................................................................... C-314 2.5.02.07d.................................................................................................................... C-314 2.5.02.07e.................................................................................................................... C-314 2.5.02.08a.i .................................................................................................................. C-314 2.5.02.08a.ii ................................................................................................................. C-315 2.5.02.08a.iii ................................................................................................................ C-315 2.5.02.08b.i .................................................................................................................. C-315 2.5.02.08b.ii ................................................................................................................. C-315 2.5.02.08c .................................................................................................................... C-315 2.5.02.09a.................................................................................................................... C-316 2.5.02.09b.................................................................................................................... C-316 2.5.02.09c .................................................................................................................... C-316 2.5.02.09d.................................................................................................................... C-316 2.5.02.10...................................................................................................................... C-316 2.5.02.11...................................................................................................................... C-317 2.5.02.12...................................................................................................................... C-318 2.5.02.13...................................................................................................................... C-319 2.5.02.14...................................................................................................................... C-319 2.5.3    Plant Control System ......................................................................................... C-322 2.5.03.01...................................................................................................................... C-322 2.5.03.02...................................................................................................................... C-322 2.5.4    Data Display and Processing System ................................................................ C-323 2.5.04.01...................................................................................................................... C-326 2.5.04.02.i .................................................................................................................... C-326 2.5.04.02.ii ................................................................................................................... C-326 2.5.04.02.iii .................................................................................................................. C-326 2.5.04.03...................................................................................................................... C-326 C.2.5.04.04a ................................................................................................................ C-327 C.2.5.04.04b ................................................................................................................ C-327 C.2.5.04.04c ................................................................................................................ C-327 2.5.5    In-Core Instrumentation System ........................................................................ C-328 2.5.05.01...................................................................................................................... C-329 2.5.05.02.i .................................................................................................................... C-329 2.5.05.02.ii ................................................................................................................... C-329 C-19
 
2.5.05.02.iii .................................................................................................................. C-329 2.5.05.03a.i .................................................................................................................. C-329 2.5.05.03a.ii ................................................................................................................. C-330 2.5.05.03b.................................................................................................................... C-330 2.5.05.03c .................................................................................................................... C-330 2.5.05.04...................................................................................................................... C-330 2.5.6    Special Monitoring System ................................................................................ C-331 2.5.06.01...................................................................................................................... C-331 2.5.06.02...................................................................................................................... C-331 2.5.7    Operation and Control Centers System ............................................................. C-332 2.5.8    Radiation Monitoring System ............................................................................. C-332 2.5.9    Seismic Monitoring System ............................................................................... C-332 2.5.09.01...................................................................................................................... C-332 2.5.09.02...................................................................................................................... C-333 2.5.09.03...................................................................................................................... C-333 2.5.10  Main Turbine Control and Diagnostic System .................................................... C-334 2.5.11  Meteorological and Environmental Monitoring System ...................................... C-334 2.5.12  Closed Circuit TV System .................................................................................. C-334 2.6    Electrical Power Systems ......................................................................................... C-335 2.6.1    Main ac Power System ...................................................................................... C-335 2.6.01.01...................................................................................................................... C-340 2.6.01.02.i .................................................................................................................... C-340 2.6.01.02.ii ................................................................................................................... C-340 2.6.01.02.iii .................................................................................................................. C-340 2.6.01.03a.................................................................................................................... C-340 2.6.01.03b.................................................................................................................... C-340 2.6.01.04a.................................................................................................................... C-340 2.6.01.04b.................................................................................................................... C-340 2.6.01.04c .................................................................................................................... C-341 2.6.01.04d.................................................................................................................... C-341 2.6.01.04e.................................................................................................................... C-341 2.6.01.04f..................................................................................................................... C-341 2.6.01.05...................................................................................................................... C-341 2.6.01.06...................................................................................................................... C-341 C-20
 
2.6.2    Non-Class 1E dc and Uninterruptible Power Supply System ............................. C-347 2.6.02.01...................................................................................................................... C-347 2.6.02.02a.................................................................................................................... C-347 2.6.02.02b.................................................................................................................... C-347 2.6.02.02c .................................................................................................................... C-348 2.6.3    Class 1E dc and Uninterruptible Power Supply System ..................................... C-351 2.6.03.01...................................................................................................................... C-356 2.6.03.02.i .................................................................................................................... C-356 2.6.03.02.ii ................................................................................................................... C-356 2.6.03.02.iii .................................................................................................................. C-357 2.6.03.03...................................................................................................................... C-357 2.6.03.04a.................................................................................................................... C-357 2.6.03.04b.................................................................................................................... C-357 2.6.03.04c .................................................................................................................... C-357 2.6.03.04d.................................................................................................................... C-358 2.6.03.04e.................................................................................................................... C-358 2.6.03.04f..................................................................................................................... C-358 2.6.03.04g .................................................................................................................... C-358 2.6.03.04h.................................................................................................................... C-359 2.6.03.04i ..................................................................................................................... C-359 2.6.03.05a.................................................................................................................... C-359 2.6.03.05b.................................................................................................................... C-359 2.6.03.05c .................................................................................................................... C-359 2.6.03.05d.i .................................................................................................................. C-359 2.6.03.05d.ii ................................................................................................................. C-359 2.6.03.06...................................................................................................................... C-360 2.6.03.07...................................................................................................................... C-360 2.6.03.08...................................................................................................................... C-360 2.6.03.09...................................................................................................................... C-360 2.6.03.10...................................................................................................................... C-361 2.6.03.11...................................................................................................................... C-361 2.6.4    Onsite Standby Power System .......................................................................... C-368 2.6.04.01...................................................................................................................... C-369 2.6.04.02a.................................................................................................................... C-369 C-21
 
2.6.04.02b.................................................................................................................... C-369 2.6.04.02c .................................................................................................................... C-369 2.6.04.03...................................................................................................................... C-369 2.6.04.04...................................................................................................................... C-369 2.6.5    Lighting System ................................................................................................. C-371 2.6.05.01...................................................................................................................... C-372 2.6.05.02.i .................................................................................................................... C-372 2.6.05.02.ii ................................................................................................................... C-372 2.6.05.03.i .................................................................................................................... C-372 2.6.05.03.ii ................................................................................................................... C-372 2.6.05.04...................................................................................................................... C-372 2.6.05.05.i .................................................................................................................... C-373 2.6.05.05.ii ................................................................................................................... C-373 2.6.05.06.i .................................................................................................................... C-373 2.6.05.06.ii ................................................................................................................... C-373 2.6.6    Grounding and Lightning Protection System...................................................... C-374 2.6.06.01.i .................................................................................................................... C-375 2.6.06.01.ii ................................................................................................................... C-375 2.6.06.01.iii .................................................................................................................. C-376 2.6.06.01.iv .................................................................................................................. C-376 2.6.7    Special Process Heat Tracing System ............................................................... C-377 2.6.8    Cathodic Protection System .............................................................................. C-377 2.6.9    Plant Security System ....................................................................................... C-377 2.6.09.01...................................................................................................................... C-378 2.6.09.03...................................................................................................................... C-379 2.6.09.04...................................................................................................................... C-379 2.6.09.05a.................................................................................................................... C-379 2.6.09.05b.................................................................................................................... C-379 2.6.09.05c .................................................................................................................... C-379 2.6.09.06...................................................................................................................... C-380 2.6.09.07a.................................................................................................................... C-380 2.6.09.07b.................................................................................................................... C-380 2.6.09.08...................................................................................................................... C-380 2.6.09.09...................................................................................................................... C-380 C-22
 
2.6.09.13a.................................................................................................................... C-380 2.6.09.13b.................................................................................................................... C-380 2.6.09.13c .................................................................................................................... C-381 2.6.09.15a.................................................................................................................... C-381 2.6.09.15b.................................................................................................................... C-381 2.6.09.16...................................................................................................................... C-381 C.2.6.9    Physical Security ........................................................................................... C-382 C.2.6.09.01 .................................................................................................................. C-382 C.2.6.09.02 .................................................................................................................. C-382 C.2.6.09.03a ................................................................................................................ C-382 C.2.6.09.03b ................................................................................................................ C-382 C.2.6.09.04a ................................................................................................................ C-383 C.2.6.09.04b ................................................................................................................ C-383 C.2.6.09.05a ................................................................................................................ C-383 C.2.6.09.05b ................................................................................................................ C-383 C.2.6.09.06 .................................................................................................................. C-383 C.2.6.09.07 .................................................................................................................. C-383 C.2.6.09.08a ................................................................................................................ C-384 C.2.6.09.08b ................................................................................................................ C-384 C.2.6.09.09 .................................................................................................................. C-384 2.6.10  Main Generation System ................................................................................... C-385 2.6.11  Excitation and Voltage Regulation System ........................................................ C-385 C.2.6.12  Transmission Switchyard and Offsite Power System ..................................... C-385 C.2.6.12.01 .................................................................................................................. C-385 C.2.6.12.02 .................................................................................................................. C-385 C.2.6.12.03 .................................................................................................................. C-385 C.2.6.12.04 .................................................................................................................. C-385 C.2.6.12.05 .................................................................................................................. C-386 C.2.6.12.06 .................................................................................................................. C-386 C.2.6.12.07.i ................................................................................................................ C-387 C.2.6.12.07.ii................................................................................................................ C-388 2.6.13 Offsite Retail Power System ................................................................................. C-388 2.7    HVAC Systems......................................................................................................... C-389 2.7.1    Nuclear Island Nonradioactive Ventilation System ............................................. C-389 C-23
 
2.7.01.01...................................................................................................................... C-394 2.7.01.02a.................................................................................................................... C-394 2.7.01.02b.................................................................................................................... C-394 2.7.01.03a.................................................................................................................... C-394 2.7.01.03b.................................................................................................................... C-395 2.7.01.04a.................................................................................................................... C-395 2.7.01.04b.................................................................................................................... C-395 2.7.01.05.i .................................................................................................................... C-395 2.7.01.05.ii ................................................................................................................... C-395 2.7.01.05.iii .................................................................................................................. C-395 2.7.01.06a.................................................................................................................... C-395 2.7.01.06b.................................................................................................................... C-396 2.7.01.07...................................................................................................................... C-396 2.7.01.08a.................................................................................................................... C-396 2.7.01.08b.................................................................................................................... C-396 2.7.01.08c .................................................................................................................... C-396 2.7.01.08d.................................................................................................................... C-396 2.7.01.09...................................................................................................................... C-396 2.7.01.10a.................................................................................................................... C-396 2.7.01.10b.................................................................................................................... C-396 2.7.01.11...................................................................................................................... C-396 2.7.01.12...................................................................................................................... C-397 2.7.01.13...................................................................................................................... C-397 2.7.01.14...................................................................................................................... C-397 2.7.2    Central Chilled Water System............................................................................ C-401 2.7.02.01...................................................................................................................... C-403 2.7.02.02...................................................................................................................... C-403 2.7.02.03a.................................................................................................................... C-403 2.7.02.03b.................................................................................................................... C-403 2.7.02.04...................................................................................................................... C-403 2.7.02.05...................................................................................................................... C-403 2.7.3    Annex/Auxiliary Building Nonradioactive Ventilation System ............................. C-407 2.7.03.01...................................................................................................................... C-408 2.7.03.02a.................................................................................................................... C-408 C-24
 
2.7.03.02b.................................................................................................................... C-408 2.7.03.03...................................................................................................................... C-408 2.7.03.04...................................................................................................................... C-408 2.7.4    Diesel Generator Building Ventilation System ................................................... C-412 2.7.04.01...................................................................................................................... C-413 2.7.04.02a.................................................................................................................... C-413 2.7.04.02b.................................................................................................................... C-413 2.7.04.02c .................................................................................................................... C-413 2.7.04.03...................................................................................................................... C-413 2.7.04.04...................................................................................................................... C-413 2.7.5    Radiologically Controlled Area Ventilation System ............................................ C-417 2.7.05.01...................................................................................................................... C-418 2.7.05.02.i .................................................................................................................... C-418 2.7.05.02.ii ................................................................................................................... C-418 2.7.05.02.iii .................................................................................................................. C-418 2.7.05.03...................................................................................................................... C-418 2.7.6    Containment Air Filtration System ..................................................................... C-420 2.7.06.01...................................................................................................................... C-421 2.7.06.02.i .................................................................................................................... C-421 2.7.06.02.ii ................................................................................................................... C-421 2.7.06.03.i .................................................................................................................... C-421 2.7.06.03.ii ................................................................................................................... C-421 2.7.06.03.iii .................................................................................................................. C-421 2.7.06.04...................................................................................................................... C-421 2.7.06.05...................................................................................................................... C-421 2.7.7    Containment Recirculation Cooling System ....................................................... C-424 2.7.07.01...................................................................................................................... C-424 2.7.07.02...................................................................................................................... C-424 2.7.8    Radwaste Building HVAC System ..................................................................... C-425 2.7.9    Turbine Island Building Ventilation System ........................................................ C-425 2.7.10  Health Physics and Hot Machine Shop HVAC System ...................................... C-425 2.7.11  Hot Water Heating System ................................................................................ C-425 3.0    Non-System Based Design Descriptions and ITAAC ................................................ C-426 3.1    Emergency Response Facilities ............................................................................ C-426 C-25
 
3.1.00.01...................................................................................................................... C-426 3.1.00.02...................................................................................................................... C-426 3.1.00.03...................................................................................................................... C-426 3.1.00.04...................................................................................................................... C-426 3.1.00.05...................................................................................................................... C-427 3.1.00.06...................................................................................................................... C-427 3.2    Human Factors Engineering ................................................................................. C-427 3.2.00.01a.................................................................................................................... C-429 3.2.00.01b.................................................................................................................... C-429 3.2.00.01c.i .................................................................................................................. C-429 3.2.00.01c.ii ................................................................................................................. C-430 3.2.00.01d.................................................................................................................... C-430 3.2.00.01e.................................................................................................................... C-430 3.2.00.02...................................................................................................................... C-431 3.2.00.03.i .................................................................................................................... C-431 3.2.00.03.ii ................................................................................................................... C-431 3.2.00.03.iii .................................................................................................................. C-431 3.2.00.03.iv .................................................................................................................. C-431 3.2.00.03.v ................................................................................................................... C-431 3.2.00.04...................................................................................................................... C-431 3.2.00.05...................................................................................................................... C-431 3.2.00.06.i .................................................................................................................... C-431 3.2.00.06.ii ................................................................................................................... C-431 3.2.00.06.iii .................................................................................................................. C-432 3.2.00.07...................................................................................................................... C-432 3.2.00.08...................................................................................................................... C-432 3.2.00.09...................................................................................................................... C-432 3.3  Buildings................................................................................................................... C-434 3.3.00.01...................................................................................................................... C-449 3.3.00.02a.i.a ............................................................................................................... C-449 3.3.00.02a.i.b ............................................................................................................... C-449 3.3.00.02a.i.c ............................................................................................................... C-450 3.3.00.02a.i.d ............................................................................................................... C-450 3.3.00.02a.ii.a .............................................................................................................. C-450 C-26
 
3.3.00.02a.ii.b .............................................................................................................. C-450 3.3.00.02a.ii.c .............................................................................................................. C-451 3.3.00.02a.ii.d .............................................................................................................. C-451 3.3.00.02a.ii.e .............................................................................................................. C-451 3.3.00.02a.ii.f ............................................................................................................... C-451 3.3.00.02b.................................................................................................................... C-451 3.3.00.02c .................................................................................................................... C-451 3.3.00.02d.................................................................................................................... C-452 3.3.00.02e.................................................................................................................... C-452 3.3.00.02f..................................................................................................................... C-452 3.3.00.02g .................................................................................................................... C-452 3.3.00.02h.................................................................................................................... C-452 3.3.00.03a.................................................................................................................... C-453 3.3.00.03b.................................................................................................................... C-453 3.3.00.03c .................................................................................................................... C-453 3.3.00.03d.................................................................................................................... C-453 3.3.00.04a.................................................................................................................... C-454 3.3.00.04b.................................................................................................................... C-454 3.3.00.04c .................................................................................................................... C-454 3.3.00.05a.................................................................................................................... C-454 3.3.00.05b.................................................................................................................... C-454 3.3.00.05c .................................................................................................................... C-455 3.3.00.06a.................................................................................................................... C-455 3.3.00.06b.................................................................................................................... C-455 3.3.00.07aa .................................................................................................................. C-455 3.3.00.07ab .................................................................................................................. C-455 3.3.00.07ac .................................................................................................................. C-456 3.3.00.07ba .................................................................................................................. C-456 3.3.00.07bb .................................................................................................................. C-456 3.3.00.07bc .................................................................................................................. C-456 3.3.00.07c.i.a ............................................................................................................... C-457 3.3.00.07c.i.b ............................................................................................................... C-457 3.3.00.07c.ii.a .............................................................................................................. C-457 3.3.00.07c.ii.b .............................................................................................................. C-457 C-27
 
3.3.00.07d.i .................................................................................................................. C-457 3.3.00.07d.ii.a .............................................................................................................. C-458 3.3.00.07d.ii.b .............................................................................................................. C-459 3.3.00.07d.ii.c .............................................................................................................. C-460 3.3.00.07d.iii.a ............................................................................................................. C-461 3.3.00.07d.iii.b ............................................................................................................. C-461 3.3.00.07d.iii.c.............................................................................................................. C-461 3.3.00.07d.iv.a ............................................................................................................. C-462 3.3.00.07d.iv.b ............................................................................................................. C-462 3.3.00.07d.iv.c ............................................................................................................. C-463 3.3.00.07d.v.a .............................................................................................................. C-463 3.3.00.07d.v.b .............................................................................................................. C-464 3.3.00.07d.v.c .............................................................................................................. C-464 3.3.00.07e.................................................................................................................... C-464 3.3.00.08...................................................................................................................... C-465 3.3.00.09...................................................................................................................... C-465 3.3.00.10.i .................................................................................................................... C-465 3.3.00.10.ii ................................................................................................................... C-465 3.3.00.10.iii .................................................................................................................. C-466 3.3.00.12...................................................................................................................... C-466 3.3.00.13...................................................................................................................... C-466 3.3.00.14...................................................................................................................... C-466 3.3.00.16...................................................................................................................... C-467 3.3.00.17...................................................................................................................... C-467 3.4  Initial Test Program .................................................................................................. C-469 3.5  Radiation Monitoring................................................................................................. C-469 3.5.00.01.i .................................................................................................................... C-473 3.5.00.01.ii ................................................................................................................... C-473 3.5.00.01.iii .................................................................................................................. C-473 3.5.00.02.i .................................................................................................................... C-473 3.5.00.02.ii ................................................................................................................... C-473 3.5.00.03...................................................................................................................... C-473 3.5.00.04...................................................................................................................... C-474 3.5.00.05...................................................................................................................... C-474 C-28
 
3.5.00.06...................................................................................................................... C-474 3.5.00.07...................................................................................................................... C-474 3.5.00.08...................................................................................................................... C-474 3.6  Reactor Coolant Pressure Boundary Leak Detection ................................................ C-476 3.6.00.01.i .................................................................................................................... C-476 3.6.00.01.ii ................................................................................................................... C-476 3.6.00.01.iii .................................................................................................................. C-477 3.6.00.01.iv .................................................................................................................. C-477 3.6.00.01.v ................................................................................................................... C-477 3.6.00.01.vi .................................................................................................................. C-477 3.6.00.01.vii ................................................................................................................. C-477 3.7  Design Reliability Assurance Program ...................................................................... C-478 3.7.00.01...................................................................................................................... C-484 C.3.8    Emergency Planning ITAAC ................................................................................. C-485 C.3.8.1.1      Emergency Classification System ....................................................... C-485 C.3.8.01.01.01 ............................................................................................................. C-485 C.3.8.01.01.02 ............................................................................................................. C-485 C.3.8.1.2      Notification Methods and Procedures ................................................. C-486 C.3.8.01.02.01 ............................................................................................................. C-486 C.3.8.01.02.02 ............................................................................................................. C-486 C.3.8.01.02.03 ............................................................................................................. C-486 C.3.8.1.3      Emergency Communications............................................................... C-487 C.3.8.01.03.01 ............................................................................................................. C-487 C.3.8.01.03.02 ............................................................................................................. C-487 C.3.8.1.4      Public Education and Information ....................................................... C-488 C.3.8.01.04.01 ............................................................................................................. C-488 C.3.8.1.5      Emergency Facilities and Equipment .................................................. C-488 C.3.8.01.05.01.01 ........................................................................................................ C-488 C.3.8.01.05.01.02 ........................................................................................................ C-488 C.3.8.01.05.01.03 ........................................................................................................ C-488 C.3.8.01.05.01.04 ........................................................................................................ C-489 C.3.8.01.05.01.05 ........................................................................................................ C-489 C.3.8.01.05.01.06 ........................................................................................................ C-489 C.3.8.01.05.01.07 ........................................................................................................ C-489 C-29
 
C.3.8.01.05.01.08 ........................................................................................................ C-489 C.3.8.01.05.02.01 ........................................................................................................ C-490 C.3.8.01.05.02.02 ........................................................................................................ C-490 C.3.8.01.05.02.03 ........................................................................................................ C-490 C.3.8.1.6      Accident Assessment ......................................................................... C-490 C.3.8.01.06.01 ............................................................................................................. C-490 C.3.8.01.06.02 ............................................................................................................. C-491 C.3.8.01.06.03 ............................................................................................................. C-491 C.3.8.01.06.04 ............................................................................................................. C-491 C.3.8.01.06.05 ............................................................................................................. C-491 C.3.8.01.06.06 ............................................................................................................. C-491 C.3.8.01.06.07 ............................................................................................................. C-491 C.3.8.01.06.08 ............................................................................................................. C-492 C.3.8.01.06.09 ............................................................................................................. C-492 C.3.8.1.7    Protective Response ............................................................................ C-493 C.3.8.01.07.01 ............................................................................................................. C-493 C.3.8.1.8      Exercises and Drills ............................................................................ C-494 C.3.8.01.08.01.01 ........................................................................................................ C-494 C.3.8.01.08.01.02 ........................................................................................................ C-501 C.3.8.01.08.01.03 ........................................................................................................ C-502 C.3.8.1.9    Implementing Procedures .................................................................... C-502 C.3.8.01.09.01 ............................................................................................................. C-502 C.3.8.2    Pipe Rupture Hazard Analysis ....................................................................... C-503 C.3.8.02.01 .................................................................................................................. C-503 C.3.8.3    Piping Design................................................................................................. C-504 C.3.8.03.01 .................................................................................................................. C-504 C.3.8.4    Waterproof Membrane ................................................................................... C-505 C.3.8.04.01 .................................................................................................................. C-505 C.3.8.5    Concrete Fill .................................................................................................. C-505 C.3.8.05.01 .................................................................................................................. C-505 C.3.8.05.02a ................................................................................................................ C-505 C.3.8.05.02b ................................................................................................................ C-505 C.3.8.6    Seismic Category I Structure Foundation Grouting ........................................ C-506 C.3.8.06.01.i ................................................................................................................ C-506 C-30
 
C.3.8.06.01.ii................................................................................................................ C-507  ....................................................................................................................... C-508 C-31
 
1.0            Introduction 1.1            Definitions The following definitions apply to terms used in the design descriptions and associated inspections, tests, analyses, and acceptance criteria (ITAAC).
Acceptance Criteria means the performance, physical condition, or analysis result for a structure, system, or component that demonstrates that the design or program commitment is met.
Analysis means a calculation, mathematical computation, or engineering or technical evaluation. Engineering or technical evaluations could include, but are not limited to, comparisons with operating experience or design of similar structures, systems, or components.
As-built means the physical properties of a structure, system, or component following the completion of its installation or construction activities at its final location at the plant site. In cases where it is technically justifiable, determination of physical properties of the as-built structure, system, or component may be based on measurements, inspections, or tests that occur prior to installation, provided that subsequent fabrication, handling, installation, and testing does not alter the properties.
Column Line is the designation applied to a plant reference grid used to define the location of building walls and columns. Column lines may not represent the center line of walls and columns.
Design Commitment means that portion of the design description that is verified by ITAAC.
Design Description means that portion of the design that is certified.
Design Plant Grade means the elevation of the soil around the nuclear island assumed in the design of the AP1000, i.e., floor elevation 100'-0".
Division (for electrical systems or electrical equipment) is the designation applied to a given safety-related system or set of components that is physically, electrically, and functionally independent from other redundant sets of components.
Floor Elevation is the designation applied to name a floor. The actual elevation may vary due to floor slope and layout requirements.
Functional Arrangement (for a system) means the physical arrangement of systems and components to provide the service for which the system is intended, and which is described in the system design description.
Inspect or Inspection means visual observations, physical examinations, or reviews of records based on visual observation or physical examination that compare a) the structure, system, or component condition to one or more design commitments or b) the program implementation C-32
 
elements to one or more program commitments, as applicable. Examples include walkdowns, configuration checks, measurements of dimensions, or nondestructive examinations.
Inspect for Retrievability of a display means to visually observe that the specified information appears on a monitor when summoned by the operator.
ITAAC Number is a unique number based on three character strings. The first string represents the source of the ITAAC where a C or E denotes the ITAAC source is from the combined license or early site permit respectively. No alpha character denotes the ITAAC source is from the design control document (DCD). The second string represents the chapter, section, and subsection where the ITAAC table is located within the source document and contains three or more numbers separated by decimals. If the source document is not numbered, the string is based on the ITAAC table number within this appendix. The third string identifies the location of the ITAAC within the table and will vary in length and composition based on the source table numbering convention.
La is the maximum allowable containment leakage as defined in 10 CFR 50 Appendix J.
Physical Arrangement (for a structure) means the arrangement of the building features (e.g.,
floors, ceilings, walls, and basemat) and of the structures, systems, and components within, which are described in the building design description.
Program Commitment means that portion of the program description that is verified by ITAAC.
The bracketed, alphanumerical designations included in the emergency planning ITAAC identify the evaluation criteria (i.e., program elements) from NUREG-0654/FEMA-REP-1 Planning Standards that were used to develop the specific generic ITAAC in NUREG-0800, Table 14.3.10-1.
Qualified for Harsh Environment means that equipment can withstand the environmental conditions that would exist before, during, and following a design basis accident without loss of its safety function, for the time required to perform the safety function. These environmental conditions include applicable time-dependent temperature and pressure profiles, humidity, chemical effects, radiation, aging, submergence, and their synergistic effects which have a significant effect on the equipment performance. Equipment identified in the Design Description as being Qualified for Harsh Environment includes the:
a) equipment itself b) sensors, switches and lubricants that are an integral part of the equipment c) electrical components connected to the equipment (wiring, cabling and terminations)
Items b and c are Qualified for Harsh Environment only when they are necessary to support operation of the equipment to meet its safety-related function listed in the Design Description table and to the extent such equipment is located in a harsh environment during or following a design basis accident.
Sensor means a transmitter, resistance temperature detector, thermocouple or other transducer, plus associated cables, connectors, preamplifiers, reference junction boxes, or other signal C-33
 
processing equipment that is located in the immediate proximity of the sensor and subject to the same environmental conditions.
Site Grade means the as-built elevation of the soil to the west side of the nuclear island.
Adjacent buildings are located on the other sides of the nuclear island.
Tag Number in the ITAACs represents the complete tag number or a portion of the tag number used to identify the actual hardware (or associated software). For instrumentation, the tag number identified in the ITAACs does not include the type of instrument (for example, the Containment Exhaust Fan A Flow Sensor, VFS-11A, does not include the designators FE [flow element] or FT [flow transmitter], which would appear on the actual hardware or in the associated software). This is because the designator VFS-11A and the equipment description are sufficient to uniquely identify the channel associated with the designated instrument function, and this method of identification eliminates the need to list every portion of the instrumentation channel required to perform the function. In most cases, the channel number includes physical hardware. There are, however, a few places where the channel number represents only a calculation in software. In those cases, the channel data can be displayed. In many instances, the word sensor is used in the equipment description to identify that the item is an instrument.
Test means the actuation, operation, or establishment of specified conditions to evaluate the performance or integrity of as-built structures, systems, or components, unless explicitly stated otherwise.
Transfer Open (Closed) means to move from a closed (open) position to an open (closed) position.
Type Test means a test on one or more sample components of the same type and manufacturer to qualify other components of the same type and manufacturer. A type test is not necessarily a test of the as-built structures, systems, or components.
UA of a heat exchanger means the product of the heat transfer coefficient and the surface area.
C-34
 
1.2              General Provisions The following general provisions are applicable to the design descriptions and associated ITAAC.
Treatment of Individual Items The absence of any discussion or depiction of an item in the design description or accompanying figures shall not be construed as prohibiting a licensee from utilizing such an item, unless it would prevent an item from performing its safety functions as discussed or depicted in the design description or accompanying figures.
If an inspections, tests, or analyses (ITA) requirement does not specify the temperature or other conditions under which a test must be run, then the test conditions are not constrained.
When the term "operate," "operates," or "operation" is used with respect to an item discussed in the acceptance criteria, it refers to the actuation and running of the item. When the term "exist,"
"exists," or "existence" is used with respect to an item discussed in the acceptance criteria, it means that the item is present and meets the design commitment.
Implementation of ITAAC The ITAAC are provided in tables with the following three-column format:
Design (or Program)            Inspections,                  Acceptance Commitment                      Tests, Analyses              Criteria Each design or program commitment in the left-hand column of the ITAAC tables has an associated ITA requirement specified in the middle column of the tables.
The identification of a separate ITA entry for each design or program commitment shall not be construed to require that separate inspections, tests, or analyses must be performed for each design or program commitment. Instead, the activities associated with more than one ITA entry may be combined, and a single inspection, test, or analysis may be sufficient to implement more than one ITA entry.
An ITA may be performed by the licensee of the plant or by its authorized vendors, contractors, or consultants. Furthermore, an ITA may be performed by more than a single individual or group, may be implemented through discrete activities separated by time, and may be performed at any time prior to fuel load (including before issuance of the combined license for those ITAACs that do not necessarily pertain to as-installed equipment). Additionally, an ITA may be performed as part of the activities that are required to be performed under 10 CFR Part 50 (including, for example, the quality assurance (QA) program required under Appendix B to Part 50); therefore, an ITA need not be performed as a separate or discrete activity.
C-35
 
Many of the acceptance criteria include the words A report exists and concludes that When these words are used, it indicates that the ITAAC for that design commitment will be met when it is confirmed that appropriate documentation exists and the documentation shows that the design commitment is met. Appropriate documentation can be a single document or a collection of documents that show that the stated acceptance criteria are met. Examples of appropriate documentation include design reports, test reports, inspection reports, analysis reports, evaluation reports, design and manufacturing procedures, certified data sheets, commercial dedication procedures and records, quality assurance records, calculation notes, and equipment qualification data packages. For plants at sites which are qualified using the hard rock high frequency (HRHF) ground motion response spectra (GMRS), high frequency seismic screening and qualification testing required as a result of the evaluation of potential high frequency sensitive components is included in the equipment qualification data packages.
Many entries in the ITA column of the ITAAC tables include the words Inspection will be performed for the existence of a report verifying When these words are used it indicates that the ITA is tests, type tests, analyses, or a combination of tests, type tests, and analyses and a report will be produced documenting the results. This report will be available to inspectors.
Many ITAAC are only a reference to another ITAAC location, either a section, subsection, or ITAAC table entry (for example, See ITAAC Table ). A reference to another ITAAC location is always in both the ITA and acceptance criteria columns for a design commitment. This reference is an indication that the ITA and acceptance criteria for that design commitment are satisfied when the referenced ITA are completed and the acceptance criteria for the referenced sections, subsections, or table entries are satisfied. If a complete section is referenced, this indicates that all the ITA and acceptance criteria in that section must be met before the referencing design commitment is satisfied.
Discussion of Matters Related to Operations In some cases, the design descriptions in this document refer to matters that relate to operation, such as normal valve or breaker alignment during normal operation modes. Such discussions are provided solely to place the design description provisions in context (for example, to explain automatic features for opening or closing valves or breakers upon off-normal conditions). Such discussions shall not be construed as requiring operators during operation to take any particular action (for example, to maintain valves or breakers in a particular position during normal operation).
Interpretation of Figures In many but not all cases, the design descriptions in Section 2 include one or more figures. The figures may represent a functional diagram, general structural representation, or another general illustration. For instrumentation and control (I&C) systems, figures may also represent aspects of the relevant logic of the system or part of the system. Unless specified explicitly, the figures are not indicative of the scale, location, dimensions, shape, or spatial relationships of as-built structures, systems, and components. In particular, the as-built attributes of structures, C-36
 
systems, and components may vary from the attributes depicted on the figures, provided that those safety functions discussed in the design description pertaining to the figure are not adversely affected.
C-37
 
1.3            Figure Legend The conventions used in this section are for figures described in the design description. The figure legend is provided for information.
C-38
 
C-39 C-40 MISCELLANEOUS A component that is part of the system functional arrangement shown on the figure and is included in the design commitments for the system.
A component that is part of the system functional arrangement shown on the figure.
A system or component of another system that is not part of the system functional arrangement shown on the figure.
A functional connection to another system that is not part of the system functional arrangement shown on the figure.
ASME CODE CLASS BREAK An ASME Code class break is identified by a single line to the designated location for the class break, as shown in the example below (see note 1).
NOTES:
: 1. The header, ASME Code Section III Class, must appear at least once on each figure on which ASME class breaks are shown, but need not appear at every class break shown on a figure.
Indicates Non-ASME Code Section III C-41
 
1.4          List of Acronyms and Abbreviations The acronyms presented in this section are provided for information.
ac          Alternating Current AC          Acceptance Criteria ADS          Automatic Depressurization System AHU          Air Handling Units ALARA        As Low As Reasonably Achievable ANS          Alert and Notification System ASME        American Society of Mechanical Engineers atm          Atmosphere BTU          British Thermal Unit CAS          Compressed and Instrument Air System CAV          Cumulative Absolute Velocity cc          Cubic Centimeter CCS          Component Cooling Water System CDE          Committed Dose Equivalent CDS          Condensate System cfm          Cubic Feet per Minute CFR          Code of Federal Regulations Ci          Curie CIM          Component Interface Module CMT          Core Makeup Tank CNS          Containment System COL          Combined Operating License/Combined License cpm          Counts Per Minute CR          Control Room CRDM        Control Rod Drive Mechanism CSA          Control Support Area CST          Condensate Storage Tank CVS          Chemical and Volume Control System CWS          Circulating Water System DAS          Diverse Actuation System DBT          Design Basis Threat dc          Direct Current DCD          Design Control Document DDS          Data Display and Processing System C-42
 
List of Acronyms and Abbreviations (cont.)
DOS          Standby Diesel Fuel Oil System D-RAP        Design Reliability Assurance Program DTS          Demineralized Water Treatment System DVI          Direct Vessel Injection DWS          Demineralized Water Transfer and Storage System EAL          Emergency Action Level EBF          Eccentrically Braced Framing ECS          Main ac Power System EDS          Non-Class 1E dc and Uninterruptible Power Supply System EFS          Communication System EGS          Grounding and Lightning Protection System EIP          Emergency Implementing Procedure El.          Elevation ELS          Plant Lighting System EMI          Electromagnetic Interference EOC          Emergency Operations Center EOF          Emergency Operations Facility EPA          Environmental Protection Agency EPZ          Emergency Planning Zone ERDS          Emergency Response Data System ERO          Emergency Response Organization ESD          Electrostatic Discharge F            Fahrenheit FE            Flow Element FHM          Fuel Handling Machine FHS          Fuel Handling and Refueling System FPS          Fire Protection System ft            Feet FT            Flow Transmitter FTS          Fuel Transfer System FWS          Main and Startup Feedwater System GRMS          Ground Motion Response Spectra gpm          Gallons per Minute GRCA          Grey Rod Cluster Assemblies GSU          Generator Stepup Transformer C-43
 
List of Acronyms and Abbreviations (cont.)
HEPA          High Efficiency Particulate Air HFE          Human Factors Engineering HL            Hot Leg hr            Hour HRHF          Hard Rock High frequency HSI          Human-System Interface HVAC          Heating, Ventilation, and Air Conditioning HX            Heat Exchanger Hz            Hertz I&C          Instrumentation and Control IDS          Class 1E dc and Uninterruptible Power Supply System IIS          In-core Instrumentation System in            Inches I&C          Instrumentation and Control IRC          Inside Reactor Containment IRWST        In-containment Refueling Water Storage Tank ITA          Inspections, Tests, Analyses ITAAC        Inspections, Tests, Analyses, and Acceptance Criteria JIC          Joint Information Center KI            Potassium Iodide kW            Kilowatt lb/hr        Pounds per Hour LBB          Leak Before Break LOCA          Loss of Coolant Accident LTOP          Low Temperature Overpressure Protection m            Meters MBtu          Million British Thermal Units MCC          Motor Control Center MCR          Main Control Room MHS          Mechanical Handling System MOV          Motor-operated Valve MSIV          Main Steam Isolation Valve MSS          Main Steam System MTS          Main Turbine System MW            Megawatt MWe          Megawatt Electric C-44
 
List of Acronyms and Abbreviations (cont.)
MWt          Megawatt Thermal NI            Nuclear Island NRC          Nuclear Regulatory Commission, U.S.
OCS          Operation and Control Centers System ORC          Outside Reactor Containment OSC          Operations Support Center PAG          Protective Action Guide PAR          Protective Action Recommendation PCCAWST      Passive Containment Cooling Ancillary Water Storage Tank PCCWST        Passive Containment Cooling Water Storage Tank PCS          Passive Containment Cooling System PGS          Plant Gas System pH            Potential of Hydrogen PLS          Plant Control System PMS          Protection and Safety Monitoring System PORV          Power-operated Relief Valve PRHR          Passive Residual Heat Removal psia          Pounds per Square Inch Absolute psig          Pounds per Square Inch Gauge PSS          Primary Sampling System pu            Per Unit PWS          Potable Water System PXS          Passive Core Cooling System QA            Quality Assurance R/hr          Roentgen per Hour RAP          Reliability Assurance Program RAT          Reserve Auxiliary Transformer RC            Reinforced Concrete RCCA          Rod Cluster Control Assembly RCDT          Reactor Coolant Drain Tank RCP          Reactor Coolant Pump RCS          Reactor Coolant System RFI          Radio Frequency Interference RM            Refueling Machine RMS          Radiation Monitoring System C-45
 
List of Acronyms and Abbreviations (cont.)
RNS          Normal Residual Heat Removal System RP            Radiation Protection RPV          Reactor Pressure Vessel RSR          Remote Shutdown Room RSW          Remote Shutdown Workstation RTD          Resistance Temperature Detector RXS          Reactor System RV            Reactor Vessel SC            Steel and Concrete scf          Standard Cubic Feet scfm          Standard Cubic Feet per Minute SDS          Sanitary Drainage System SFHT          Spent Fuel Handling Tool SFP          Spent Fuel Pool SFS          Spent Fuel Pool Cooling System SG            Steam Generator SGS          Steam Generator System SJS          Seismic Monitoring System SMS          Special Monitoring System SSCs          Structures, Systems, and Components SSE          Safe Shutdown Earthquake SWC          Surge Withstand Capability SWS          Service Water System TEDE          Total Effective Dose Equivalent TSC          Technical Support Center UAT          Unit Auxiliary Transformer UPS          Uninterruptible Power Supply V            Volt VAS          Radiologically Controlled Area Ventilation System VBS          Nuclear Island Nonradioactive Ventilation System VCS          Containment Recirculation Cooling System Vdc          Direct Current Voltage VES          Main Control Room Emergency Habitability System VFS          Containment Air Filtration System VHS          Health Physics and Hot Machine Shop Areas VLS          Containment Hydrogen Control System C-46
 
List of Acronyms and Abbreviations (cont.)
VRS          Radwaste Building HVAC System VWS          Central Chilled Water System VXS          Annex/Auxiliary Building Nonradioactive Ventilation System VZS          Diesel Generator Building Ventilation System wg            Water Gauge WGS          Gaseous Radwaste System WLS          Liquid Radwaste System WSS          Solid Radwaste System WWS          Waste Water System WRS          Radioactive Waste Drain System ZOI          Zone of Influence ZOS          Onsite Standby Power System C-47
 
2.0            System Based Design Descriptions and ITAAC 2.1            Reactor 2.1.1          Fuel Handling and Refueling System Design Description The fuel handling and refueling system (FHS) transfers fuel assemblies and core components during fueling operations and stores new and spent fuel assemblies in the new and spent fuel storage racks. The refueling machine (RM) and the fuel transfer tube are operated during refueling mode. The fuel handling machine (FHM) is operated during normal modes of plant operation, including startup, power operation, cooldown, shutdown and refueling.
The component locations of the FHS are as shown in Table 2.1.1-2.
: 1. The functional arrangement of the FHS is as described in the Design Description of this Section 2.1.1.
: 2. The FHS has the RM, the FHM, and the new and spent fuel storage racks.
: 3. The FHS preserves containment integrity by isolation of the fuel transfer tube penetrating containment.
: 4. The RM and FHM/spent fuel handling tool (SFHT) gripper assemblies are designed to prevent opening while the weight of the fuel assembly is suspended from the grippers.
: 5. The lift height of the RM mast and FHM hoist(s) is limited such that the minimum required depth of water shielding is maintained.
: 6. The RM and FHM are designed to maintain their load carrying and structural integrity functions during a safe shutdown earthquake.
: 7. The new and spent fuel storage racks maintain the effective neutron multiplication factor required by 10 CFR 50.68 limits during normal operation, design basis seismic events, and design basis dropped spent fuel assembly accidents over the spent fuel storage racks.
C-48
 
Table 2.1.1-1 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No.                Design Commitment                    Inspections, Tests, Analyses      Acceptance Criteria 1    2.1.01.01  1. The functional arrangement of the FHS        Inspection of the as-built      The as-built FHS conforms is as described in the Design Description of    system will be performed.      with the functional this Section 2.1.1.                                                              arrangement as described in the Design Description of this Section 2.1.1.
2    2.1.01.02  2. The FHS has the refueling machine            Inspection of the system will  The FHS has the RM, the (RM), the fuel handling machine (FHM),          be performed.                  FHM, and the new and spent and the new and spent fuel storage racks.                                        fuel storage racks.
3    2.1.01.03  3. The FHS preserves containment                See ITAAC Table 2.2.1-3,        See ITAAC Table 2.2.1-3, integrity by isolation of the fuel transfer      items 1 and 7.                  items 1 and 7.
tube penetrating containment.
4    2.1.01.04  4. The RM and FHM/spent fuel handling            The RM and FHM/SFHT            The RM and FHM/SFHT tool (SFHT) gripper assemblies are              gripper assemblies will be      gripper assemblies will not designed to prevent opening while the            tested by operating the open    open while suspending a weight of the fuel assembly is suspended        controls of the gripper while  dummy test assembly.
from the grippers.                              suspending a dummy fuel assembly.
5    2.1.01.05  5. The lift height of the RM mast and            The RM and FHM will be          The bottom of the dummy FHM hoist(s) is limited such that the            tested by attempting to raise a fuel assembly cannot be minimum required depth of water shielding        dummy fuel assembly.            raised to within 24 ft, 6 in.
is maintained.                                                                  of the operating deck floor.
6  2.1.01.06.i  6. The RM and FHM are designed to                i) Inspection will be          i) The RM and FHM are maintain their load carrying and structural      performed to verify that the    located on the nuclear integrity functions during a safe shutdown      RM and FHM are located on      island.
earthquake.                                      the nuclear island.
7  2.1.01.06.ii 6. The RM and FHM are designed to                ii) Type test, analysis, or a  ii) A report exists and maintain their load carrying and structural      combination of type tests and  concludes that the RM and integrity functions during a safe shutdown      analyses of the RM and FHM      FHM can withstand seismic earthquake.                                      will be performed.              design basis dynamic loads without loss of load carrying or structural integrity functions.
8  2.1.01.07.i  7. The new and spent fuel storage racks          i) Analyses will be performed  i) The calculated effective maintain the effective neutron                  to calculate the effective      neutron multiplication factor multiplication factor required by 10 CFR        neutron multiplication factor  for the new and spent fuel 50.68 limits during normal operation,            in the new and spent fuel      storage racks meets the design basis seismic events, and design          storage racks during normal    requirements of basis dropped spent fuel assembly                conditions.                    10 CFR 50.68(1) limits under accidents over the spent fuel storage racks.                                    normal conditions.
9  2.1.01.07.ii 7. The new and spent fuel storage racks          ii) Inspection will be          ii) The new and spent fuel maintain the effective neutron                  performed to verify that the    storage racks are located on multiplication factor required by 10 CFR        new and spent fuel storage      the nuclear island.
50.68 limits during normal operation, C-49
 
Table 2.1.1-1 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No.                  Design Commitment                    Inspections, Tests, Analyses      Acceptance Criteria design basis seismic events, and design        racks are located on the basis dropped spent fuel assembly              nuclear island.
accidents over the spent fuel storage racks.
10    2.1.01.07.iii  7. The new and spent fuel storage racks        iii) Seismic analysis of the  iii) A report exists and maintain the effective neutron                new and spent fuel storage    concludes that the new and multiplication factor required by 10 CFR      racks will be performed.      spent fuel racks can 50.68 limits during normal operation,                                        withstand seismic design design basis seismic events, and design                                      basis dynamic loads and basis dropped spent fuel assembly                                            maintain the calculated accidents over the spent fuel storage racks.                                  effective neutron multiplication factor required by 10 CFR 50.68(1) limits.
11    2.1.01.07.iv    7. The new and spent fuel storage racks        iv) Analysis of the new and    iv) A report exists and maintain the effective neutron                spent fuel storage racks under concludes that the new and multiplication factor required by 10 CFR      design basis dropped spent    spent fuel racks can 50.68 limits during normal operation,          fuel assembly loads will be    withstand design basis design basis seismic events, and design        performed.                    dropped spent fuel assembly basis dropped spent fuel assembly                                            loads and maintain the accidents over the spent fuel storage racks.                                  calculated effective neutron multiplication factor required by 10 CFR 50.68(1) limits.
Note:
: 1. The requirements of 10 CFR 50.68 are summarized as follows:
* For new fuel storage racks:
        - The effective neutron multiplication factor (K-effective) must not exceed 0.95 when flooded with unborated water and
        - K-effective must not exceed 0.98 with optimum moderator conditions.
* For spent fuel storage racks:
        - If methodology does not take credit for soluble boron:
* K-effective must not exceed 0.95 when flooded with unborated water.
        - Or if methodology takes credit for soluble boron:
* K-effective must not exceed 0.95 when flooded with borated water and
* K-effective must remain below 1.0 when flooded with unborated water.
C-50
 
Table 2.1.1-2 Component Name  Tag No.        Component Location Refueling Machine        FHS-FH-01              Containment Fuel Handling Machine    FHS-FH-02          Auxiliary Building Spent Fuel Storage Racks FHS-FS-02          Auxiliary Building New Fuel Storage Racks  FHS-FS-01          Auxiliary Building Fuel Transfer Tube      FHS-FT-01    Auxiliary Building/Containment C-51
 
2.1.2          Reactor Coolant System Design Description The reactor coolant system (RCS) removes heat from the reactor core and transfers it to the secondary side of the steam generators for power generation. The RCS contains two vertical U-tube steam generators, four sealless reactor coolant pumps (RCPs), and one pressurizer.
The RCS is as shown in Figure 2.1.2-1 and the component locations of the RCS are as shown in Table 2.1.2-5.
: 1. The functional arrangement of the RCS is as described in the Design Description of this Section 2.1.2.
: 2. a) The components identified in Table 2.1.2-1 as ASME Code Section III are designed and constructed in accordance with ASME Code Section III requirements.
b) The piping identified in Table 2.1.2-2 as ASME Code Section III is designed and constructed in accordance with ASME Code Section III requirements.
: 3. a) Pressure boundary welds in components identified in Table 2.1.2-1 as ASME Code Section III meet ASME Code Section III requirements.
b) Pressure boundary welds in piping identified in Table 2.1.2-2 as ASME Code Section III meet ASME Code Section III requirements.
: 4. a) The components identified in Table 2.1.2-1 as ASME Code Section III retain their pressure boundary integrity at their design pressure.
b) The piping identified in Table 2.1.2-2 as ASME Code Section III retains its pressure boundary integrity at its design pressure.
: 5. a) The seismic Category I equipment identified in Table 2.1.2-1 can withstand seismic design basis loads without loss of safety function.
b) Each of the lines identified in Table 2.1.2-2 for which functional capability is required is designed to withstand combined normal and seismic design basis loads without a loss of its functional capability.
: 6. Each of the as-built lines identified in Table 2.1.2-2 as designed for leak before break (LBB) meets the LBB criteria, or an evaluation is performed of the protection from the dynamic effects of a rupture of the line.
: 7. a) The Class 1E equipment identified in Table 2.1.2-1 as being qualified for a harsh environment can withstand the environmental conditions that would exist before, during, and following a design basis accident without loss of safety function for the time required to perform the safety function.
C-52
 
b) The Class 1E components identified in Table 2.1.2-1 are powered from their respective Class 1E division.
c) Separation is provided between RCS Class 1E divisions, and between Class 1E divisions and non-Class 1E cable.
: 8. The RCS provides the following safety-related functions:
a) The pressurizer safety valves provide overpressure protection in accordance with Section III of the ASME Boiler and Pressure Vessel Code.
b) The reactor coolant pumps (RCPs) have a rotating inertia to provide RCS flow coastdown on loss of power to the pumps.
c) Each RCP flywheel assembly can withstand a design overspeed condition.
d) The RCS provides automatic depressurization during design basis events.
e) The RCS provides emergency letdown during design basis events.
: 9. The RCS provides the following nonsafety-related functions:
a) The RCS provides circulation of coolant to remove heat from the core.
b) The RCS provides the means to control system pressure.
c) The pressurizer heaters trip after a signal is generated by the PMS.
: 10. Safety-related displays identified in Table 2.1.2-1 can be retrieved in the main control room (MCR).
: 11. a) Controls exist in the MCR to cause the remotely operated valves identified in Table 2.1.2-1 to perform active functions.
b) The valves identified in Table 2.1.2-1 as having protection and safety monitoring system (PMS) control perform an active safety function after receiving a signal from the PMS.
c) The valves identified in Table 2.1.2-1 as having diverse actuation system (DAS) control perform an active safety function after receiving a signal from DAS.
: 12. a) The valves identified in Table 2.1.2-1 perform an active safety-related function to change position as indicated in the table.
b) After loss of motive power, the remotely operated valves identified in Table 2.1.2-1 assume the indicated loss of motive power position.
: 13. a) Controls exist in the MCR to trip the RCPs.
b) The RCPs trip after receiving a signal from the PMS.
c) The RCPs trip after receiving a signal from the DAS.
C-53
: 14. Controls exist in the MCR to cause the components identified in Table 2.1.2-3 to perform the listed function.
: 15. Displays of the parameters identified in Table 2.1.2-3 can be retrieved in the MCR.
Table 2.1.2-1 ASME                          Class 1E/                                Loss of Code              Remotely    Qual. for  Safety-    Control            Motive Section Seismic    Operated      Harsh    Related      PMS/    Active    Power Equipment Name              Tag No.      III    Cat. I      Valve      Envir. Display      DAS    Function  Position Steam Generator 1            RCS-MB-01    Yes      Yes          -          -/-        -          -        -      -
Steam Generator 2            RCS-MB-02    Yes      Yes          -          -/-        -          -        -      -
RCP 1A                      RCS-MP-01A    Yes      Yes          -        No/No        No      Yes/Yes    No        -
(pump trip)
RCP 1B                      RCS-MP-01B    Yes      Yes          -        No/No        No      Yes/Yes    No        -
(pump trip)
RCP 2A                      RCS-MP-02A    Yes      Yes          -        No/No        No      Yes/Yes    No        -
(pump trip)
RCP 2B                      RCS-MP-02B    Yes      Yes          -        No/No        No      Yes/Yes    No        -
(pump trip)
Pressurizer                  RCS-MV-02    Yes      Yes          -        No/No        -      Yes/No      No        -
(heaters)              (heater trip)
Automatic                  PXS-MW-01A    Yes      Yes          -          -/-        -        -/-        -      -
Depressurization System (ADS)
Sparger A ADS Sparger B              PXS-MW-01B    Yes      Yes          -          -/-        -        -/-        -      -
Pressurizer Safety        RCS-PL-V005A    Yes      Yes        No          -/-        No        -/-    Transfer    -
Valve                                                                                                    Open/
Transfer Closed Pressurizer Safety        RCS-PL-V005B    Yes      Yes        No          -/-        No        -/-    Transfer    -
Valve                                                                                                    Open/
Transfer Closed First-stage ADS            RCS-PL-V001A    Yes      Yes        Yes      Yes/Yes      Yes      Yes/Yes  Transfer  As Is Motor-operated Valve                                                                (Valve              Open (MOV)                                                                              Position)
C-54
 
Table 2.1.2-1 ASME                          Class 1E/                              Loss of Code            Remotely    Qual. for  Safety-  Control          Motive Section Seismic  Operated    Harsh    Related    PMS/    Active    Power Equipment Name        Tag No.      III    Cat. I    Valve      Envir. Display    DAS    Function  Position First-stage ADS MOV  RCS-PL-V001B  Yes    Yes        Yes      Yes/Yes    Yes    Yes/Yes  Transfer  As Is (Valve            Open Position)
Second-stage ADS      RCS-PL-V002A  Yes    Yes        Yes      Yes/Yes    Yes    Yes/Yes  Transfer  As Is MOV                                                                          (Valve            Open Position)
Second-stage ADS      RCS-PL-V002B  Yes    Yes        Yes      Yes/Yes    Yes    Yes/Yes  Transfer  As Is MOV                                                                          (Valve            Open Position)
Third-stage ADS      RCS-PL-V003A  Yes    Yes        Yes      Yes/Yes    Yes    Yes/Yes  Transfer  As Is MOV                                                                          (Valve            Open Position)
Third-stage ADS      RCS-PL-V003B  Yes    Yes        Yes      Yes/Yes  Yes (Valve Yes/Yes  Transfer  As Is MOV                                                                        Position)          Open Fourth-stage ADS      RCS-PL-V004A  Yes    Yes        Yes      Yes/Yes  Yes (Valve Yes/Yes  Transfer  As Is Squib Valve                                                                Position)          Open Fourth-stage ADS      RCS-PL-V004B  Yes    Yes        Yes      Yes/Yes  Yes (Valve Yes/Yes  Transfer  As Is Squib Valve                                                                Position)          Open Fourth-stage ADS      RCS-PL-V004C  Yes    Yes        Yes      Yes/Yes  Yes (Valve Yes/Yes  Transfer  As Is Squib Valve                                                                Position)          Open Fourth-stage ADS      RCS-PL-V004D  Yes    Yes        Yes      Yes/Yes  Yes (Valve Yes/Yes  Transfer  As Is Squib Valve                                                                Position)          Open ADS Discharge Header  RCS-PL-V010A  Yes    Yes        No      Yes/Yes      No      No/No  Transfer    -
A Vacuum Relief Valve                                                                          Open ADS Discharge Header  RCS-PL-V010B  Yes    Yes        No      Yes/Yes      No      No/No  Transfer    -
B Vacuum Relief Valve                                                                          Open First-stage ADS      RCS-PL-V011A  Yes    Yes        Yes      Yes/Yes  Yes (Valve Yes/Yes  Transfer  As Is Isolation MOV                                                              Position)          Open First-stage ADS      RCS-PL-V011B  Yes    Yes        Yes      Yes/Yes  Yes (Valve Yes/Yes  Transfer  As Is Isolation MOV                                                              Position)          Open Second-stage ADS      RCS-PL-V012A  Yes    Yes        Yes      Yes/Yes  Yes (Valve Yes/Yes  Transfer  As Is Isolation MOV                                                              Position)          Open Second-stage ADS      RCS-PL-V012B  Yes    Yes        Yes      Yes/Yes  Yes (Valve Yes/Yes  Transfer  As Is Isolation MOV                                                              Position)          Open Third-stage ADS      RCS-PL-V013A  Yes    Yes        Yes      Yes/Yes  Yes (Valve Yes/Yes  Transfer  As Is Isolation MOV                                                              Position)          Open Third-stage ADS      RCS-PL-V013B  Yes    Yes        Yes      Yes/Yes  Yes (Valve Yes/Yes  Transfer  As Is Isolation MOV                                                              Position)          Open Fourth-stage ADS      RCS-PL-V014A  Yes    Yes        Yes      Yes/Yes  Yes (Valve Yes/No    None      As Is MOV                                                                        Position)
Fourth-stage ADS      RCS-PL-V014B  Yes    Yes        Yes      Yes/Yes  Yes (Valve Yes/No    None      As Is MOV                                                                        Position)
C-55
 
Table 2.1.2-1 ASME                          Class 1E/                              Loss of Code            Remotely    Qual. for  Safety-  Control          Motive Section Seismic  Operated    Harsh    Related    PMS/    Active    Power Equipment Name      Tag No. III    Cat. I    Valve      Envir. Display    DAS    Function  Position Fourth-stage ADS    RCS-PL-V014C  Yes    Yes        Yes      Yes/Yes  Yes (Valve Yes/No    None      As Is MOV                                                                      Position)
Fourth-stage ADS    RCS-PL-V014D  Yes    Yes        Yes      Yes/Yes  Yes (Valve Yes/No    None      As Is MOV                                                                      Position)
Reactor Vessel Head RCS-PL-V150A  Yes    Yes        Yes      Yes/Yes  Yes (Valve Yes/No  Transfer  Closed Vent Valve                                                                Position)          Open Reactor Vessel Head RCS-PL-V150B  Yes    Yes        Yes      Yes/Yes  Yes (Valve Yes/No  Transfer  Closed Vent Valve                                                                Position)          Open Reactor Vessel Head RCS-PL-V150C  Yes    Yes        Yes      Yes/Yes  Yes (Valve Yes/No  Transfer  Closed Vent Valve                                                                Position)          Open Reactor Vessel Head RCS-PL-V150D  Yes    Yes        Yes      Yes/Yes  Yes (Valve Yes/No  Transfer  Closed Vent Valve                                                                Position)          Open RCS Hot Leg 1        RCS-101A      -      Yes          -      Yes/No      No        -/-      -        -
Flow Sensor RCS Hot Leg 1        RCS-101B      -      Yes          -      Yes/No      No        -/-      -        -
Flow Sensor RCS Hot Leg 1        RCS-101C      -      Yes          -      Yes/No      No        -/-      -        -
Flow Sensor RCS Hot Leg 1        RCS-101D      -      Yes          -      Yes/No      No        -/-      -        -
Flow Sensor RCS Hot Leg 2        RCS-102A      -      Yes          -      Yes/No      No        -/-      -        -
Flow Sensor RCS Hot Leg 2        RCS-102B      -      Yes          -      Yes/No      No        -/-      -        -
Flow Sensor RCS Hot Leg 2        RCS-102C      -      Yes          -      Yes/No      No        -/-      -        -
Flow Sensor RCS Hot Leg 2        RCS-102D      -      Yes          -      Yes/No      No        -/-      -        -
Flow Sensor RCS Cold Leg 1A      RCS-121A      -      Yes          -      Yes/Yes    No        -/-      -        -
Narrow Range Temperature Sensor RCS Cold Leg 1B      RCS-121B      -      Yes          -      Yes/Yes    No        -/-      -        -
Narrow Range Temperature Sensor RCS Cold Leg 1B      RCS-121C      -      Yes          -      Yes/Yes    No        -/-      -        -
Narrow Range Temperature Sensor RCS Cold Leg 1A      RCS-121D      -      Yes          -      Yes/Yes    No        -/-      -        -
Narrow Range Temperature Sensor C-56
 
Table 2.1.2-1 ASME                          Class 1E/                            Loss of Code            Remotely    Qual. for  Safety-  Control          Motive Section Seismic  Operated    Harsh    Related    PMS/    Active  Power Equipment Name    Tag No. III    Cat. I    Valve      Envir. Display    DAS    Function Position RCS Cold Leg 2B    RCS-122A    -      Yes          -      Yes/Yes    No      -/-      -        -
Narrow Range Temperature Sensor RCS Cold Leg 2A    RCS-122B    -      Yes          -      Yes/Yes    No      -/-      -        -
Narrow Range Temperature Sensor RCS Cold Leg 2A    RCS-122C    -      Yes          -      Yes/Yes    No      -/-      -        -
Narrow Range Temperature Sensor RCS Cold Leg 2B    RCS-122D    -      Yes          -      Yes/Yes    No      -/-      -        -
Narrow Range Temperature Sensor RCS Cold Leg 1A    RCS-125A    -      Yes          -      Yes/Yes  Yes (Wide  -/-      -        -
Dual Range                                                          Range)
Temperature Sensor RCS Cold Leg 2A    RCS-125B    -      Yes          -      Yes/Yes  Yes (Wide  -/-      -        -
Dual Range                                                          Range)
Temperature Sensor RCS Cold Leg 1B    RCS-125C    -      Yes          -      Yes/Yes  Yes (Wide  -/-      -        -
Dual Range                                                            Range Temperature Sensor RCS Cold Leg 2B    RCS-125D    -      Yes          -      Yes/Yes  Yes (Wide  -/-      -        -
Dual Range                                                          Range)
Temperature Sensor RCS Hot Leg 1      RCS-131A    -      Yes          -      Yes/Yes    No      -/-      -        -
Narrow Range Temperature Sensor RCS Hot Leg 2      RCS-131B    -      Yes          -      Yes/Yes    No      -/-      -        -
Narrow Range Temperature Sensor RCS Hot Leg 1      RCS-131C    -      Yes          -      Yes/Yes    No      -/-      -        -
Narrow Range Temperature Sensor RCS Hot Leg 2      RCS-131D    -      Yes          -      Yes/Yes    No      -/-      -        -
Narrow Range Temperature Sensor RCS Hot Leg 1      RCS-132A    -      Yes          -      Yes/Yes    No      -/-      -        -
Narrow Range Temperature Sensor RCS Hot Leg 2      RCS-132B    -      Yes          -      Yes/Yes    No      -/-      -        -
Narrow Range Temperature Sensor RCS Hot Leg 1      RCS-132C    -      Yes          -      Yes/Yes    No      -/-      -        -
Narrow Range Temperature Sensor C-57
 
Table 2.1.2-1 ASME                          Class 1E/                          Loss of Code            Remotely    Qual. for Safety- Control          Motive Section Seismic  Operated    Harsh    Related  PMS/    Active  Power Equipment Name        Tag No. III    Cat. I    Valve      Envir. Display  DAS    Function Position RCS Hot Leg 2        RCS-132D    -      Yes          -      Yes/Yes    No      -/-      -        -
Narrow Range Temperature Sensor RCS Hot Leg 1        RCS-133A    -      Yes          -      Yes/Yes    No      -/-      -        -
Narrow Range Temperature Sensor RCS Hot Leg 2        RCS-133B    -      Yes          -      Yes/Yes    No      -/-      -        -
Narrow Range Temperature Sensor RCS Hot Leg 1        RCS-133C    -      Yes          -      Yes/Yes    No      -/-      -        -
Narrow Range Temperature Sensor RCS Hot Leg 2        RCS-133D    -      Yes          -      Yes/Yes    No      -/-      -        -
Narrow Range Temperature Sensor RCS Hot Leg 1 Wide    RCS-135A    -      Yes          -      Yes/Yes    Yes    -/-      -        -
Range Temperature Sensor RCS Hot Leg 2 Wide    RCS-135B    -      Yes          -      Yes/Yes    Yes    -/-      -        -
Range Temperature Sensor RCS Wide Range        RCS-140A    -      Yes          -      Yes/Yes    Yes    -/-      -        -
Pressure Sensor RCS Wide Range        RCS-140B    -      Yes          -      Yes/Yes    Yes    -/-      -        -
Pressure Sensor RCS Wide Range        RCS-140C    -      Yes          -      Yes/Yes    Yes    -/-      -        -
Pressure Sensor RCS Wide Range        RCS-140D    -      Yes          -      Yes/Yes    Yes    -/-      -        -
Pressure Sensor RCS Hot Leg 1 Level  RCS-160A    -      Yes          -      Yes/Yes    Yes    -/-      -        -
Sensor RCS Hot Leg 2 Level  RCS-160B    -      Yes          -      Yes/Yes    Yes    -/-      -        -
Sensor Passive Residual Heat  RCS-161    -      Yes          -      Yes/Yes    Yes    -/-      -        -
Removal (PRHR)
Return Line Temperature Sensor Pressurizer Pressure  RCS-191A    -      Yes          -      Yes/Yes    Yes    -/-      -        -
Sensor Pressurizer Pressure  RCS-191B    -      Yes          -      Yes/Yes    Yes    -/-      -        -
Sensor Pressurizer Pressure  RCS-191C    -      Yes          -      Yes/Yes    Yes    -/-      -        -
Sensor C-58
 
Table 2.1.2-1 ASME                          Class 1E/                          Loss of Code            Remotely    Qual. for Safety- Control          Motive Section Seismic  Operated    Harsh    Related  PMS/    Active  Power Equipment Name      Tag No. III    Cat. I    Valve      Envir. Display  DAS    Function Position Pressurizer Pressure RCS-191D    -      Yes          -      Yes/Yes    Yes    -/-      -        -
Sensor Pressurizer Level    RCS-193A    -      Yes          -      Yes/Yes    Yes    -/-      -        -
Reference Leg Temperature Sensor Pressurizer Level    RCS-193B    -      Yes          -      Yes/Yes    Yes    -/-      -        -
Reference Leg Temperature Sensor Pressurizer Level    RCS-193C    -      Yes          -      Yes/Yes    Yes    -/-      -        -
Reference Leg Temperature Sensor Pressurizer Level    RCS-193D    -      Yes          -      Yes/Yes    Yes    -/-      -        -
Reference Leg Temperature Sensor Pressurizer Level    RCS-195A    -      Yes          -      Yes/Yes    Yes    -/-      -        -
Sensor Pressurizer Level    RCS-195B    -      Yes          -      Yes/Yes    Yes    -/-      -        -
Sensor Pressurizer Level    RCS-195C    -      Yes          -      Yes/Yes    Yes    -/-      -        -
Sensor Pressurizer Level    RCS-195D    -      Yes          -      Yes/Yes    Yes    -/-      -        -
Sensor RCP 1A Bearing Water RCS-211A    -      Yes          -      Yes/Yes    No      -/-      -        -
Temperature Sensor RCP 1A Bearing Water RCS-211B    -      Yes          -      Yes/Yes    No      -/-      -        -
Temperature Sensor RCP 1A Bearing Water RCS-211C    -      Yes          -      Yes/Yes    No      -/-      -        -
Temperature Sensor RCP 1A Bearing Water RCS-211D    -      Yes          -      Yes/Yes    No      -/-      -        -
Temperature Sensor RCP 1B Bearing Water RCS-212A    -      Yes          -      Yes/Yes    No      -/-      -        -
Temperature Sensor RCP 1B Bearing Water RCS-212B    -      Yes          -      Yes/Yes    No      -/-      -        -
Temperature Sensor RCP 1B Bearing Water RCS-212C    -      Yes          -      Yes/Yes    No      -/-      -        -
Temperature Sensor RCP 1B Bearing Water RCS-212D    -      Yes          -      Yes/Yes    No      -/-      -        -
Temperature Sensor C-59
 
Table 2.1.2-1 ASME                          Class 1E/                                  Loss of Code              Remotely    Qual. for    Safety-    Control            Motive Section  Seismic  Operated    Harsh      Related    PMS/      Active  Power Equipment Name            Tag No.          III    Cat. I    Valve      Envir.      Display    DAS      Function Position RCP 2A Bearing Water      RCS-213A            -      Yes          -      Yes/Yes      No          -/-        -        -
Temperature Sensor RCP 2A Bearing Water      RCS-213B            -      Yes          -      Yes/Yes      No          -/-        -        -
Temperature Sensor RCP 2A Bearing Water      RCS-213C            -      Yes          -      Yes/Yes      No          -/-        -        -
Temperature Sensor RCP 2A Bearing Water      RCS-213D            -      Yes          -      Yes/Yes      No          -/-        -        -
Temperature Sensor RCP 2B Bearing Water      RCS-214A            -      Yes          -      Yes/Yes      No          -/-        -        -
Temperature Sensor RCP 2B Bearing Water      RCS-214B            -      Yes          -      Yes/Yes      No          -/-        -        -
Temperature Sensor RCP 2B Bearing Water      RCS-214C            -      Yes          -      Yes/Yes      No          -/-        -        -
Temperature Sensor RCP 2B Bearing Water      RCS-214D            -      Yes          -      Yes/Yes      No          -/-        -        -
Temperature Sensor RCP 1A Pump Speed          RCS-281            -      Yes          -      Yes/Yes      No          -/-        -        -
Sensor RCP 1B Pump Speed          RCS-282            -      Yes          -      Yes/Yes      No          -/-        -        -
Sensor RCP 2A Pump Speed          RCS-283            -      Yes          -      Yes/Yes      No          -/-        -        -
Sensor RCP 2B Pump Speed          RCS-284            -      Yes          -      Yes/Yes      No          -/-        -        -
Sensor Note: Dash (-) indicates not applicable.
Table 2.1.2-2 ASME Code        Leak Before      Functional Capability Line Name              Line Number        Section III        Break              Required Hot Legs                      RCS-L001A            Yes              Yes                    Yes RCS-L001B Cold Legs                    RCS-L002A            Yes              Yes                    Yes RCS-L002B RCS-L002C RCS-L002D C-60
 
Table 2.1.2-2 ASME Code    Leak Before Functional Capability Line Name          Line Number  Section III    Break          Required Pressurizer Surge Line      RCS-L003      Yes          Yes              Yes ADS Inlet Headers        RCS-L004A/B    Yes          Yes              Yes RCS-L006A/B RCS-L030A/B RCS-L020A/B Safety Valve Inlet Piping  RCS-L005A      Yes          Yes              Yes RCS-L005B Safety Valve Discharge    RCS-L050A/B    Yes          No              Yes Piping                    RCS-L051A/B ADS First-stage Valve    RCS-L010A/B    Yes          No              Yes Inlet Piping              RCS-L011A/B ADS Second-stage          RCS-L021A/B    Yes          Yes              Yes Valve Inlet Piping        RCS-L022A/B                  No ADS Third-stage Valve      RCS-L131      Yes          Yes              Yes Inlet Piping              RCS-L031A/B                  Yes RCS-L032A/B                  No ADS Outlet Piping        RCS-L012A/B    Yes          No              Yes RCS-L023A/B RCS-L033A/B RCS-L061A/B RCS-L063A/B RCS-L064A/B RCS-L200 RCS-L069A/B RCS-L240A/B PXS-L130A/B ADS Fourth-stage Inlet    RCS-L133A/B    Yes          Yes              Yes Piping                    RCS-L135A/B RCS-L136A/B RCS-L137A/B Pressurizer Spray Piping    RCS-L106      Yes          No              No RCS-L110A/B RCS-L212A/B RCS-L213 RCS-L215 RNS Suction Piping          RCS-L139      Yes          Yes              No RCS-L140 CVS Purification Piping    RCS-L111      Yes          No              No RCS-L112 C-61
 
Table 2.1.2-3 Equipment          Tag No.      Display Control Function RCP 1A Breaker (Status)          ECS-ES-31      Yes          -
RCP 1A Breaker (Status)          ECS-ES-32      Yes          -
RCP 1B Breaker (Status)          ECS-ES-41      Yes          -
RCP 1B Breaker (Status)          ECS-ES-42      Yes          -
RCP 2A Breaker (Status)          ECS-ES-51      Yes          -
RCP 2A Breaker (Status)          ECS-ES-52      Yes          -
RCP 2B Breaker (Status)          ECS-ES-61      Yes          -
RCP 2B Breaker (Status)          ECS-ES-62      Yes          -
Pressurizer Heaters              RCS-EH-03      Yes      On/Off Pressurizer Heaters            RCS-EH-04A      Yes      On/Off Pressurizer Heaters            RCS-EH-04B      Yes      On/Off Pressurizer Heaters            RCS-EH-04C      Yes      On/Off Pressurizer Heaters            RCS-EH-04D      Yes      On/Off Fourth-stage ADS Squib Valve  RCS-PL-V004A      Yes          -
(Position Indication)
Fourth-stage ADS Squib Valve  RCS-PL-V004B      Yes          -
(Position Indication)
Fourth-stage ADS Squib Valve  RCS-PL-V004C      Yes          -
(Position Indication)
Fourth-stage ADS Squib Valve  RCS-PL-V004D      Yes          -
(Position Indication)
Pressurizer Safety Valve      RCS-PL-V005A      Yes          -
(Position Indication)
Pressurizer Safety Valve      RCS-PL-V005B      Yes          -
(Position Indication)
Pressurizer Spray Valve        RCS-PL-V110A      Yes          -
(Position Indication)
Pressurizer Spray Valve        RCS-PL-V110B      Yes          -
(Position Indication)
Reactor Vessel Head Vent Valve RCS-PL-V150A      Yes          -
(Position Indication)
Reactor Vessel Head Vent Valve RCS-PL-V150B      Yes          -
(Position Indication)
C-62
 
Table 2.1.2-3 Equipment                              Tag No.                Display      Control Function Reactor Vessel Head Vent Valve                    RCS-PL-V150C                  Yes                -
(Position Indication)
Reactor Vessel Head Vent Valve                    RCS-PL-V150D                    Yes                -
(Position Indication)
Note: Dash (-) indicates not applicable.
Table 2.1.2-4 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No.                  Design Commitment                  Inspections, Tests, Analyses      Acceptance Criteria 12    2.1.02.01        1. The functional arrangement of the        Inspection of the as-built    The as-built RCS conforms RCS is as described in the Design          system will be performed. with the functional Description of this Section 2.1.2.                                        arrangement described in the Design Description of this Section 2.1.2.
13    2.1.02.02a      2.a) The components identified in          Inspection will be conducted  The ASME Code Section III Table 2.1.2-1 as ASME Code                  of the as-built components as design reports exist for the as-Section III are designed and                documented in the ASME        built components identified in constructed in accordance with ASME        design reports.              Table 2.1.2-1 as ASME Code Code Section III requirements.                                            Section III.
14    2.1.02.02b      2.b) The piping identified in              Inspection will be conducted  The ASME code Section III Table 2.1.2-2 as ASME Code                  of the as-built piping as    design reports exist for the as-Section III is designed and constructed    documented in the ASME        built piping identified in Table in accordance with ASME Code                design reports.              2.1.2-2 as ASME Code Section Section III requirements.                                                III.
15    2.1.02.03a      3.a) Pressure boundary welds in            Inspection of the as-built    A report exists and concludes components identified in Table 2.1.2-1      pressure boundary welds will  that the ASME Code Section as ASME Code Section III meet              be performed in accordance    III requirements are met for ASME Code Section III requirements.        with the ASME Code            non-destructive examination of Section III.                  pressure boundary welds.
16    2.1.02.03b      3.b) Pressure boundary welds in            Inspection of the as-built    A report exists and concludes piping identified in Table 2.1.2-2 as      pressure boundary welds will  that the ASME Code Section ASME Code Section III meet ASME            be performed in accordance    III requirements are met for Code Section III requirements.              with the ASME Code Section    non-destructive examination of III.                          pressure boundary welds.
C-63
 
Table 2.1.2-4 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No.                Design Commitment                  Inspections, Tests, Analyses        Acceptance Criteria 17    2.1.02.04a  4.a) The components identified in          A hydrostatic test will be      A report exists and concludes Table 2.1.2-1 as ASME Code                  performed on the components    that the results of the Section III retain their pressure          required by the ASME Code      hydrostatic test of the boundary integrity at their design          Section III to be              components identified in pressure.                                  hydrostatically tested.        Table 2.1.2-1 as ASME Code Section III conform with the requirements of the ASME Code Section III.
18  2.1.02.04b    4.b) The piping identified in              A hydrostatic test will be      A report exists and concludes Table 2.1.2-2 as ASME Code                  performed on the piping        that the results of the Section III retains its pressure            required by the ASME Code      hydrostatic test of the piping boundary integrity at its design            Section III to be              identified in Table 2.1.2-2 as pressure.                                  hydrostatically tested.        ASME Code Section III conform with the requirements of the ASME Code Section III.
19  2.1.02.05a.i  5.a) The seismic Category I                i) Inspection will be          i) The seismic Category I equipment identified in Table 2.1.2-1      performed to verify that the    equipment identified in can withstand seismic design basis          seismic Category I equipment    Table 2.1.2-1 is located on the loads without loss of safety function.      and valves identified in Table  Nuclear Island.
2.1.2-1 are located on the Nuclear Island.
20  2.1.02.05a.ii  5.a) The seismic Category I                ii) Type tests, analyses, or a  ii) A report exists and equipment identified in Table 2.1.2-1      combination of type tests and  concludes that the seismic can withstand seismic design basis          analyses of seismic Category I  Category I equipment can loads without loss of safety function.      equipment will be performed. withstand seismic design basis loads without loss of safety function.
21  2.1.02.05a.iii 5.a) The seismic Category I                iii) Inspection will be        iii) A report exists and equipment identified in Table 2.1.2-1      performed for the existence of  concludes that the as-built can withstand seismic design basis          a report verifying that the as- equipment including anchorage loads without loss of safety function.      built equipment including      is seismically bounded by the anchorage is seismically        tested or analyzed conditions.
bounded by the tested or analyzed conditions.
22  2.1.02.05b    5.b) Each of the lines identified in        Inspection will be performed    A report exists and concludes Table 2.1.2-2 for which functional          for the existence of a report  that each of the as-built lines capability is required is designed to      verifying that the as-built    identified in Table 2.1.2-2 for withstand combined normal and              piping meets the requirements  which functional capability is seismic design basis loads without a        for functional capability.      required meets the loss of its functional capability.                                          requirements for functional capability.
C-64
 
Table 2.1.2-4 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No.              Design Commitment                  Inspections, Tests, Analyses          Acceptance Criteria 23  2.1.02.06    6. Each of the as-built lines identified  Inspection will be performed    An LBB evaluation report in Table 2.1.2-2 as designed for LBB      for the existence of an LBB      exists and concludes that the meets the LBB criteria, or an              evaluation report or an          LBB acceptance criteria are evaluation is performed of the            evaluation report on the        met by the as-built RCS piping protection from the dynamic effects of    protection from dynamic          and piping materials, or a pipe a rupture of the line.                    effects of a pipe break.        break evaluation report exists Section 3.3, Nuclear Island      and concludes that protection Buildings, contains the design  from the dynamic effects of a descriptions and inspections,    line break is provided.
tests, analyses, and acceptance criteria for protection from the dynamic effects of pipe rupture.
24  2.1.02.07a.i  7.a) The Class 1E equipment                i) Type tests, analyses, or a    i) A report exists and identified in Table 2.1.2-1 as being      combination of type tests and    concludes that the Class 1E qualified for a harsh environment can      analyses will be performed on    equipment identified in withstand the environmental                Class 1E equipment located in    Table 2.1.2-1 as being qualified conditions that would exist before,        a harsh environment.            for a harsh environment can during, and following a design basis                                        withstand the environmental accident without loss of safety                                            conditions that would exist function for the time required to                                          before, during, and following a perform the safety function.                                                design basis accident without loss of safety function for the time required to perform the safety function.
25  2.1.02.07a.ii 7.a) The Class 1E equipment                ii) Inspection will be          ii) A report exists and identified in Table 2.1.2-1 as being      performed of the as-built Class  concludes that the as-built qualified for a harsh environment can      1E equipment and the            Class 1E equipment and the withstand the environmental                associated wiring, cables, and  associated wiring, cables, and conditions that would exist before,        terminations located in a harsh  terminations identified in during, and following a design basis      environment.                    Table 2.1.2-1 as being accident without loss of safety                                            qualified for a harsh function for the time required to                                          environment are bounded by perform the safety function.                                                type tests, analyses, or a combination of type tests and analyses.
26  2.1.02.07b  7.b) The Class 1E components              Testing will be performed on    A simulated test signal exists at identified in Table 2.1.2-1 are powered    the RCS by providing a          the Class 1E equipment from their respective Class 1E            simulated test signal in each    identified in Table 2.1.2-1 division.                                  Class 1E division.              when the assigned Class 1E division is provided the test signal.
C-65
 
Table 2.1.2-4 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No.              Design Commitment                Inspections, Tests, Analyses        Acceptance Criteria 27  2.1.02.07c  7.c) Separation is provided between      See ITAAC Table 3.3-6, item    See ITAAC Table 3.3-6, RCS Class 1E divisions, and between      7.d.                            item 7.d.
Class 1E divisions and non-Class 1E cable.
28  2.1.02.08a.i  8.a) The pressurizer safety valves        i) Inspections will be          i) The sum of the rated provide overpressure protection in        conducted to confirm that the  capacities recorded on the accordance with Section III of the        value of the vendor code plate  valve ASME Code plates of the ASME Boiler and Pressure Vessel          rating is greater than or equal safety valves exceeds Code.                                    to system relief requirements. 1,500,000 lb/hr.
29  2.1.02.08a.ii 8.a) The pressurizer safety valves        ii) Testing and analysis in    ii) A report exists and provide overpressure protection in        accordance with ASME Code      concludes that the safety valves accordance with Section III of the        Section III will be performed  set pressure is 2485 psig + 25 ASME Boiler and Pressure Vessel          to determine set pressure.      psi Code.
30  2.1.02.08b  8.b) The RCPs have a rotating inertia    A test will be performed to    The pump flow coastdown will to provide RCS flow coastdown on          determine the pump flow        provide RCS flows greater than loss of power to the pumps.              coastdown curve.                or equal to the flow shown in Figure 2.1.2-2, Flow Transient for Four Cold Legs in Operation, Four Pumps Coasting Down.
31  2.1.02.08c  8.c) Each RCP flywheel assembly can      Shop testing of each RCP        Each RCP flywheel assembly withstand a design overspeed              flywheel assembly will be      has passed an overspeed condition.                                performed at the vendor        condition of no less than 125%
facility at overspeed          of operating speed.
conditions.
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Table 2.1.2-4 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No.              Design Commitment                  Inspections, Tests, Analyses          Acceptance Criteria 32  2.1.02.08d.i  8.d) The RCS provides automatic          i) A low pressure flow test      i) The calculated ADS piping depressurization during design basis      and associated analysis will be  flow resistance from the events.                                  conducted to determine the      pressurizer through the sparger total piping flow resistance of  with all valves of each ADS each ADS valve group            group open is connected to the pressurizer    < 2.91E-6 ft/gpm2.
(i.e., ADS Stages 1-3) from the pressurizer through the outlet of the downstream ADS control valves. The reactor coolant system will be at cold conditions with the pressurizer full of water. The normal residual heat removal pumps will be used to provide injection flow into the RCS discharging through the ADS valves.
Inspections and associated analysis of the piping flow paths from the discharge of the ADS valve groups connected to the pressurizer (i.e., ADS Stages 1-3) to the spargers will be conducted to verify the line routings are consistent with the line routings used for design flow resistance calculations.
33  2.1.02.08d.ii  8.d) The RCS provides automatic          ii) Inspections and associated  ii) The calculated flow depressurization during design basis      analysis of each fourth-stage    resistance for each group of events.                                  ADS valve group (four valves    fourth-stage ADS valves and and associated piping            piping with all valves open is:
connected to each hot leg) will be conducted to verify the line Loop 1: < 1.70x10-7 ft/gpm2 routing is consistent with the line routing used for design flow resistance calculations. Loop 2: < 1.57x10-7 ft/gpm2 34  2.1.02.08d.iii 8.d) The RCS provides automatic          iii) Inspections of each fourth- iii) The flow area through each depressurization during design basis      stage ADS valve will be          fourth-stage ADS valve is events.                                  conducted to determine the      > 67 in2.
flow area through each valve.
C-67
 
Table 2.1.2-4 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No.              Design Commitment                Inspections, Tests, Analyses        Acceptance Criteria 35  2.1.02.08d.iv  8.d) The RCS provides automatic          iv) Type tests and analysis    iv) A report exists and depressurization during design basis      will be performed to            concludes that the effective events.                                  determine the effective flow    flow area through each stage 1 area through each stage 1,2,3  ADS valve > 4.6 in2 and each ADS valve.                      stage 2,3 ADS valve is > 21 in2.
36  2.1.02.08d.v  8.d) The RCS provides automatic          v) Inspections of the elevation v) The minimum elevation of depressurization during design basis      of the ADS stage 4 valve        the bottom inside surface of the events.                                  discharge will be conducted. outlet of these valves is greater than plant elevation 110 feet.
37  2.1.02.08d.vi  8.d) The RCS provides automatic          vi) Inspections of the ADS      vi) The discharge of the ADS depressurization during design basis      stage 4 valve discharge will be stage 4 valves is directed into events.                                  conducted.                      the steam generator compartments.
38  2.1.02.08d.vii  8.d) The RCS provides automatic          vii) Inspection of each ADS    vii) The flow area through the depressurization during design basis      sparger will be conducted to    holes in each ADS sparger is events.                                  determine the flow area        > 274 in2.
through the sparger holes.
39  2.1.02.08d.viii 8.d) The RCS provides automatic          viii) Inspection of the        viii) The centerline of the depressurization during design basis      elevation of each ADS sparger  connection of the sparger arms events.                                  will be conducted.              to the sparger hub is < 11.5 feet below the IRWST overflow level.
40    2.1.02.08e    8.e) The RCS provides emergency          Inspections of the reactor      A report exists and concludes letdown during design basis events.      vessel head vent valves and    that the capacity of the reactor inlet and outlet piping will be vessel head vent is sufficient to conducted.                      pass not less than 8.2 lbm/sec at 1250 psia in the RCS.
41    2.1.02.09a    9.a) The RCS provides circulation of      Testing and analysis to        The calculated post-fuel load coolant to remove heat from the core. measure RCS flow with four      RCS flow rate is > 301,670 reactor coolant pumps          gpm.
operating at no-load RCS pressure and temperature conditions will be performed.
Analyses will be performed to convert the measured pre-fuel load flow to post-fuel load flow with 10-percent steam generator tube plugging.
C-68
 
Table 2.1.2-4 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No.              Design Commitment                  Inspections, Tests, Analyses          Acceptance Criteria 42  2.1.02.09b.i  9.b) The RCS provides the means to        i) Inspections will be            i) Pressurizer heater backup control system pressure.                  performed to verify the rated    groups A and B each has a capacity of pressurizer heater    rated capacity of at least 168 backup groups A and B.            kW.
                                                            .
43  2.1.02.09b.ii 9.b) The RCS provides the means to        ii) Tests will be performed to    ii) Controls in the MCR control system pressure.                  verify that the pressurizer      operate to cause the pressurizer spray valves can open and        spray valves to open and close.
close when operated from the MCR.
44  2.1.02.09c  9.c) The pressurizer heaters trip after    Testing will be performed to      The pressurizer heaters a signal is generated by the PMS.          confirm trip of the pressurizer  identified in Table 2.1.2-3 trip heaters identified in            after a signal is generated by Table 2.1.2-3.                    the PMS.
45    2.1.02.10  10. Safety-related displays identified    Inspection will be performed      Safety-related displays in Table 2.1.2-1 can be retrieved in the  for retrievability of the safety- identified in Table 2.1.2-1 can MCR.                                      related displays in the MCR.      be retrieved in the MCR.
46  2.1.02.11a.i  11.a) Controls exist in the MCR to        i) Testing will be performed      i) Controls in the MCR cause the remotely operated valves        on the squib valves identified    operate to cause a signal at the identified in Table 2.1.2-1 to perform    in Table 2.1.2-1 using controls  squib valve electrical leads active functions.                          in the MCR without stroking      which is capable of actuating the valve.                        the squib valve.
47  2.1.02.11a.ii 11.a) Controls exist in the MCR to        ii) Stroke testing will be        ii) Controls in the MCR cause the remotely operated valves        performed on the other            operate to cause the remotely identified in Table 2.1.2-1 to perform    remotely operated valves          operated valves (other than active functions.                          listed in Table 2.1.2-1 using    squib valves) to perform active controls in the MCR.              functions.
48  2.1.02.11b.i  11.b) The valves identified in            i) Testing will be performed      i) The squib valves receive a Table 2.1.2-1 as having PMS control        on the squib valves identified    signal at the valve electrical perform an active safety function after    in Table 2.1.2-1 using real or    leads that is capable of receiving a signal from the PMS.          simulated signals into the        actuating the squib valve.
PMS without stroking the valve.
49  2.1.02.11b.ii 11.b) The valves identified in            ii) Testing will be performed    ii) The other remotely Table 2.1.2-1 as having PMS control        on the other remotely operated    operated valves identified in perform an active safety function after    valves identified in Table        Table 2.1.2-1 as having PMS receiving a signal from the PMS.          2.1.2-1 using real or simulated  control perform the active signals into the PMS.            function identified in the table after receiving a signal from PMS.
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Table 2.1.2-4 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No.              Design Commitment                  Inspections, Tests, Analyses          Acceptance Criteria 50  2.1.02.11b.iii 11.b) The valves identified in            iii) Testing will be performed  iii) These valves open within Table 2.1.2-1 as having PMS control        to demonstrate that remotely    the following times after perform an active safety function after    operated RCS valves              receipt of an actuation signal:
receiving a signal from the PMS.          RCS-V001A/B, V002A/B,            V001A/B < 40 sec V003A/B, V011A/B,                V002A/B,V003A/B < 100 V012A/B, V013A/B open            sec within the required response    V011A/B < 30 sec times.                          V012A/B,V013A/B < 60 sec 51  2.1.02.11c.i  11.c) The valves identified in            i) Testing will be performed    i) The squib valves receive a Table 2.1.2-1 as having DAS control        on the squib valves identified  signal at the valve electrical perform an active safety function after    in Table 2.1.2-1 using real or  leads that is capable of receiving a signal from DAS.              simulated signals into the      actuating the squib valve DAS without stroking the valve.
52  2.1.02.11c.ii  11.c) The valves identified in            ii) Testing will be performed    ii) The other remotely Table 2.1.2-1 as having DAS control        on the other remotely operated  operated valves identified in perform an active safety function after    valves identified in Table      Table 2.1.2-1 as having DAS receiving a signal from DAS.              2.1.2-1 using real or simulated  control perform the active signals into the DAS.            function identified in the table after receiving a signal from DAS.
53  2.1.02.12a.i  12.a) The automatic depressurization      i) Tests or type tests of motor- i) A test report exists and valves identified in Table 2.1.2-1        operated valves will be          concludes that each motor-perform an active safety-related          performed that demonstrate      operated valve changes function to change position as            the capability of the valve to  position as indicated in indicated in the table.                    operate under its design        Table 2.1.2-1 under design conditions.                      conditions.
54  2.1.02.12a.ii  12.a) The automatic depressurization      ii) Inspection will be          ii) A report exists and valves identified in Table 2.1.2-1        performed for the existence of  concludes that the as-built perform an active safety-related          a report verifying that the as-  motor-operated valves are function to change position as            built motor-operated valves      bounded by the tests or type indicated in the table.                    are bounded by the tests or      tests.
type tests.
55  2.1.02.12a.iii 12.a) The automatic depressurization      iii) Tests of the motor-        iii) Each motor-operated valve valves identified in Table 2.1.2-1        operated valves will be          changes position as indicated perform an active safety-related          performed under pre-            in Table 2.1.2-1 under pre-function to change position as            operational flow, differential  operational test conditions.
indicated in the table.                    pressure and temperature conditions.
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Table 2.1.2-4 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No.              Design Commitment                  Inspections, Tests, Analyses          Acceptance Criteria 56  2.1.02.12a.iv  12.a) The automatic depressurization      iv) Tests or type tests of squib  iv) A test report exists and valves identified in Table 2.1.2-1        valves will be performed that    concludes that each squib valve perform an active safety-related          demonstrate the capability of    changes position as indicated function to change position as            the valve to operate under its    in Table 2.1.2-1 under design indicated in the table.                    design conditions.                conditions.
57  2.1.02.12a.v  12.a) The automatic depressurization      v) Inspection will be            v) A report exists and valves identified in Table 2.1.2-1        performed for the existence of    concludes that the as-built perform an active safety-related          a report verifying that the as-  squib valves are bounded by function to change position as            built squib valves are bounded    the tests or type tests.
indicated in the table.                    by the tests or type tests.
58  2.1.02.12a.vi  12.a) The automatic depressurization      vi) See item 8.d.i in this table. vi) See item 8.d.i in this table.
valves identified in Table 2.1.2-1                                          The ADS stage 1-3 valve flow perform an active safety-related                                            resistances are verified to be function to change position as                                              consistent with the ADS stage indicated in the table.                                                      1-3 path flow resistances.
59  2.1.02.12a.vii  12.a) The automatic depressurization      vii) See item 8.d.ii in this      vii) See item 8.d.ii in this valves identified in Table 2.1.2-1        table.                            table. The ADS stage 4 valve perform an active safety-related                                            flow resistances are verified to function to change position as                                              be consistent with the ADS indicated in the table.                                                      stage 4 path flow resistances.
60  2.1.02.12a.viii 12.a) The automatic depressurization      viii) See item 8.d.iii in this    viii) See item 8.d.iii in this valves identified in Table 2.1.2-1        table.                            table.
perform an active safety-related function to change position as indicated in the table.
61  2.1.02.12a.ix  12.a) The automatic depressurization      ix) See item 8.d.iv in this      ix) See item 8.d.iv in this valves identified in Table 2.1.2-1        table.                            table.
perform an active safety-related function to change position as indicated in the table.
62    2.1.02.12b    12.b) After loss of motive power, the      Testing of the remotely          Upon loss of motive power, remotely operated valves identified in    operated valves will be          each remotely operated valve Table 2.1.2-1 assume the indicated        performed under the              identified in Table 2.1.2-1 loss of motive power position.            conditions of loss of motive      assumes the indicated loss of power.                            motive power position.
63    2.1.02.13a    13.a) Controls exist in the MCR to        Testing will be performed on      Controls in the MCR operate to trip the RCPs.                            the RCPs using controls in the    trip the RCPs.
MCR.
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Table 2.1.2-4 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No.                Design Commitment                  Inspections, Tests, Analyses          Acceptance Criteria 64  2.1.02.13b    13.b) The RCPs trip after receiving a      Testing will be performed        The RCPs trip after receiving a signal from the PMS.                      using real or simulated signals  signal from the PMS.
into the PMS.
65  2.1.02.13c    13.c) The RCPs trip after receiving a      Testing will be performed        The RCPs trip after receiving a signal from the DAS.                      using real or simulated signals  signal from the DAS.
into the DAS.
66  2.1.02.14      14. Controls exist in the MCR to          Testing will be performed on    Controls in the MCR operate to cause the components identified in        the components in Table 2.1.2-  cause the components listed in Table 2.1.2-3 to perform the listed        3 using controls in the MCR. Table 2.1.2-3 to perform the function.                                                                  listed functions.
67  2.1.02.15      15. Displays of the parameters            Inspection will be performed    The displays identified in identified in Table 2.1.2-3 can be        for retrievability of the RCS    Table 2.1.2-3 can be retrieved retrieved in the MCR.                      parameters in the MCR.          in the MCR.
Table 2.1.2-5 Component Name                                    Tag No.                Component Location Steam Generator 1                                            RCS-MB-01                      Containment Steam Generator 2                                            RCS-MB-02                      Containment Reactor Coolant Pump 1A                                      RCS-MP-01A                      Containment Reactor Coolant Pump 1B                                      RCS-MP-01B                      Containment Reactor Coolant Pump 2A                                      RCS-MP-02A                      Containment Reactor Coolant Pump 2B                                      RCS-MP-02B                      Containment Pressurizer                                                  RCS-MV-02                      Containment ADS Sparger A                                                PXS-MW-01A                      Containment ADS Sparger B                                                PXS-MW-01B                      Containment C-72
 
Figure 2.1.2-1 (Sheet 1 of 2)
Reactor Coolant System C-73
 
Figure 2.1.2-1 (Sheet 2 of 2)
Reactor Coolant System C-74
 
Figure 2.1.2-2 Flow Transient for Four Cold Legs in Operation, Four Pumps Coasting Down C-75
 
2.1.3            Reactor System Design Description The reactor system (RXS) generates heat by a controlled nuclear reaction and transfers the heat generated to the reactor coolant, provides a barrier that prevents the release of fission products to the atmosphere and a means to insert negative reactivity into the reactor core and to shutdown the reactor core.
The reactor core contains a matrix of fuel rods assembled into fuel assemblies using structural elements. Rod cluster control assemblies (RCCAs) are positioned and held within the fuel assemblies by control rod drive mechanisms (CRDMs). The CRDMs unlatch upon termination of electrical power to the CRDM thereby releasing the RCCAs. The fuel assemblies and RCCAs are designed in accordance with the principal design requirements.
The RXS is operated during normal modes of plant operation, including startup, power operation, cooldown, shutdown and refueling.
The component locations of the RXS are as shown in Table 2.1.3-3.
: 1. The functional arrangement of the RXS is as described in the Design Description of this Section 2.1.3.
: 2. a) The reactor upper internals rod guide arrangement is as shown in Figure 2.1.3-1.
b) The rod cluster control and drive rod arrangement is as shown in Figure 2.1.3-2.
c) The reactor vessel arrangement is as shown in Figure 2.1.3-3.
: 3. The components identified in Table 2.1.3-1 as ASME Code Section III are designed and constructed in accordance with ASME Code Section III requirements.
: 4. Pressure boundary welds in components identified in Table 2.1.3-1 as ASME Code Section III meet ASME Code Section III requirements.
: 5. The pressure boundary components (reactor vessel [RV], control rod drive mechanisms
[CRDMs], and incore instrument QuickLoc assemblies) identified in Table 2.1.3-1 as ASME Code Section III retain their pressure boundary integrity at their design pressure.
: 6. The seismic Category I equipment identified in Table 2.1.3-1 can withstand seismic design basis loads without loss of safety function.
: 7. The reactor internals will withstand the effects of flow induced vibration.
: 8. The reactor vessel direct injection nozzle limits the blowdown of the reactor coolant system (RCS) following the break of a direct vessel injection line.
: 9. a) The Class 1E equipment identified in Table 2.1.3-1 as being qualified for a harsh environment can withstand the environmental conditions that would exist before, during, and following a design basis accident without loss of safety function for the time required to perform the safety function.
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b) The Class 1E components identified in Table 2.1.3-1 are powered from their respective Class 1E division.
c) Separation is provided between RXS Class 1E divisions, and between Class 1E divisions and non-Class 1E cable.
: 10. The reactor lower internals assembly is equipped with holders for at least eight capsules for storing material surveillance specimens.
: 11. The reactor pressure vessel (RPV) beltline material has a Charpy upper-shelf energy of no less than 75 ft-lb.
: 12. Safety-related displays of the parameters identified in Table 2.1.3-1 can be retrieved in the main control room (MCR).
: 13. The fuel assemblies and rod cluster control assemblies intended for initial core load and listed in Table 2.1.3-1 have been designed and constructed in accordance with the principal design requirements.
: 14. A top-of-the-head visual inspection, including 360 degrees around each reactor vessel head penetration nozzle, can be performed.
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Table 2.1.3-1 ASME Code                Class 1E/    Safety-Section III  Seismic  Qual. for    Related Equipment Name                            Tag No.                    Classification  Cat. I  Harsh Envir. Display RV                              RXS-MV-01                                    Yes              Yes      -            -
Reactor Upper Internals Assembly RXS-MI-01                                    Yes              Yes      -            -
Reactor Lower Internals Assembly RXS-MI-02                                    Yes              Yes      -            -
Fuel Assemblies (157 locations)  RXS-FA-A07/A08/A09/B05/B06/B07/B08/          No(1)            Yes      -            -
B09/B10/B11/C04/C05/C06/C07/C08/C09/C10/
C11/C12/D03/D04/D05/D06/D07/D08/D09/
D10/D11/D12/D13/E02/E03/E04/E05/E06/E07/
E08/E09/E10/E11/E12/E13/E14/F02/F03/F04/
F05/F06/F07/F08/F09/F10/F11/F12/F13/F14/
G01/G02/G03/G04/G05/G06/G07/G08/G09/
G10/G11/G12/G13/G14/G15/H01/H02/H03/
H04/H05/H06/H07/H08/H09/H10/H11/H12/
H13/H14/H15/J01/J02/J03/J04/J05/J06/J07/J08/
J09/J10/J11/J12/J13/J14/J15/K02/K03/K04/
K05/K06/K07/K08/K09/K10/K11/K12/K13/
K14/L02/L03/L04/L05/L06/L07/L08/L09/L10/
L11/L12/L13/L14/M03/M04/M05/M06/M07/
M08/M09/M10/M11/M12/M13/N04/N05/N06/
N07/N08/N09/N10/N11/N12/P05/P06/P07/P08/
P09/P10/P11/ R07/R08/R09 Rod Cluster Control Assemblies  RXS-FR-B06/B10/C05/C07/C09/C11/D06/          No(1)            Yes      -            -
(RCCAs) (minimum 53 locations)  D08/D10/E03/E05/E07/E09/E11/E13/F02/F04/
F12/F14/G03/G05/G07/G09/G11/G13/H04/
H08/H12/J03/J05/J07/J09/J11/J13/K02/K04/
K12/K14/L03/L05/L07/L09/L11/L13/M06/
M08/M10/N05/N07/N09/N11/P06/P10 Gray Rod Cluster Assemblies      RXS-FG-B08/D04/D12/F06/F08/F10/H02/H06/      No(1)            Yes      -            -
(GRCAs) (16 locations)          H10/H14/K06/K08/K10/M04/M12/P08 C-78
 
Table 2.1.3-1 ASME Code                Class 1E/      Safety-Section III  Seismic  Qual. for    Related Equipment Name                                    Tag No.                    Classification  Cat. I  Harsh Envir. Display Control Rod Drive Mechanisms          RXS-MV-11B06/11B08/11B10/11C05/11C07/          Yes              Yes      No/No        No (CRDMs) (69 Locations)                11C09/11C11/11D04/11D06/11D08/11D10/
11D12/11E03/11E05/11E07/11E09/11E11/
11E13/11F02/11F04/11F06/11F08/11F10/
11F12/11F14/11G03/11G05/11G07/11G09/
11G11/11G13/11H02/11H04/11H06/11H08/
11H10/11H12/11H14/11J03/11J05/11J07/
11J09/11J11/11J13/11K02/11K04/11K06/
11K08/11K10/11K12/11K14/11L03/11L05/
11L07/11L09/11L11/11L13/11M04/11M06/
11M08/11M10/11M12/11N05/11N07/11N09/
11N11/11P06/11P08/11P10 Incore Instrument QuickLoc            RXS-MY-Y11 through Y18                        Yes              Yes      -            -
Assemblies (8 Locations)
Source Range Detectors (4)            RXS-JE-NE001A/NE001B/NE001C/NE001D            -                Yes      Yes/Yes      No Intermediate Range Detectors (4)      RXS-JE-NE002A/NE002B/NE002C/NE002D            -                Yes      Yes/Yes      Yes Power Range Detectors - Lower (4)      RXS-JE-NE003A/NE003B/NE003C/NE003D            -                Yes      Yes/Yes      No Power Range Detectors - Upper (4)      RXS-JE-NE004A/NE004B/NE004C/NE004D            -                Yes      Yes/Yes      No Note: Dash (-) indicates not applicable.
: 1. Fuel assemblies are designed using ASME Section III as a general guide.
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Table 2.1.3-2 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No.              Design Commitment                  Inspections, Tests, Analyses      Acceptance Criteria 68  2.1.03.01  1. The functional arrangement of the RXS      Inspection of the as-built      The as-built RXS conforms is as described in the Design Description of  system will be performed.      with the functional this Section 2.1.3.                                                          arrangement as described in the Design Description of this Section 2.1.3.
69  2.1.03.02a 2.a) The reactor upper internals rod guide    Inspection of the as-built      The as-built RXS will arrangement is as shown in Figure 2.1.3-1. system will be performed.      accommodate the fuel assembly and control rod drive mechanism pattern shown in Figure 2.1.3-1.
70  2.1.03.02b 2.b) The control assemblies (rod cluster      Inspection of the as-built      The as-built RXS will and gray rod) and drive rod arrangement is    system will be performed.      accommodate the control as shown in Figure 2.1.3-2.                                                  assemblies (rod cluster and gray rod) and drive rod arrangement shown in Figure 2.1.3-2.
71  2.1.03.02c 2.c) The reactor vessel arrangement is as    Inspection of the as-built      The as-built RXS will shown in Figure 2.1.3-3.                      system will be performed.      accommodate the reactor vessel arrangement shown in Figure 2.1.3-3.
72  2.1.03.03  3. The components identified in Table        Inspection will be conducted    The ASME Code Section III 2.1.3-1 as ASME Code Section III are          of the as-built components as  design reports exist for the designed and constructed in accordance        documented in the ASME          as-built components with ASME Code Section III requirements.      design reports.                identified in Table 2.1.3-1 as ASME Code Section III.
73  2.1.03.04  4. Pressure boundary welds in components      Inspection of as-built pressure A report exists and identified in Table 2.1.3-1 as ASME Code      boundary welds will be          concludes that the ASME Section III meet ASME Code Section III        performed in accordance with    Code Section III requirements.                                the ASME Code Section III.      requirements are met for non-destructive examination of pressure boundary welds.
74  2.1.03.05  5. The pressure boundary components (RV,      A hydrostatic test will be      A report exists and CRDMs, and incore instrument QuickLoc        performed on the components    concludes that the results of assemblies) identified in Table 2.1.3-1 as    of the RXS required by the      the hydrostatic test of the ASME Code Section III retain their            ASME Code Section III to be    pressure boundary pressure boundary integrity at their design  hydrostatically tested.        components (RV, CRDMs, pressure.                                                                    and incore instrument QuickLoc assemblies) conform with the requirements of the ASME Code Section III.
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Table 2.1.3-2 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No.                Design Commitment                  Inspections, Tests, Analyses        Acceptance Criteria 75  2.1.03.06.i  6. The seismic Category I equipment            i) Inspection will be            i) The seismic Category I identified in Table 2.1.3-1 can withstand      performed to verify that the    equipment identified in seismic design basis loads without loss of    seismic Category I equipment    Table 2.1.3-1 is located on safety function.                              identified in Table 2.1.3-1 is  the Nuclear Island.
located on the Nuclear Island.
76  2.1.03.06.ii 6. The seismic Category I equipment            ii) Type tests, analyses, or a  ii) A report exists and identified in Table 2.1.3-1 can withstand      combination of type tests and    concludes that the seismic seismic design basis loads without loss of    analyses of seismic Category I  Category I equipment can safety function.                              equipment will be performed. withstand seismic design basis loads without loss of safety function.
77  2.1.03.06.iii 6. The seismic Category I equipment            iii) Inspection will be          iii) A report exists and identified in Table 2.1.3-1 can withstand      performed for the existence of  concludes that the as-built seismic design basis loads without loss of    a report verifying that the as-  equipment including safety function.                              built equipment including        anchorage is seismically anchorage is seismically        bounded by the tested or bounded by the tested or        analyzed conditions.
analyzed conditions.
78  2.1.03.07.i  7. The reactor internals will withstand the    i) A vibration type test will be i) A report exists and effects of flow induced vibration.            conducted on the (first unit)    concludes that the (first unit) reactor internals                reactor internals have no representative of AP1000.        observable damage or loose parts as a result of the vibration type test.
79  2.1.03.07.ii 7. The reactor internals will withstand the    ii) A pre-test inspection, a    ii) The as-built reactor effects of flow induced vibration.            flow test and a post-test        internals have no observable inspection will be conducted    damage or loose parts.
on the as-built reactor internals.
80    2.1.03.08  8. The reactor vessel direct vessel injection  An inspection will be            The throat area of the direct nozzle limits the blowdown of the RCS          conducted to verify the flow    vessel injection line nozzle following the break of a direct vessel        area of the flow limiting        flow limiting venturi is less injection line.                                venturi within each direct      than or equal to 12.57 in2.
vessel injection nozzle.
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Table 2.1.3-2 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No.                Design Commitment                  Inspections, Tests, Analyses      Acceptance Criteria 81  2.1.03.09a.i  9.a) The Class 1E equipment identified in      i) Type tests, analysis, or a  i) A report exists and Table 2.1.3-1 as being qualified for a harsh  combination of type tests and  concludes that the Class 1E environment can withstand the                  analysis will be performed on  equipment identified in environmental conditions that would exist      Class 1E equipment located in  Table 2.1.3-1 as being before, during, and following a design        a harsh environment.          qualified for a harsh basis accident without loss of safety                                        environment can withstand function for the time required to perform                                    the environmental the safety function.                                                          conditions that would exist before, during, and following a design basis accident without loss of safety function for the time required to perform the safety function.
82  2.1.03.09a.ii 9.a) The Class 1E equipment identified in      ii) Inspection will be        ii) A report exists and Table 2.1.3-1 as being qualified for a harsh  performed of the as-built      concludes that the as-built environment can withstand the                  Class 1E equipment and the    Class 1E equipment and the environmental conditions that would exist      associated wiring, cables, and associated wiring, cables, before, during, and following a design        terminations located in a      and terminations identified basis accident without loss of safety          harsh environment              in Table 2.1.3-1 as being function for the time required to perform                                    qualified for a harsh the safety function.                                                          environment are bounded by type tests, analyses, or a combination of type tests and analyses.
83  2.1.03.09b  9.b) The Class 1E components identified        Testing will be performed by  A simulated test signal in Table 2.1.3-1 are powered from their        providing simulated test      exists for Class 1E respective Class 1E division.                  signals in each Class 1E      equipment identified in division.                      Table 2.1.3-1 when the assigned Class 1E division is provided the test signal.
84  2.1.03.09c  9.c) Separation is provided between RXS        See ITAAC Table 3.3-6, item    See ITAAC Table 3.3-6, Class 1E divisions, and between Class 1E      7.d.                          item 7.d.
divisions and non-Class 1E cable.
85  2.1.03.10    10. The reactor lower internals assembly is    Inspection of the reactor      At least eight capsules are in equipped with holders for at least eight      lower internals assembly for  the reactor lower internals capsules for storing material surveillance    the presence of capsules will  assembly.
specimens.                                    be performed.
86  2.1.03.11    11. The RPV beltline material has a            Manufacturing tests of the    A report exists and Charpy upper-shelf energy of no less than      Charpy V-Notch specimen of    concludes that the initial 75 ft-lb.                                      the RPV beltline material will RPV beltline Charpy upper-be performed.                  shelf energy is no less than 75 ft-lb.
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Table 2.1.3-2 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No.            Design Commitment                    Inspections, Tests, Analyses          Acceptance Criteria 87  2.1.03.12 12. Safety-related displays of the            Inspection will be performed      Safety-related displays parameters identified in Table 2.1.3-1 can    for retrievability of the safety- identified in Table 2.1.3-1 be retrieved in the MCR.                      related displays in the MCR.      can be retrieved in the MCR.
88  2.1.03.13 13. The fuel assemblies and rod cluster        An analysis is performed of      A report exists and control assemblies intended for initial core  the reactor core design.          concludes that the fuel load and listed in Table 2.1.3-1 have been                                      assemblies and rod cluster designed and constructed in accordance                                          control assemblies intended with the established design requirements.                                        for the initial core load and listed in Table 2.1.3-1 have been designed and constructed in accordance with the principal design requirements.
89  2.1.03.14 14. A top-of-the-head visual inspection,      A preservice visual              A report exists that including 360 degrees around each reactor      examination of the reactor        documents the results of the vessel head penetration nozzle, can be        vessel head top surface and      top-of-the-head visual performed.                                    penetration nozzles will be      inspection, including 360 performed.                        degrees around each reactor vessel head penetration nozzle.
C-83
 
Table 2.1.3-3 Component Name                      Tag No.                Component Location RV                              RXS-MV-01                    Containment Reactor Upper Internals Assembly RXS-MI-01                    Containment Reactor Lower Internals Assembly RXS-MI-02                    Containment Fuel Assemblies (157 locations)  RXS-FA-A07/A08/A09/B05/      Containment (located in auxiliary B06/B07/B08/B09/B10/B11/    building prior to fuel loading)
C04/C05/C06/C07/C08/C09/
C10/C11/C12/D03/D04/D05/
D06/D07/D08/D09/D10/D11/
D12/D13/E02/E03/E04/E05/
E06/E07/E08/E09/E10/E11/E12/
E13/E14/F02/F03/F04/F05/F06/
F07/F08/F09/F10/F11/F12/F13/
F14/G01/G02/G03/G04/G05/
G06/G07/G08/G09/G10/G11/
G12/G13/G14/G15/H01/H02/
H03/H04/H05/H06/H07/H08/
H09/H10/H11/H12/H13/H14/
H15/J01/J02/J03/J04/J05/J06/
J07/J08/J09/J10/J11/J12/J13/
J14/J15/K02/K03/K04/K05/
K06/K07/K08/K09/K10/K11/
K12/K13/K14/L02/L03/L04/
L05/L06/L07/L08/L09/L10/L11/
L12/L13/L14/M03/M04/M05/
M06/M07/M08/M09/M10/M11/
M12/M13/N04/N05/N06/N07/
N08/N09/N10/N11/N12/P05/
P06/P07/P08/P09/P10/P11/R07/
R08/R09 Rod Cluster Control Assemblies  RXS-FR-B06/B10/C05/C07/      Containment (located in auxiliary (RCCAs) (minimum 53 locations)  C09/C11/D06/D08/D10/E03/    building prior to fuel loading)
E05/E07/E09/E11/E13/F02/F04/
F12/F14/G03/G05/G07/G09/
G11/G13/H04/H08/H12/J03/
J05/J07/J09/J11/J13/K02/K04/
K12/K14/L03/L05/L07/L09/
L11/L13/M06/M08/M10/N05/
N07/N09/N11/P06/P10 Gray Rod Cluster Assemblies      RXS-FG-B08/D04/D12/F06/      Containment (located in auxiliary (GRCAs) (16 locations)          F08/F10/H02/H06/H10/H14/    building prior to fuel loading)
K06/K08/K10/M04/M12/P08 C-84
 
Table 2.1.3-3 Component Name                    Tag No.                  Component Location Control Rod Drive Mechanisms      RXS-MV-11B06/11B08/            Containment (CRDMs) (69 Locations)            11B10/11C05/11C07/11C09/
11C11/11D04/11D06/11D08/
11D10/11D12/11E03/11E05/
11E07/11E09/11E11/11E13/
11F02/11F04/11F06/11F08/
11F10/11F12/11F14/11G03/
11G05/11G07/11G09/11G11/
11G13/11H02/11H04/11H06/
11H08/11H10/11H12/11H14/
11J03/11J05/11J07/11J09/11J11/
11J13/11K02/11K04/11K06/
11K08/11K10/11K12/11K14/
11L03/11L05/11L07/11L09/
11L11/11L13/11M04/11M06/
11M08/11M10/11M12/11N05/
11N07/11N09/11N11/11P06/
11P08/11P10 Incore Instrument QuickLoc        RXS-MY-Y11 through Y18        Containment Assemblies (8 Locations)
Source Range Detectors (4)        RXS-JE-NE001A/NE001B/          Containment NE001C/NE001D Intermediate Range Detectors (4)  RXS-JE-NE002A/NE002B/          Containment NE002C/NE002D Power Range Detectors - Lower (4) RXS-JE-NE003A/NE003B/          Containment NE003C/NE003D Power Range Detectors - Upper (4) RXS-JE-NE004A/NE004B/          Containment NE004C/NE004D C-85
 
Table 2.1.3-4 Key Dimensions and Acceptable Variations of the Reactor Vessel and Internals (Figure 2.1.3.2 and Figure 2.1.3-3)
Dimension  Nominal          Acceptable or Elevation  Value          Variation Description                            (inches)    (inches)          (inches)
RV inside diameter at beltline (inside cladding)                  A          159.0          +1.0/-1.0 RV wall thickness at beltline (without cladding)                  B            8.4        +1.0/-0.12 RV wall thickness at bottom head (without cladding)                C            6.0        +1.0/-0.12 RV inlet nozzle inside diameter at safe end                        D          22.0        +0.35/-0.10 RV outlet nozzle inside diameter at safe end                      E          31.0        +0.35/-0.10 Elevation from RV mating surface to centerline of inlet            F          62.5        +0.25/-0.25 nozzle Elevation from RV mating surface to centerline of outlet          G          80.0        +0.25/-0.25 nozzle Elevation from RV mating surface to centerline of direct          H          100.0        +0.25/-0.25 vessel injection nozzle Elevation from RV mating surface to inside of RV bottom            I        397.59        +1.0/-0.50 head (inside cladding)
Elevation from RV mating surface to top of lower core              J        327.3        +0.50/-0.50 support plate Separation distance between bottom of upper core plate            K          189.8        +0.20/0.20 and top of lower core support with RV head in place C-86
 
Figure 2.1.3-1 Reactor Upper Internals Rod Guide Arrangement C-87
 
Figure 2.1.3-2 Rod Cluster Control and Drive Rod Arrangement C-88
 
Figure 2.1.3-3 Reactor Vessel Arrangement C-89
 
2.2            Nuclear Safety Systems 2.2.1          Containment System Design Description The containment system (CNS) is the collection of boundaries that separates the containment atmosphere from the outside environment during design basis accidents.
The CNS is as shown in Figure 2.2.1-1 and the component locations of the CNS are as shown in Table 2.2.1-4.
: 1. The functional arrangement of the CNS and associated systems is as described in the Design Description of this Section 2.2.1.
: 2. a) The components identified in Table 2.2.1-1 as ASME Code Section III are designed and constructed in accordance with ASME Code Section III requirements.
b) The piping identified in Table 2.2.1-2 as ASME Code Section III is designed and constructed in accordance with ASME Code Section III requirements.
: 3. a) Pressure boundary welds in components identified in Table 2.2.1-1 as ASME Code Section III meet ASME Code Section III requirements.
b) Pressure boundary welds in piping identified in Table 2.2.1-2 as ASME Code Section III meet ASME Code Section III requirements.
: 4. a) The components identified in Table 2.2.1-1 as ASME Code Section III retain their pressure boundary integrity at their design pressure.
b) The piping identified in Table 2.2.1-2 as ASME Code Section III retains its pressure boundary integrity at its design pressure.
: 5. The seismic Category I equipment identified in Table 2.2.1-1 can withstand seismic design basis loads without loss of structural integrity and safety function.
: 6. a) The Class 1E equipment identified in Table 2.2.1-1 as being qualified for a harsh environment can withstand the environmental conditions that would exist before, during, and following a design basis accident without loss of safety function for the time required to perform the safety function.
b) The Class 1E components identified in Table 2.2.1-1 are powered from their respective Class 1E division.
c) Separation is provided between CNS Class 1E divisions, and between Class 1E divisions and non-Class 1E cable.
d) The non-Class 1E electrical penetrations identified in Table 2.2.1-1 as being qualified for a harsh environment can withstand the environmental conditions that would exist before, during, and following a design basis accident without loss of containment pressure boundary integrity.
C-90
: 7. The CNS provides the safety-related function of containment isolation for containment boundary integrity and provides a barrier against the release of fission products to the atmosphere.
: 8. Containment electrical penetration assemblies are protected against currents that are greater than the continuous ratings.
: 9. Safety-related displays identified in Table 2.2.1-1 can be retrieved in the main control room (MCR).
: 10. a) Controls exist in the MCR to cause those remotely operated valves identified in Table 2.2.1-1 to perform active functions.
b) The valves identified in Table 2.2.1-1 as having protection and safety monitoring system (PMS) control perform an active function after receiving a signal from the PMS.
c) The valves identified in Table 2.2.1-1 as having diverse actuation system (DAS) control perform an active function after receiving a signal from the DAS.
: 11. a) The motor-operated and check valves identified in Table 2.2.1-1 perform an active safety-related function to change position as indicated in the table.
b) After loss of motive power, the remotely operated valves identified in Table 2.2.1-1 assume the indicated loss of motive power position.
C-91
 
Table 2.2.1-1 ASME                        Class 1E/                              Loss of Code              Remotely Qual. for  Safety-                      Motive Section Seismic    Operated  Harsh    Related    Control  Active    Power Equipment Name              Tag No. III    Cat. I      Valve  Envir. Display  PMS/DAS  Function  Position Service Air Supply Outside      CAS-PL-V204  Yes    Yes          No      -/-      No        -/-    None        -
Containment Isolation Valve CAS-PL-V205  Yes    Yes          No      -/-      No        -/-    Transfer    -
Service Air Supply Inside                                                                              Closed Containment Isolation Check Valve Instrument Air Supply Outside  CAS-PL-V014  Yes    Yes        Yes    Yes/No  Yes (Valve  Yes/No  Transfer  Closed Containment Isolation Valve                                                        Position)          Closed
                                                                                      -
CAS-PL-V015  Yes    Yes          No      -/-                  -/-    Transfer    -
Instrument Air Supply Inside                                                                          Closed Containment Isolation Check Valve Component Cooling Water        CCS-PL-V200  Yes    Yes        Yes    Yes/No  Yes (Valve  Yes/No  Transfer  As Is System (CCS) Containment                                                          Position)          Closed Isolation Motor-operated Valve (MOV) - Inlet Line Outside Reactor Containment (ORC)
No CCS-PL-V201  Yes    Yes          No      -/-                  -/-    Transfer    -
CCS Containment Isolation                                                                              Closed Check Valve - Inlet Line Inside Reactor Containment (IRC)
CCS Containment Isolation MOV  CCS-PL-V207  Yes    Yes        Yes    Yes/Yes  Yes (Valve  Yes/No  Transfer  As Is
- Outlet Line IRC                                                                  Position)          Closed CCS Containment Isolation MOV  CCS-PL-V208  Yes    Yes        Yes    Yes/No  Yes (Valve  Yes/No  Transfer  As Is
- Outlet Line ORC                                                                  Position)          Closed CCS Containment Isolation      CCS-PL-220    Yes    Yes          No      -/-      No        -/-    Transfer    -
Relief Valve - Outlet Line IRC                                                                        Closed/
Transfer Open C-92
 
Table 2.2.1-1 ASME                        Class 1E/                              Loss of Code              Remotely Qual. for  Safety-                      Motive Section Seismic    Operated  Harsh    Related    Control  Active    Power Equipment Name                Tag No. III    Cat. I      Valve  Envir. Display  PMS/DAS  Function  Position Demineralized Water Supply      DWS-PL-V244  Yes    Yes          No      -/-      No        -/-    None      -
Containment Isolation Valve ORC Demineralized Water Supply      DWS-PL-V245  Yes    Yes          No      -/-      No        -/-    Transfer    -
Containment Isolation Check                                                                            Closed Valve IRC Fuel Transfer Tube              FHS-FT-001    Yes    Yes          -      -/-        -        -/-      -        -
Fuel Transfer Tube Isolation    FHS-PL-V001  Yes    Yes          -      -/-        -        -/-    Transfer    -
Valve                                                                                                  Closed Fire Water Containment Supply    FPS-PL-V050  Yes    Yes          No      -/-      No        -/-    None      -
Isolation Valve - Outside Fire Water Containment Isolation FPS-PL-V052  Yes    Yes          No      -/-      No        -/-    Transfer    -
Supply Check Valve - Inside                                                                            Closed Spent Fuel Pool Cooling System  SFS-PL-V037  Yes    Yes          No      -/-      No        -/-    Transfer    -
(SFS) Discharge Line                                                                                    Closed Containment Isolation Check Valve - IRC SFS Discharge Line Containment  SFS-PL-V038  Yes    Yes        Yes    Yes/No  Yes (Valve  Yes/No  Transfer  As Is Isolation MOV - ORC                                                                Position)          Closed SFS Suction Line Containment    SFS-PL-V034  Yes    Yes        Yes    Yes/Yes  Yes (Valve  Yes/No  Transfer  As Is Isolation MOV - IRC                                                                Position)          Closed Yes (Valve SFS Suction Line Containment    SFS-PL-V035  Yes    Yes        Yes    Yes/No    Position)  Yes/No  Transfer  As Is Isolation MOV - ORC                                                                                    Closed No SFS Suction Line Containment    SFS-PL-V067  Yes    Yes          No      -/-                  -/-    Transfer    -
Isolation Relief Valve - IRC                                                                            Closed/
Transfer Open C-93
 
Table 2.2.1-1 ASME                        Class 1E/                              Loss of Code              Remotely Qual. for  Safety-                      Motive Section Seismic    Operated  Harsh    Related    Control  Active    Power Equipment Name            Tag No. III    Cat. I      Valve  Envir. Display  PMS/DAS  Function  Position Containment Purge Inlet      VFS-PL-V003  Yes    Yes        Yes    Yes/No      Yes      Yes/Yes  Transfer  Closed Containment Isolation Valve -                                                    (Valve              Closed ORC                                                                              Position)
Containment Purge Inlet      VFS-PL-V004  Yes    Yes        Yes    Yes/Yes    Yes      Yes/Yes  Transfer  Closed Containment Isolation Valve -                                                    (Valve              Closed IRC                                                                              Position)
Integrated Leak Rate Testing  VFS-PL-V008  Yes    Yes          No      -/-        No        -/-    None        -
Vent Discharge Containment Isolation Valve - ORC Containment Purge Discharge  VFS-PL-V009  Yes    Yes        Yes    Yes/Yes  Yes (Valve  Yes/Yes  Transfer  Closed Containment Isolation Valve -                                                    Position)            Closed IRC Yes (Valve Containment Purge Discharge  VFS-PL-V010  Yes    Yes        Yes    Yes/No    Position)  Yes/Yes  Transfer  Closed Containment Isolation Valve -                                                                        Closed ORC C-94
 
Table 2.2.1-1 ASME                        Class 1E/                              Loss of Code              Remotely Qual. for  Safety-                      Motive Section Seismic    Operated  Harsh    Related    Control  Active    Power Equipment Name            Tag No. III    Cat. I      Valve  Envir. Display  PMS/DAS  Function  Position Vacuum Relief Containment      VFS-PL-V800A  Yes    Yes        Yes    Yes/No  Yes (Valve  Yes/No  Transfer  As Is Isolation A - ORC                                                                  Position)          Closed/
Transfer Open Yes (Valve Vacuum Relief Containment      VFS-PL-V800B  Yes    Yes        Yes    Yes/No    Position)  Yes/No  Transfer  As Is Isolation B - ORC                                                                                      Closed/
Transfer No                Open Vacuum Relief Containment      VFS-PL-V803A  Yes    Yes          No      -/-                  -/-    Transfer    -
Isolation Check Valve A - IRC                                                                          Closed/
Transfer No                Open Vacuum Relief Containment      VFS-PL-V803B  Yes    Yes          No      -/-                  -/-    Transfer    -
Isolation Check Valve B - IRC                                                                          Closed/
Transfer Open Fan Coolers Return Containment VWS-PL-V082    Yes    Yes        Yes    Yes/Yes  Yes (Valve  Yes/No  Transfer  Closed Isolation Valve - IRC                                                              Position)          Closed Yes (Valve Fan Coolers Return Containment VWS-PL-V086    Yes    Yes        Yes    Yes/No    Position)  Yes/No  Transfer  Closed Isolation Valve - ORC                                                                                  Closed No Fan Coolers Return Containment VWS-PL-V080    Yes    Yes          No      -/-                  -/-    Transfer    -
Isolation Relief Valve - IRC                                                                          Closed/
Transfer Open C-95
 
Table 2.2.1-1 ASME                        Class 1E/                              Loss of Code              Remotely Qual. for  Safety-                      Motive Section Seismic    Operated  Harsh    Related    Control  Active    Power Equipment Name            Tag No. III    Cat. I      Valve  Envir. Display  PMS/DAS  Function  Position Fan Coolers Supply Containment VWS-PL-V058  Yes    Yes        Yes    Yes/No      Yes      Yes/No  Transfer  Closed Isolation Valve - ORC                                                              (Valve            Closed Position)
Fan Coolers Supply Containment VWS-PL-V062  Yes    Yes          No      -/-        No        -/-    Transfer    -
Isolation Check Valve - IRC                                                                          Closed Reactor Coolant Drain Tank    WLS-PL-V067  Yes    Yes        Yes    Yes/Yes  Yes (Valve  Yes/No  Transfer  Closed (RCDT) Gas Outlet Containment                                                    Position)          Closed Isolation Valve - IRC Yes (Valve RCDT Gas Outlet Containment    WLS-PL-V068  Yes    Yes        Yes    Yes/No    Position)  Yes/No  Transfer  Closed Isolation Valve - ORC                                                                                Closed Sump Discharge Containment    WLS-PL-V055  Yes    Yes        Yes    Yes/Yes  Yes (Valve  Yes/Yes  Transfer  Closed Isolation Valve - IRC                                                            Position)          Closed Yes (Valve Sump Discharge Containment    WLS-PL-V057  Yes    Yes        Yes    Yes/No    Position)  Yes/Yes  Transfer  Closed Isolation Valve - ORC                                                                                Closed Sump Discharge Containment    WLS-PL-V058  Yes    Yes          No      -/-        No        -/-    Transfer    -
Isolation Relief Valve - IRC                                                                          Closed/
Transfer Open Spare Penetration              CNS-PY-C01    Yes    Yes          -      -/-        -        -/-      -        -
Spare Penetration              CNS-PY-C02    Yes    Yes          -      -/-        -        -/-      -        -
Spare Penetration              CNS-PY-C03    Yes    Yes          -      -/-        -        -/-      -        -
Main Equipment Hatch          CNS-MY-Y01    Yes    Yes          -      -/-        -        -/-      -        -
Maintenance Hatch              CNS-MY-Y02    Yes    Yes          -      -/-        -        -/-      -        -
Personnel Hatch                CNS-MY-Y03    Yes    Yes          -      -/-        -        -/-      -        -
Personnel Hatch                CNS-MY-Y04    Yes    Yes          -      -/-        -        -/-      -        -
C-96
 
Table 2.2.1-1 ASME                        Class 1E/                          Loss of Code              Remotely Qual. for Safety-                  Motive Section Seismic    Operated  Harsh    Related  Control  Active  Power Equipment Name          Tag No. III    Cat. I      Valve  Envir. Display PMS/DAS  Function Position Containment Vessel        CNS-MV-01      Yes    Yes          -      -/-      -      -/-      -        -
Electrical Penetration P03 DAS-EY-P03Z    Yes    Yes          -    No/Yes      -      -/-      -        -
Electrical Penetration P01 ECS-EY-P01X    Yes    Yes          -    No/Yes      -      -/-      -        -
Electrical Penetration P02 ECS-EY-P02X    Yes    Yes          -    No/Yes      -      -/-      -        -
Electrical Penetration P06 ECS-EY-P06Y    Yes    Yes          -    No/Yes      -      -/-      -        -
Electrical Penetration P09 ECS-EY-P09W    Yes    Yes          -    No/Yes      -      -/-      -        -
Electrical Penetration P10 ECS-EY-P10W    Yes    Yes          -    No/Yes      -      -/-      -        -
Electrical Penetration P11 IDSA-EY-P11Z  Yes    Yes          -    Yes/Yes    -      -/-      -        -
Electrical Penetration P12 IDSA-EY-P12Y  Yes    Yes          -    Yes/Yes    -      -/-      -        -
Electrical Penetration P13 IDSA-EY-P13Y  Yes    Yes          -    Yes/Yes    -      -/-      -        -
Electrical Penetration P14 IDSD-EY-P14Z  Yes    Yes          -    Yes/Yes    -      -/-      -        -
Electrical Penetration P15 IDSD-EY-P15Y  Yes    Yes          -    Yes/Yes    -      -/-      -        -
Electrical Penetration P16 IDSD-EY-P16Y  Yes    Yes          -    Yes/Yes    -      -/-      -        -
Electrical Penetration P18 ECS-EY-P18X    Yes    Yes          -    No/Yes      -      -/-      -        -
Electrical Penetration P21 EDS-EY-P21Z    Yes    Yes          -    No/Yes      -      -/-      -        -
Electrical Penetration P22 ECS-EY-P22X    Yes    Yes          -    No/Yes      -      -/-      -        -
Electrical Penetration P23 ECS-EY-P23X    Yes    Yes          -    No/Yes      -      -/-      -        -
Electrical Penetration P24 ECS-EY-P24    Yes    Yes          -    No/Yes      -      -/-      -        -
Electrical Penetration P25 ECS-EY-P25W    Yes    Yes          -    No/Yes      -      -/-      -        -
Electrical Penetration P26 ECS-EY-P26W    Yes    Yes          -    No/Yes      -      -/-      -        -
Electrical Penetration P27 IDSC-EY-P27Z  Yes    Yes          -    Yes/Yes    -      -/-      -        -
Electrical Penetration P28 IDSC-EY-P28Y  Yes    Yes          -    Yes/Yes    -      -/-      -        -
C-97
 
Table 2.2.1-1 ASME                        Class 1E/                          Loss of Code              Remotely Qual. for Safety-                  Motive Section Seismic    Operated  Harsh    Related  Control  Active  Power Equipment Name                  Tag No. III    Cat. I      Valve  Envir. Display PMS/DAS  Function Position Electrical Penetration P29        IDSC-EY-P29Y  Yes    Yes          -    Yes/Yes    -      -/-      -        -
Electrical Penetration P30        IDSB-EY-P30Z  Yes    Yes          -    Yes/Yes    -      -/-      -        -
Electrical Penetration P31        IDSB-EY-P31Y  Yes    Yes          -    Yes/Yes    -      -/-      -        -
Electrical Penetration P32        IDSB-EY-P32Y  Yes    Yes          -    Yes/Yes    -      -/-      -        -
Instrument Penetration P46        PCS-PY-C01    Yes    Yes          -      -/-      -      -/-      -        -
Instrument Penetration P47        PCS-PY-C02    Yes    Yes          -      -/-      -      -/-      -        -
Instrument Penetration P48        PCS-PY-C03    Yes    Yes          -      -/-      -      -/-      -        -
Instrument Penetration P49        PCS-PY-C04    Yes    Yes          -      -/-      -      -/-      -        -
Note: Dash (-) indicates not applicable.
C-98
 
Table 2.2.1-2 ASME Code Line Name                              Line Number          Section III Instrument Air In                                            CAS-PL-L015            Yes Service Air In                                                CAS-PL-L204            Yes Component Cooling Water Supply to Containment                CCS-PL-L201            Yes Component Cooling Water Outlet from Containment              CCS-PL-L207            Yes Demineralized Water In                                    DWS-PL-L245, L230          Yes Fire Protection Supply to Containment                        FPS-PL-L107            Yes Spent Fuel Pool Cooling Discharge                            SFS-PL-L017            Yes Spent Fuel Pool Cooling Suction from Containment              SFS-PL-L038            Yes Containment Purge Inlet to Containment                  VFS-PL-L104, L105, L106      Yes Containment Purge Discharge from Containment            VFS-PL-L203, L204, L205,      Yes L800, L801A/B, L803, L804, L805A/B Fan Cooler Supply Line to Containment                        VWS-PL-L032              Yes Fan Cooler Return Line from Containment                      VWS-PL-L055              Yes RCDT Gas Out                                                  WLS-PL-L022            Yes Waste Sump Out                                                WLS-PL-L073            Yes C-99
 
Table 2.2.1-3 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No.                Design Commitment                  Inspections, Tests, Analyses    Acceptance Criteria 90  2.2.01.01    1. The functional arrangement of the CNS      Inspection of the as-built    The as-built CNS conforms and associated systems is as described in    system will be performed. with the functional the Design Description of this Section                                      arrangement as described in 2.2.1.                                                                      the Design Description of this Section 2.2.1.
91  2.2.01.02a  2.a) The components identified in Table      Inspection will be conducted  The ASME Code Section III 2.2.1-1 as ASME Code Section III are          of the as-built components as design reports exist for the designed and constructed in accordance        documented in the ASME        as-built components with ASME Code Section III requirements.      design reports.              identified in Table 2.2.1-1 as ASME Code Section III./
92  2.2.01.02b  2.b) The piping identified in Table 2.2.1-2  Inspection will be conducted  The ASME Code Section III as ASME Code Section III is designed and      of the as-built piping as    design reports exist for the constructed in accordance with ASME          documented in the ASME        as-built piping identified in Code Section III requirements.                design reports.              Table 2.2.1-2 as ASME Code Section III.
93  2.2.01.03a  3.a) Pressure boundary welds in              Inspection of the as-built    A report exists and components identified in Table 2.2.1-1 as    pressure boundary welds will  concludes that the ASME ASME Code Section III meet ASME Code          be performed in accordance    Code Section III Section III requirements.                    with the ASME Code Section    requirements are met for III.                          non-destructive examination of pressure boundary welds.
94  2.2.01.03b  3.b) Pressure boundary welds in piping        Inspection of the as-built    A report exists and identified in Table 2.2.1-2 as ASME Code      pressure boundary welds will  concludes that the ASME Section III meet ASME Code Section III        be performed in accordance    Code Section III requirements.                                with the ASME Code Section    requirements are met for III.                          non-destructive examination of pressure boundary welds.
95  2.2.01.04a.i  4.a) The components identified in Table      i) A hydrostatic or pressure  i) A report exists and 2.2.1-1 as ASME Code Section III retain      test will be performed on the concludes that the results of their pressure boundary integrity at their    components required by the    the pressure test of the design pressure.                              ASME Code Section III to be  components identified in tested.                      Table 2.2.1-1 as ASME Code Section III conform with the requirements of the ASME Code Section III.
96  2.2.01.04a.ii 4.a) The components identified in Table      ii) Impact testing will be    ii) A report exists and 2.2.1-1 as ASME Code Section III retain      performed on the containment  concludes that the their pressure boundary integrity at their    and pressure-retaining        containment and pressure-design pressure.                              penetration materials in      retaining penetration accordance with the ASME      materials conform with Code Section III, Subsection  fracture toughness NE, to confirm the fracture  requirements of the ASME toughness of the materials. Code Section III.
C-100
 
Table 2.2.1-3 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No.                Design Commitment                  Inspections, Tests, Analyses        Acceptance Criteria 97  2.2.01.04b  4.b) The piping identified in Table 2.2.1-2    A hydrostatic or pressure test  A report exists and as ASME Code Section III retains its          will be performed on the        concludes that the results of pressure boundary integrity at its design      piping required by the ASME    the pressure test of the pressure.                                      Code Section III to be          piping identified in pressure tested.                Table 2.2.1-2 as ASME Code Section III conform with the requirements of the ASME Code Section III.
98  2.2.01.05.i  5. The seismic Category I equipment            i) Inspection will be          i) The seismic Category I identified in Table 2.2.1-1 can withstand      performed to verify that the    equipment identified in seismic design basis loads without loss of    seismic Category I equipment    Table 2.2.1-1 is located on structural integrity and safety function.      and valves identified in Table  the Nuclear Island.
2.2.1-1 are located on the Nuclear Island.
99  2.2.01.05.ii 5. The seismic Category I equipment            ii) Type tests, analyses, or a  ii) A report exists and identified in Table 2.2.1-1 can withstand      combination of type tests and  concludes that the seismic seismic design basis loads without loss of    analyses of seismic Category I  Category I equipment can structural integrity and safety function.      equipment will be performed. withstand seismic design basis dynamic loads without loss of structural integrity and safety function.
100 2.2.01.05.iii 5. The seismic Category I equipment            iii) Inspection will be        iii) The as-built equipment identified in Table 2.2.1-1 can withstand      performed for the existence of  including anchorage is seismic design basis loads without loss of    a report verifying that the as- seismically bounded by the structural integrity and safety function.      built equipment including      tested or analyzed anchorage is seismically        conditions.
bounded by the tested or analyzed conditions.
101 2.2.01.06a.i  6.a) The Class 1E equipment identified in      i) Type tests, analyses, or a  i) A report exists and Table 2.2.1-1 as being qualified for a harsh  combination of type tests and  concludes that the Class 1E environment can withstand the                  analyses will be performed on  equipment identified in environmental conditions that would exist      Class 1E equipment located in  Table 2.2.1-1 as being before, during, and following a design        a harsh environment.            qualified for a harsh basis accident without loss of safety                                          environment can withstand function for the time required to perform                                      the environmental the safety function.                                                          conditions that would exist before, during, and following a design basis accident without loss of safety function for the time required to perform the safety function.
C-101
 
Table 2.2.1-3 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No.                  Design Commitment                  Inspections, Tests, Analyses      Acceptance Criteria 102 2.2.01.06a.ii 6.a) The Class 1E equipment identified in      ii) Inspection will be          ii) A report exists and Table 2.2.1-1 as being qualified for a harsh  performed of the as-built      concludes that the as-built environment can withstand the                  Class 1E equipment and the      Class 1E equipment and the environmental conditions that would exist      associated wiring, cables, and  associated wiring, cables, before, during, and following a design        terminations located in a      and terminations identified basis accident without loss of safety          harsh environment.              in Table 2.2.1-1 as being function for the time required to perform                                      qualified for a harsh the safety function.                                                          environment are bounded by type tests, analyses, or a combination of type tests and analyses.
103  2.2.01.06b  6.b) The Class 1E components identified        Testing will be performed by    A simulated test signal in Table 2.2.1-1 are powered from their        providing a simulated test      exists at the Class 1E respective Class 1E division.                  signal in each Class 1E        equipment identified in division.                      Table 2.2.1-1 when the assigned Class 1E division is provided the test signal.
104  2.2.01.06c  6.c) Separation is provided between CNS        See ITAAC Table 3.3-6, item    See ITAAC Table 3.3-6, Class 1E divisions, and between Class 1E      7.d.                            item 7.d.
divisions and non-Class 1E cable.
105 2.2.01.06d.i  6.d) The non-Class 1E electrical              i) Type tests, analyses, or a  i) A report exists and penetrations identified in Table 2.2.1-1 as    combination of type tests and  concludes that the non-Class being qualified for a harsh environment can    analyses will be performed on  1E electrical penetrations withstand the environmental conditions        non-Class 1E electrical        identified in Table 2.2.1-1 as that would exist before, during, and          penetrations located in a harsh being qualified for a harsh following a design basis accident without      environment.                    environment can withstand loss of containment pressure boundary                                          the environmental conditions integrity.                                                                    that would exist before, during, and following a design basis accident without loss of containment pressure boundary integrity.
106 2.2.01.06d.ii 6.d) The non-Class 1E electrical              ii) Inspection will be          ii) A report exists and penetrations identified in Table 2.2.1-1 as    performed of the as-built non-  concludes that the as-built being qualified for a harsh environment can    Class 1E electrical            non-Class 1E electrical withstand the environmental conditions        penetrations located in a harsh penetrations identified in that would exist before, during, and          environment.                    Table 2.2.1-1 as being following a design basis accident without                                      qualified for a harsh loss of containment pressure boundary                                          environment are bounded by integrity.                                                                    type tests, analyses, or a combination of type tests and analyses.
C-102
 
Table 2.2.1-3 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No.                Design Commitment                  Inspections, Tests, Analyses      Acceptance Criteria 107  2.2.01.07.i  7. The CNS provides the safety-related        i) A containment integrated    i) The leakage rate from function of containment isolation for          leak rate test will be        containment for the containment boundary integrity and            performed.                    integrated leak rate test is provides a barrier against the release of                                    less than La.
fission products to the atmosphere.
108  2.2.01.07.ii 7. The CNS provides the safety-related        ii) Testing will be performed  ii) The containment purge function of containment isolation for          to demonstrate that remotely  isolation valves (VFS-PL-containment boundary integrity and            operated containment          V003, -V004, -V009, and -
provides a barrier against the release of      isolation valves close within  V010) close within fission products to the atmosphere.            the required response times. 20 seconds, containment vacuum relief isolation valves (VFS-PL-V800A and
                                                                                                -V800B) close within 30 seconds, SGS valves SGS-PL-V040A/B and SGS-PL-V057A/B are covered in subsection 2.2.4, Table 2.2.4-4 (item 11.b.ii) and all other containment isolation valves close within 60 seconds upon receipt of an actuation signal.
109  2.2.01.08  8. Containment electrical penetration          An analysis for the as-built  Analysis exists for the as-assemblies are protected against currents      containment electrical        built containment electrical that are greater than the continuous ratings. penetration assemblies will be penetration assemblies and performed to demonstrate (1)  concludes that the that the maximum current of    penetrations are protected the circuits does not exceed  against currents which are the continuous rating of the  greater than their continuous containment electrical        ratings.
penetration assembly, or (2) that the circuits have redundant protection devices in series and that the redundant current protection devices are coordinated with the containment electrical penetration assemblys rated short circuit thermal capacity data and prevent current from exceeding the continuous current rating of the containment electrical penetration assembly.
C-103
 
Table 2.2.1-3 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No.                  Design Commitment                  Inspections, Tests, Analyses          Acceptance Criteria 110  2.2.01.09    9. Safety-related displays identified in      Inspection will be performed      Safety-related displays Table 2.2.1-1 can be retrieved in the MCR. for retrievability of the safety- identified in Table 2.2.1-1 related displays in the MCR.      can be retrieved in the MCR.
111  2.2.01.10a  10.a) Controls exist in the MCR to cause      Stroke testing will be            Controls in the MCR those remotely operated valves identified    performed on remotely            operate to cause remotely in Table 2.2.1-1 to perform active            operated valves identified in    operated valves identified in functions.                                    Table 2.2.1-1 using the          Table 2.2.1-1 to perform controls in the MCR.              active safety functions.
112  2.2.01.10b    10.b) The valves identified in Table 2.2.1-  Testing will be performed on      The remotely operated 1 as having PMS control perform an active    remotely operated valves          valves identified in safety function after receiving a signal      listed in Table 2.2.1-1 using    Table 2.2.1-1 as having from the PMS.                                real or simulated signals into    PMS control perform the the PMS.                          active function identified in the table after receiving a signal from PMS.
113  2.2.01.10c  10.c) The valves identified in Table 2.2.1-1  Testing will be performed on      The remotely operated as having DAS control perform an active      remotely operated valves          valves identified in safety function after receiving a signal      listed in Table 2.2.1-1 using    Table 2.2.1-1 as having from DAS.                                    real or simulated signals into    DAS control perform the the DAS.                          active function identified in the table after receiving a signal from DAS.
114  2.2.01.11a.i  11.a) The motor-operated and check valves    i) Tests or type tests of        i) A test report exists and identified in Table 2.2.1-1 perform an        motor-operated valves will be    concludes that each motor-active safety-related function to change      performed to demonstrate the      operated valve changes position as indicated in the table.          capability of each valve to      position as indicated in operate under design              Table 2.2.1-1 under design conditions.                      conditions.
115 2.2.01.11a.ii  11.a) The motor-operated and check valves    ii) Inspection will be            ii) A report exists and identified in Table 2.2.1-1 perform an        performed for the existence of    concludes that the as-built active safety-related function to change      a report verifying that the as-  motor-operated valves are position as indicated in the table.          built motor-operated valves      bounded by the tests or type are bounded by the tests or      tests.
type tests.
116 2.2.01.11a.iii 11.a) The motor-operated and check valves    iii) Tests of the motor-          iii) Each motor-operated identified in Table 2.2.1-1 perform an        operated valves will be          valve changes position as active safety-related function to change      performed under                  indicated in Table 2.2.1-1 position as indicated in the table.          preoperational flow,              under pre-operational test differential pressure, and        conditions.
temperature conditions.
C-104
 
Table 2.2.1-3 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No.                Design Commitment                    Inspections, Tests, Analyses          Acceptance Criteria 117 2.2.01.11a.iv 11.a) The motor-operated and check valves      iv) Exercise testing of the        iv) Each check valve identified in Table 2.2.1-1 perform an          check valves with active          changes position as active safety-related function to change        safety functions identified in    indicated in Table 2.2.1-1.
position as indicated in the table.            Table 2.2.1-1 will be performed under preoperational test pressure, temperature and fluid flow conditions.
118  2.2.01.11b  11.b) After loss of motive power, the          Testing of the remotely            After loss of motive power, remotely operated valves identified in          operated valves will be            each remotely operated Table 2.2.1-1 assume the indicated loss of      performed under the                valve identified in Table motive power position.                          conditions of loss of motive      2.2.1-1 assumes the power.                            indicated loss of motive power position.
Table 2.2.1-4 Component Name                              Tag No.                          Component Location Containment Vessel                                CNS-MV-01                              Shield Building C-105
 
Figure 2.2.1-1 Containment System C-106
 
2.2.2          Passive Containment Cooling System Design Description The passive containment cooling system (PCS) removes heat from the containment during design basis events.
The PCS is as shown in Figure 2.2.2-1 and the component locations of the PCS are as shown in Table 2.2.2-4.
: 1. The functional arrangement of the PCS is as described in the Design Description of this Section 2.2.2.
: 2. a) The components identified in Table 2.2.2-1 as ASME Code Section III are designed and constructed in accordance with ASME Code Section III requirements.
b) The pipelines identified in Table 2.2.2-2 as ASME Code Section III are designed and constructed in accordance with ASME Code Section III requirements.
: 3. a) Pressure boundary welds in components identified in Table 2.2.2-1 as ASME Code Section III meet ASME Code Section III requirements.
b) Pressure boundary welds in the pipelines identified in Table 2.2.2-2 as ASME Code Section III meet ASME Code Section III requirements.
: 4. a) The components identified in Table 2.2.2-1 as ASME Code Section III retain their pressure boundary integrity at their design pressure.
b) The pipelines identified in Table 2.2.2-2 as ASME Code Section III retain their pressure boundary integrity at their design pressure.
: 5. a) The seismic Category I components identified in Table 2.2.2-1 can withstand seismic design basis loads without loss of safety function.
b) Each of the pipelines identified in Table 2.2.2-2 for which functional capability is required is designed to withstand combined normal and seismic design basis loads without a loss of its functional capability.
c) The passive containment cooling ancillary water storage tank (PCCAWST) can withstand a seismic event.
: 6. a) The Class 1E components identified in Table 2.2.2-1 as being qualified for a harsh environment can withstand the environmental conditions that would exist before, during, and following a design basis accident without loss of safety function for the time required to perform the safety function.
b) The Class 1E components identified in Table 2.2.2-1 are powered from their respective Class 1E division.
c) Separation is provided between PCS Class 1E divisions, and between Class 1E divisions and non-Class 1E cable.
: 7. The PCS performs the following safety-related functions:
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a) The PCS delivers water from the PCCWST to the outside, top of the containment vessel.
b) The PCS wets the outside surface of the containment vessel. The inside and outside of the containment vessel above the operating deck are coated with an inorganic zinc coating.
c) The PCS provides air flow over the outside of the containment vessel by a natural circulation air flow path from the air inlets to the air discharge structure.
d) The PCS drains the excess water from the outside of the containment vessel through the two upper annulus drains.
e) The PCS provides a flow path for long-term water makeup to the passive containment cooling water storage tank (PCCWST).
f) The PCS provides a flow path for long-term water makeup from the PCCWST to the spent fuel pool.
: 8. The PCS performs the following nonsafety-related functions:
a) The PCCAWST contains an inventory of cooling water sufficient for PCS containment cooling from hour 72 through day 7.
b) The PCS delivers water from the PCCAWST to the PCCWST and spent fuel pool simultaneously.
c) The PCCWST includes a water inventory for the fire protection system.
: 9. Safety-related displays identified in Table 2.2.2-1 can be retrieved in the main control room (MCR).
: 10. a) Controls exist in the MCR to cause the remotely operated valves identified in Table 2.2.2-1 to perform active functions.
b) The valves identified in Table 2.2.2-1 as having protection and safety monitoring system (PMS) control perform an active safety function after receiving a signal from the PMS.
c) The valves identified in Table 2.2.2-1 as having diverse actuation system (DAS) control perform an active safety function after receiving a signal from the DAS.
: 11. a) The motor-operated valves identified in Table 2.2.2-1 perform an active safety-related function to change position as indicated in the table.
b) After loss of motive power, the remotely operated valves identified in Table 2.2.2-1 assume the indicated loss of motive power position.
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Table 2.2.2-1 ASME                        Class 1E/                            Loss of Code              Remotely  Qual. Safety-  Control          Motive Section Seismic    Operated for Harsh Related    PMS/    Active  Power Component Name            Tag No. III    Cat. I      Valve    Envir. Display    DAS    Function Position PCCWST                        PCS-MT-01    No      Yes          -        -        -        -      -        -
Water Distribution Bucket    PCS-MT-03    No      Yes          -        -        -        -      -        -
Water Distribution Wiers      PCS-MT-04    No      Yes          -        -        -        -      -        -
PCCWST Isolation Valve      PCS-PL-V001A  Yes      Yes          Yes    Yes/No    Yes    Yes/Yes Transfer  Open (Valve            Open Position)
PCCWST Isolation Valve      PCS-PL-V001B  Yes      Yes          Yes    Yes/No    Yes    Yes/Yes Transfer  Open (Valve            Open Position)
PCCWST Isolation Valve      PCS-PL-V001C  Yes      Yes          Yes    Yes/No    Yes    Yes/Yes Transfer  As Is (Valve            Open Position)
PCCWST Isolation Block      PCS-PL-V002A  Yes      Yes          Yes    Yes/No    Yes    Yes/No  Transfer  As Is MOV                                                                              (Valve            Open Position)
PCCWST Isolation Block      PCS-PL-V002B  Yes      Yes          Yes    Yes/No    Yes    Yes/No  Transfer  As Is MOV                                                                              (Valve            Open Position)
PCCWST Isolation Block      PCS-PL-V002C  Yes      Yes          Yes    Yes/No    Yes    Yes/No  Transfer  As Is MOV                                                                              (Valve            Open Position)
PCS Recirculation Return    PCS-PL-V023  Yes      Yes          -      -/No      No        -    Transfer    -
Isolation Valve                                                                                    Close PCCWST Supply to Fire        PCS-PL-V005  Yes      Yes          -      -/No      No        -    Transfer    -
Protection System Isolation                                                                        Close Valve PCS Makeup to SFS            PCS-PL-V009  Yes      Yes          -      -/No      No        -    Transfer    -
Isolation Valve                                                                                    Open/
Transfer Close C-109
 
Table 2.2.2-1 ASME                        Class 1E/                            Loss of Code              Remotely  Qual. Safety- Control            Motive Section Seismic    Operated for Harsh Related  PMS/    Active    Power Component Name          Tag No. III    Cat. I      Valve    Envir. Display  DAS    Function  Position Water Makeup Isolation    PCS-PL-V044  Yes      Yes          -      -/No    No      -    Transfer    -
Valve                                                                                          Open Water Bucket Makeup Line  PCS-PL-V015  Yes      Yes          -      -/No    No      -    Transfer    -
Drain Valve                                                                                    Close Water Bucket Makeup Line  PCS-PL-V020  Yes      Yes          -      -/No    No      -    Transfer    -
Isolation Valve                                                                                Open PCCWST Long-Term          PCS-PL-V039  Yes      Yes          -      -/No    No      -    Transfer    -
Makeup Line Check Valve                                                                        Open PCCWST Long-Term          PCS-PL-V042  Yes      Yes          -      -/No    No      -    Transfer    -
Makeup Drain Isolation                                                                          Close PCS Discharge to SFS Pool  PCS-PL-V045  Yes      Yes          -      -/No    No      -    Transfer    -
Isolation Valve                                                                                Open Recirc Header Discharge to PCS-PL-V046  Yes      Yes          -      -/No    No      -    Transfer    -
PCCWST Isolation Valve                                                                          Close PCCWST Drain Isolation    PCS-PL-V049  Yes      Yes          -      -/No    No      -    Transfer    -
Valve                                                                                          Close Recirc Header Discharge to PCS-PL-V050  Yes      Yes          -      -/No    No      -    Transfer    -
SFS Pool Isolation Valve                                                                      Open/Close PCCWST Discharge to SFS    PCS-PL-V051  Yes      Yes          -      -/No    No      -    Transfer    -
Pool Isolation Valve                                                                          Open/Close PCS Water Delivery Flow      PCS-001    No      Yes          -    Yes/No    Yes      -        -        -
Sensor PCS Water Delivery Flow      PCS-002    No      Yes          -    Yes/No    Yes      -        -        -
Sensor PCS Water Delivery Flow      PCS-003    No      Yes          -    Yes/No    Yes      -        -        -
Sensor PCS Water Delivery Flow      PCS-004    No      Yes          -    Yes/No    Yes      -        -        -
Sensor C-110
 
Table 2.2.2-1 ASME                        Class 1E/                          Loss of Code              Remotely  Qual. Safety- Control          Motive Section Seismic    Operated for Harsh Related  PMS/    Active  Power Component Name              Tag No. III    Cat. I      Valve    Envir. Display  DAS    Function Position Containment Pressure              PCS-005  No      Yes          -    Yes/Yes  Yes      -      -        -
Sensor Containment Pressure              PCS-006  No      Yes          -    Yes/Yes  Yes      -      -        -
Sensor Containment Pressure              PCS-007  No      Yes          -    Yes/Yes  Yes      -      -        -
Sensor Containment Pressure              PCS-008  No      Yes          -    Yes/Yes  Yes      -      -        -
Sensor PCCWST Water Level                PCS-010  No      Yes          -    Yes/No    Yes      -      -        -
Sensor PCCWST Water Level                PCS-011  No      Yes          -    Yes/No    Yes      -      -        -
Sensor High-range Containment            PCS-012  No      Yes          -    Yes/Yes  Yes      -      -        -
Pressure Sensor High-range Containment            PCS-013  No      Yes          -    Yes/Yes  Yes      -      -        -
Pressure Sensor High-range Containment            PCS-014  No      Yes          -    Yes/Yes  Yes      -      -        -
Pressure Sensor Note: Dash (-) indicates not applicable.
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Table 2.2.2-2 Functional ASME Code    Capability Pipeline Name                  Line Number            Section III  Required PCCWST Discharge Lines              PCS-PL-L001A/B/C/D            Yes        Yes PCCWST Discharge Cross-connect            PCS-PL-L002              Yes        Yes Line PCCWST Discharge Header Lines          PCS-PL-L003A/B              Yes        Yes PCS-PL-L005 Post-72-hour Supply Line Connection      PCS-PL-L051              Yes        Yes PCS-PL-L054 PCS-PL-L065 Post-72-hour Containment Cooling          PCS-PL-L004              Yes        Yes Makeup From Supply Line                  PCS-PL-L007 Connections                              PCS-PL-L008 PCS-PL-L023 PCS-PL-L050 Post-72-hour SFS Makeup From              PCS-PL-L011              Yes        Yes PCCWST                                    PCS-PL-L017 PCS-PL-L018 PCS-PL-L030*
PCS-PL-L073 Post-72-hour SFS Makeup From              PCS-PL-L025              Yes        Yes Supply Line Connection                    PCS-PL-L029 PCS-PL-L030*
PCS-PL-L048 PCS-PL-L049 Note:
* Line PCS-PL-L030 is a common makeup line from both sources.
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Table 2.2.2-3 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No.        Design Commitment                Inspections, Tests, Analyses            Acceptance Criteria 119  2.2.02.01  1. The functional arrangement        Inspection of the as-built system  The as-built PCS conforms to the of the PCS is as described in        will be performed.                  functional arrangement as the Design Description of this                                          described in the Design Section 2.2.2.                                                          Description of this Section 2.2.2.
120  2.2.02.02a 2.a) The components identified      Inspection will be conducted of    The ASME Code Section III in Table 2.2.2-1 as ASME Code        the as-built components as          design reports exist for the as-Section III are designed and        documented in the ASME design      built components identified in constructed in accordance with      reports.                            Table 2.2.2-1 as ASME Code ASME Code Section III                                                    Section III.
requirements.
121  2.2.02.02b 2.b) The pipelines identified in    Inspection will be conducted of    The ASME Code Section III Table 2.2.2-2 as ASME Code          the as-built piping as documented  design reports exist for the as-Section III are designed and        in the ASME design reports.        built piping identified in constructed in accordance with                                          Table 2.2.2-2 as ASME Code ASME Code Section III                                                    Section III.
requirements.
122  2.2.02.03a 3.a) Pressure boundary welds        Inspection of the as-built pressure A report exists and concludes that in components identified in          boundary welds will be performed    the ASME Code Section III Table 2.2.2-1 as ASME Code          in accordance with the ASME        requirements are met for non-Section III meet ASME Code          Code Section III.                  destructive examination of Section III requirements.                                                pressure boundary welds.
123  2.2.02.03b 3.b) Pressure boundary welds        Inspection of the as-built pressure A report exists and concludes that in the pipelines identified in      boundary welds will be performed    the ASME Code Section III Table 2.2.2-2 as ASME Code          in accordance with the ASME        requirements are met for non-Section III meet ASME Code          Code Section III.                  destructive examination of Section III requirements.                                                pressure boundary welds.
124  2.2.02.04a 4.a) The components identified      A hydrostatic test will be          A report exists and concludes that in Table 2.2.2-1 as ASME Code        performed on the components        the results of the hydrostatic test Section III retain their pressure    required by the ASME Code          of the components identified in boundary integrity at their          Section III to be hydrostatically  Table 2.2.2-1 as ASME Code design pressure.                    tested.                            Section III conform with the requirements of the ASME Code Section III.
125  2.2.02.04b 4.b) The pipelines identified in    A hydrostatic test will be          A report exists and concludes that Table 2.2.2-2 as ASME Code          performed on the piping required    the results of the hydrostatic test Section III retain their pressure    by the ASME Code Section III to    of the piping identified in boundary integrity at their          be hydrostatically tested.          Table 2.2.2-2 as ASME Code design pressure.                                                        Section III conform with the requirements of the ASME Code Section III.
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Table 2.2.2-3 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No.          Design Commitment                  Inspections, Tests, Analyses            Acceptance Criteria 126  2.2.02.05a.i  5.a) The seismic Category I          i) Inspection will be performed to  i) The seismic Category I components identified in            verify that the seismic Category I  components identified in Table 2.2.2-1 can withstand          components and valves identified    Table 2.2.2-1 are located on the seismic design basis loads          in Table 2.2.2-1 are located on the Nuclear Island.
without loss of safety function. Nuclear Island.
127 2.2.02.05a.ii  5.a) The seismic Category I          ii) Type tests, analyses, or a      ii) A report exists and concludes components identified in            combination of type tests and      that the seismic Category I Table 2.2.2-1 can withstand          analyses of seismic Category I      components can withstand seismic design basis loads          components will be performed.      seismic design basis loads without without loss of safety function.                                        loss of safety function.
128 2.2.02.05a.iii 5.a) The seismic Category I          iii) Inspection will be performed  iii) The report exists and components identified in            for the existence of a report      concludes that the as-built Table 2.2.2-1 can withstand          verifying that the as-built        components including anchorage seismic design basis loads          components including anchorage      are seismically bounded by the without loss of safety function. are seismically bounded by the      tested or analyzed conditions.
tested or analyzed conditions.
129  2.2.02.05b    5.b) Each of the pipelines          Inspection will be performed for    A report exists and concludes that identified in Table 2.2.2-2 for      the existence of a report          each of the as-built pipelines which functional capability is      concluding that the as-built        identified in Table 2.2.2-2 for required is designed to              pipelines meet the requirements    which functional capability is withstand combined normal and        for functional capability.          required meets the requirements seismic design basis loads                                              for functional capability.
without a loss of its functional capability.
130  2.2.02.05c  5.c) The PCCAWST can                Inspection will be performed for    A report exists and concludes that withstand a seismic event.          the existence of a report verifying the as-built PCCAWST and its that the as-built PCCAWST and      anchorage are designed using its anchorage are designed using    seismic Category II methods and seismic Category II methods and    criteria.
criteria.
131  2.2.02.06a.i  6.a) The Class 1E components        i) Type tests or a combination of  i) A report exists and concludes identified in Table 2.2.2-1 as      type tests and analyses will be    that the Class 1E components being qualified for a harsh          performed on Class 1E              identified in Table 2.2.2-1 as environment can withstand the        components located in a harsh      being qualified for a harsh environmental conditions that        environment.                        environment can withstand the would exist before, during, and                                          environmental conditions that following a design basis                                                would exist before, during, and accident without loss of safety                                          following a design basis accident function for the time required to                                        without loss of safety function for perform the safety function.                                            the time required to perform the safety function.
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Table 2.2.2-3 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No.          Design Commitment                  Inspections, Tests, Analyses              Acceptance Criteria 132 2.2.02.06a.ii 6.a) The Class 1E components        ii) Inspection will be performed    ii) A report exists and concludes identified in Table 2.2.2-1 as      of the as-built Class 1E            that the as-built Class 1E being qualified for a harsh          components and the associated      components and the associated environment can withstand the        wiring, cables, and terminations    wiring, cables, and terminations environmental conditions that        located in a harsh environment. identified in Table 2.2.2-1 as would exist before, during, and                                          being qualified for a harsh following a design basis                                                environment are bounded by type accident without loss of safety                                          tests, analyses, or a combination function for the time required to                                        of type tests and analyses.
perform the safety function.
133  2.2.02.06b  6.b) The Class 1E components        Testing will be performed by        A simulated test signal exists at identified in Table 2.2.2-1 are      providing a simulated test signal  the Class 1E components powered from their respective        in each Class 1E division.          identified in Table 2.2.2-1 when Class 1E division.                                                      the assigned Class 1E division is provided the test signal.
134  2.2.02.06c  6.c) Separation is provided          See ITAAC Table 3.3-6, item 7.d. See ITAAC Table 3.3-6, item 7.d.
between PCS Class 1E divisions, and between Class 1E divisions and non-Class 1E cable.
135 2.2.02.07a.i  7.a) The PCS delivers water          i) Testing will be performed to    i) When tested, each one of the from the PCCWST to the              measure the PCCWST delivery        three flow paths delivers water at outside, top of the containment      rate from each one of the three    greater than or equal to:
vessel.                              parallel flow paths.                - 469.1 gpm at a PCCWST water level of 27.4 ft + 0.2, - 0.0 ft above the tank floor
                                                                                          - 226.6 gpm when the PCCWST water level uncovers the first (i.e. tallest) standpipe
                                                                                          - 176.3 gpm when the PCCWST water level uncovers the second tallest standpipe
                                                                                          - 144.2 gpm when the PCCWST water level uncovers the third tallest standpipe 136 2.2.02.07a.ii 7.a) The PCS delivers water          ii) Testing and or analysis will be ii) When tested and/or analyzed from the PCCWST to the              performed to demonstrate the        with all flow paths delivering and outside, top of the containment      PCCWST inventory provides          an initial water level at 27.4 +
vessel.                              72 hours of adequate water flow. 0.2, - 0.00 ft, the PCCWST water inventory provides greater than or equal to 72 hours of flow, and the flow rate at 72 hours is greater than or equal to 100.7 gpm.
C-115
 
Table 2.2.2-3 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No.          Design Commitment                  Inspections, Tests, Analyses            Acceptance Criteria 137 2.2.02.07a.iii 7.a) The PCS delivers water          iii) Inspection will be performed  iii) The elevations of the from the PCCWST to the              to determine the PCCWST            standpipes above the tank floor outside, top of the containment      standpipes elevations.              are:
vessel.                                                                  - 16.8 ft +/- 0.2 ft
                                                                                            - 20.3 ft +/- 0.2 ft
                                                                                            - 24.1 ft +/- 0.2 ft 138  2.2.02.07b.i  7.b) The PCS wets the outside        i) Testing will be performed to    i) A report exists and concludes surface of the containment          measure the outside wetted          that when the water in the vessel. The inside and the          surface of the containment vessel  PCCWST uncovers the standpipes outside of the containment          with one of the three parallel flow at the following levels, the water vessel above the operating deck      paths delivering water to the top  delivered by one of the three are coated with an inorganic        of the containment vessel.          parallel flow paths to the zinc material.                                                          containment shell provides coverage measured at the spring line that is equal to or greater than the stated coverages.
                                                                                            - 24.1 +/- 0.2 ft above the tank floor; at least 90% of the perimeter is wetted.
                                                                                            - 20.3 +/- 0.2 ft above the tank floor; at least 72.9% of the perimeter is wetted.
                                                                                            - 16.8 +/- 0.2 ft above the tank floor; at least 59.6% of the perimeter is wetted.
139 2.2.02.07b.ii  7.b) The PCS wets the outside        ii) Inspection of the containment  ii) A report exists and concludes surface of the containment          vessel exterior coating will be    that the containment vessel vessel. The inside and the          conducted.                          exterior surface is coated with an outside of the containment                                              inorganic zinc coating above vessel above the operating deck                                          elevation 135'-3".
are coated with an inorganic zinc material.
140 2.2.02.07b.iii 7.b) The PCS wets the outside        iii) Inspection of the containment  iii) A report exists and concludes surface of the containment          vessel interior coating will be    that the containment vessel vessel. The inside and the          conducted.                          interior surface is coated with an outside of the containment                                              inorganic zinc coating above 7' vessel above the operating deck                                          above the operating deck.
are coated with an inorganic zinc material.
C-116
 
Table 2.2.2-3 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No.          Design Commitment                  Inspections, Tests, Analyses          Acceptance Criteria 141  2.2.02.07c  7.c) The PCS provides air flow        Inspections of the air flow path  Flow paths exist at each of the over the outside of the              segments will be performed.        following locations:
containment vessel by a natural                                          -  Air inlets circulation air flow path from                                          -  Base of the outer annulus the air inlets to the air discharge                                      -  Base of the inner annulus structure.                                                              -  Discharge structure 142  2.2.02.07d  7.d) The PCS drains the excess        Testing will be performed to      With a water level within the water from the outside of the        verify the upper annulus drain    upper annulus 10" + 1" above the containment vessel through the        flow performance.                  annulus drain inlet, the flow rate two upper annulus drains.                                                through each drain is greater than or equal to 525 gpm.
143 2.2.02.07e.i  7.e) The PCS provides a flow          i) See item 1 in this table.      i) See item 1 in this table.
path for long-term water makeup to the PCCWST.
144 2.2.02.07e.ii 7.e) The PCS provides a flow          ii) Testing will be performed to  ii) With a water supply connected path for long-term water              measure the delivery rate from the to the PCS long-term makeup makeup to the PCCWST.                long-term makeup connection to    connection, each PCS the PCCWST.                        recirculation pump delivers greater than or equal to 100 gpm when tested separately.
145 2.2.02.07f.i  7.f) The PCS provides a flow          i) Testing will be performed to    i) With the PCCWST water level path for long-term water              measure the delivery rate from the at 27.4 ft + 0.2, - 0.0 ft above the makeup from the PCCWST to            PCCWST to the spent fuel pool. bottom of the tank, the flow path the spent fuel pool.                                                    from the PCCWST to the spent fuel pool delivers greater than or equal to 118 gpm.
146 2.2.02.07f.ii 7.f) The PCS provides a flow          ii) Inspection of the PCCWST      ii) The volume of the PCCWST path for long-term water              will be performed.                is greater than 756,700 gallons.
makeup from the PCCWST to the spent fuel pool.
147  2.2.02.08a  8.a) The PCCAWST contains            Inspection of the PCCAWST will    The volume of the PCCAWST is an inventory of cooling water        be performed.                      greater than 780,000 gallons.
sufficient for PCS containment cooling from hour 72 through day 7.
148  2.2.02.08b  8.b) The PCS delivers water          Testing will be performed to      With PCCASWST aligned to the from the PCCAWST to the              measure the delivery rate from the suction of the recirculation PCCWST and spent fuel pool            PCCAWST to the PCCWST and          pumps, each pump delivers simultaneously.                      spent fuel pool simultaneously. greater than or equal to 100 gpm to the PCCWST and 35 gpm to the spent fuel pool simultaneously when each pump is tested separately.
C-117
 
Table 2.2.2-3 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No.            Design Commitment                Inspections, Tests, Analyses            Acceptance Criteria 149  2.2.02.08c  8.c) The PCCWST includes a          See ITAAC Table 2.3.4-2, items 1    See ITAAC Table 2.3.4-2, items 1 water inventory for the fire        and 2.                              and 2.
protection system.
150  2.2.02.09    9. Safety-related displays          Inspection will be performed for    Safety-related displays identified identified in Table 2.2.2-1 can      retrievability of the safety-related in Table 2.2.2-1 can be retrieved be retrieved in the MCR.            displays in the MCR.                in the MCR.
151  2.2.02.10a  10.a) Controls exist in the          Stroke testing will be performed    Controls in the MCR operate to MCR to cause the remotely            on the remotely operated valves      cause remotely operated valves operated valves identified in        identified in Table 2.2.2-1 using    identified in Table 2.2.2-1 to Table 2.2.2-1 to perform active      the controls in the MCR.            perform active functions.
functions.
152  2.2.02.10b    10.b) The valves identified in      Testing will be performed on the    The remotely operated valves Table 2.2.2-1 as having PMS          remotely operated valves in          identified in Table 2.2.2-1 as control perform an active safety    Table 2.2.2-1 using real or          having PMS control perform the function after receiving a signal    simulated signals into the PMS.      active function identified in the from the PMS.                                                            table after receiving a signal from the PMS.
153  2.2.02.10c  10.c) The valves identified in      Testing will be performed on the    The remotely operated valves Table 2.2.2-1 as having DAS          remotely operated valves listed in  identified in Table 2.2.2-1 as control perform an active safety    Table 2.2.2-1 using real or          having DAS control perform the function after receiving a signal    simulated signals into the DAS.      active function identified in the from the DAS.                                                            table after receiving a signal from the DAS.
154  2.2.02.11a.i  11.a) The motor-operated            i) Tests or type tests of motor-    i) A test report exists and valves identified in Table 2.2.2-    operated valves will be performed    concludes that each motor-1 perform an active safety-          to demonstrate the capability of    operated valve changes position related function to change          the valve to operate under its      as indicated in Table 2.2.2-1 position as indicated in the        design conditions.                  under design conditions.
table.
155 2.2.02.11a.ii  11.a) The motor-operated            ii) Inspection will be performed    ii) A report exists and concludes valves identified in Table 2.2.2-    for the existence of a report        that the capability of the as-built 1 perform an active safety-          verifying that the capability of the motor-operated valves bound the related function to change          as-built motor-operated valves      tested conditions.
position as indicated in the        bound the tested conditions.
table.
156 2.2.02.11a.iii 11.a) The motor-operated            iii) Tests of the motor-operated    iii) Each motor-operated valve valves identified in Table 2.2.2-    valves will be performed under      changes position as indicated in 1 perform an active safety-          preoperational flow, differential    Table 2.2.2-1 under related function to change          pressure, and temperature            preoperational test conditions.
position as indicated in the        conditions.
table.
C-118
 
Table 2.2.2-3 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No.            Design Commitment                Inspections, Tests, Analyses          Acceptance Criteria 157  2.2.02.11b    11.b) After loss of motive          Testing of the remotely operated  After loss of motive power, each power, the remotely operated        valves will be performed under    remotely operated valve identified valves identified in Table 2.2.2-  the conditions of loss of motive  in Table 2.2.2-1 assumes the 1 assume the indicated loss of      power.                            indicated loss of motive power motive power position.                                                position.
Table 2.2.2-4 Component Name                                Tag No.                      Component Location PCCWST                                PCS-MT-01                        Shield Building PCCAWST                                PCS-MT-05                              Yard Recirculation Pump A                        PCS-MP-01A                      Auxiliary Building Recirculation Pump B                        PCS-MP-01B                      Auxiliary Building C-119
 
Figure 2.2.2-1 Passive Containment Cooling System C-120
 
2.2.3          Passive Core Cooling System Design Description The passive core cooling system (PXS) provides emergency core cooling during design basis events.
The PXS is as shown in Figure 2.2.3-1 and the component locations of the PXS are as shown in Table 2.2.3-5.
: 1. The functional arrangement of the PXS is as described in the Design Description of this Section 2.2.3.
: 2. a) The components identified in Table 2.2.3-1 as ASME Code Section III are designed and constructed in accordance with ASME Code Section III requirements.
b) The piping identified in Table 2.2.3-2 as ASME Code Section III is designed and constructed in accordance with ASME Code Section III requirements.
: 3. a) Pressure boundary welds in components identified in Table 2.2.3-1 as ASME Code Section III meet ASME Code Section III requirements.
b) Pressure boundary welds in piping identified in Table 2.2.3-2 as ASME Code Section III meet ASME Code Section III requirements.
: 4. a) The components identified in Table 2.2.3-1 as ASME Code Section III retain their pressure boundary integrity at their design pressure.
b) The piping identified in Table 2.2.3-2 as ASME Code Section III retains its pressure boundary integrity at its design pressure.
: 5. a) The seismic Category I equipment identified in Table 2.2.3-1 can withstand seismic design basis loads without loss of safety function.
b) Each of the lines identified in Table 2.2.3-2 for which functional capability is required is designed to withstand combined normal and seismic design basis loads without a loss of its functional capability.
: 6. Each of the as-built lines identified in Table 2.2.3-2 as designed for leak before break (LBB) meets the LBB criteria, or an evaluation is performed of the protection from the dynamic effects of a rupture of the line.
: 7. a) The Class 1E equipment identified in Table 2.2.3-1 as being qualified for a harsh environment can withstand the environmental conditions that would exist before, during, and following a design basis accident without loss of safety function for the time required to perform the safety function.
b) The Class 1E components identified in Table 2.2.3-1 are powered from their respective Class 1E division.
c) Separation is provided between PXS Class 1E divisions, and between Class 1E divisions and non-Class 1E cable.
: 8. The PXS provides the following safety-related functions:
C-121
 
a) The PXS provides containment isolation of the PXS lines penetrating the containment.
b) The PRHR HX provides core decay heat removal during design basis events.
c) The CMTs, accumulators, in-containment refueling water storage tank (IRWST) and containment recirculation provide reactor coolant system (RCS) makeup, boration, and safety injection during design basis events.
d) The PXS provides pH adjustment of water flooding the containment following design basis accidents.
: 9. The PXS has the following features:
a) The PXS provides a function to cool the outside of the reactor vessel during a severe accident.
b) The accumulator discharge check valves (PXS-PL-V028A/B and V029A/B) are of a different check valve type than the CMT discharge check valves (PXS-PL-V016A/B and V017A/B).
c) The equipment listed in Table 2.2.3-6 has sufficient thermal lag to withstand the effects of identified hydrogen burns associated with severe accidents.
: 10. Safety-related displays of the parameters identified in Table 2.2.3-1 can be retrieved in the main control room (MCR).
: 11. a) Controls exist in the MCR to cause the remotely operated valves identified in Table 2.2.3-1 to perform their active function(s).
b) The valves identified in Table 2.2.3-1 as having protection and safety monitoring system (PMS) control perform their active function after receiving a signal from the PMS.
c) The valves identified in Table 2.2.3-1 as having diverse actuation system (DAS) control perform their active function after receiving a signal from the DAS.
: 12. a) The squib valves and check valves identified in Table 2.2.3-1 perform an active safety-related function to change position as indicated in the table.
b) After loss of motive power, the remotely operated valves identified in Table 2.2.3-1 assume the indicated loss of motive power position.
: 13. Displays of the parameters identified in Table 2.2.3-3 can be retrieved in the MCR C-122
 
Table 2.2.3-1 ASME                        Class 1E/                          Loss of Code              Remotely  Qual. Safety- Control          Motive Section Seismic    Operated  Harsh    Related  PMS/    Active  Power Equipment Name          Tag No. III    Cat. I      Valve  Envir. Display  DAS    Function Position Passive Residual Heat      PXS-ME-01  Yes    Yes          -      -/-      -      -/-      -        -
Removal Heat Exchanger (PRHR HX)
Accumulator Tank A        PXS-MT-01A  Yes    Yes          -      -/-      -      -/-      -        -
Accumulator Tank B        PXS-MT-01B  Yes    Yes          -      -/-      -      -/-      -        -
Core Makeup Tank (CMT) A  PXS-MT-02A  Yes    Yes          -      -/-      -      -/-      -        -
CMT B                      PXS-MT-02B  Yes    Yes          -      -/-      -      -/-      -        -
IRWST                      PXS-MT-03  No      Yes          -      -/-      -      -/-      -        -
IRWST Screen A            PXS-MY-Y01A  No      Yes          -      -/-      -      -/-      -        -
IRWST Screen B            PXS-MY-Y01B  No      Yes          -      -/-      -      -/-      -        -
IRWST Screen C            PXS-MY-Y01C  No      Yes          -      -/-      -      -/-      -        -
Containment Recirculation PXS-MY-Y02A  No      Yes          -      -/-      -      -/-      -        -
Screen A Containment Recirculation PXS-MY-Y02B  No      Yes          -      -/-      -      -/-      -        -
Screen B pH Adjustment Basket 3A  PXS-MY-Y03A  No      Yes          -      -/-      -      -/-      -        -
pH Adjustment Basket 3B  PXS-MY-Y03B  No      Yes          -      -/-      -      -/-      -        -
pH Adjustment Basket 4A  PXS-MY-Y04A  No      Yes                  -/-              -/-
pH Adjustment Basket 4B  PXS-MY-Y04B  No      Yes                  -/-              -/-
Downspout Screen 1A        PXS-MY-Y81  No      Yes          -      -/-      -      -/-      -        -
Downspout Screen 1B        PXS-MY-Y82  No      Yes          -      -/-      -      -/-      -        -
Downspout Screen 1C        PXS-MY-Y83  No      Yes          -      -/-      -      -/-      -        -
Downspout Screen 1D        PXS-MY-Y84  No      Yes          -      -/-      -      -/-      -        -
Downspout Screen 2A        PXS-MY-Y85  No      Yes          -      -/-      -      -/-      -        -
Downspout Screen 2B        PXS-MY-Y86  No      Yes          -      -/-      -      -/-      -        -
C-123
 
Table 2.2.3-1 ASME                        Class 1E/                              Loss of Code              Remotely  Qual. Safety-  Control          Motive Section Seismic    Operated  Harsh    Related    PMS/    Active    Power Equipment Name              Tag No. III    Cat. I      Valve  Envir. Display    DAS    Function  Position Downspout Screen 2C          PXS-MY-Y87    No      Yes          -      -/-        -        -/-        -      -
Downspout Screen 2D          PXS-MY-Y88    No      Yes          -      -/-        -        -/-        -      -
CMT A Inlet Isolation        PXS-PL-V002A  Yes    Yes        Yes    Yes/Yes    Yes    Yes/No    None      As Is Motor-operated Valve                                                            (Position)
CMT B Inlet Isolation Motor- PXS-PL-V002B  Yes    Yes        Yes    Yes/Yes    Yes    Yes/No    None      As Is operated Valve                                                                  (Position)
CMT A Discharge Isolation    PXS-PL-V014A  Yes    Yes        Yes    Yes/Yes    Yes    Yes/Yes  Transfer  Open Valve                                                                          (Position)          Open CMT B Discharge Isolation    PXS-PL-V014B  Yes    Yes        Yes    Yes/Yes    Yes    Yes/Yes  Transfer  Open Valve                                                                          (Position)          Open CMT A Discharge Isolation    PXS-PL-V015A  Yes    Yes        Yes    Yes/Yes    Yes    Yes/Yes  Transfer  Open Valve                                                                          (Position)          Open CMT B Discharge Isolation    PXS-PL-V015B  Yes    Yes        Yes    Yes/Yes    Yes    Yes/Yes  Transfer  Open Valve                                                                          (Position)          Open CMT A Discharge Check        PXS-PL-V016A  Yes    Yes          No      -/-      No        -/-    Transfer    -
Valve                                                                                                Open/
Transfer Closed CMT B Discharge Check        PXS-PL-V016B  Yes    Yes          No      -/-      No        -/-    Transfer    -
Valve                                                                                                Open/
Transfer Closed CMT A Discharge Check        PXS-PL-V017A  Yes    Yes          No      -/-      No        -/-    Transfer    -
Valve                                                                                                Open/
Transfer Closed C-124
 
Table 2.2.3-1 ASME                        Class 1E/                          Loss of Code              Remotely  Qual. Safety- Control          Motive Section Seismic    Operated  Harsh    Related  PMS/    Active    Power Equipment Name      Tag No.      III    Cat. I      Valve  Envir. Display  DAS    Function  Position CMT B Discharge Check  PXS-PL-V017B  Yes    Yes          No      -/-      No      -/-    Transfer    -
Valve                                                                                        Open/
Transfer Closed Accumulator A Pressure  PXS-PL-V022A  Yes    Yes          No      -/-      No      -/-    Transfer    -
Relief Valve                                                                                Open/
Transfer Closed Accumulator B Pressure  PXS-PL-V022B  Yes    Yes          No      -/-      No      -/-    Transfer    -
Relief Valve                                                                                Open/
Transfer Closed Accumulator A Discharge PXS-PL-V027A  Yes    Yes        Yes      -/-      Yes    - /No    None      As Is Isolation Valve Accumulator B Discharge PXS-PL-V027B  Yes    Yes        Yes      -/-      Yes    - /No    None      As Is Isolation Valve Accumulator A Discharge PXS-PL-V028A  Yes    Yes          No      -/-      No      -/-    Transfer    -
Check Valve                                                                                  Open/
Close Accumulator B Discharge PXS-PL-V028B  Yes    Yes          No      -/-      No      -/-    Transfer    -
Check Valve                                                                                  Open/
Close Accumulator A Discharge PXS-PL-V029A  Yes    Yes          No      -/-      No      -/-    Transfer    -
Check Valve                                                                                  Open/
Close Accumulator B Discharge PXS-PL-V029B  Yes    Yes          No      -/-      No      -/-    Transfer    -
Check Valve                                                                                  Open/
Close C-125
 
Table 2.2.3-1 ASME                        Class 1E/                                Loss of Code              Remotely  Qual. Safety-  Control            Motive Section Seismic    Operated  Harsh    Related    PMS/    Active      Power Equipment Name            Tag No. III    Cat. I      Valve  Envir. Display    DAS    Function    Position Nitrogen Supply              PXS-PL-V042  Yes    Yes        Yes    Yes/No      Yes    Yes/No  Transfer    Close Containment Isolation Valve                                                    (position)          Closed Nitrogen Supply              PXS-PL-V043  Yes    Yes          No      -/-      No        -/-    Transfer      -
Containment Isolation Check                                                                        Closed Valve PRHR HX Inlet Isolation      PXS-PL-V101  Yes    Yes        Yes    Yes/Yes    Yes    Yes/No    None        As Is Motor-operated Valve                                                          (position)
PRHR HX Control Valve      PXS-PL-V108A  Yes    Yes        Yes    Yes/Yes    Yes    Yes/Yes  Transfer    Open (Position)          Open PRHR HX Control Valve      PXS-PL-V108B  Yes    Yes        Yes    Yes/Yes    Yes    Yes/Yes  Transfer    Open (Position)          Open Containment Recirculation A PXS-PL-V117A  Yes    Yes        Yes    Yes/Yes    Yes    Yes/Yes  None        As Is Isolation Motor-operated                                                      (position)
Valve Containment Recirculation B PXS-PL-V117B  Yes    Yes        Yes    Yes/Yes    Yes    Yes/Yes  None        As Is Isolation Motor-operated                                                      (position)
Valve Containment Recirculation A PXS-PL-V118A  Yes    Yes        Yes    Yes/Yes    Yes    Yes/Yes  Transfer    As Is Squib Valve                                                                    (Position)          Open Containment Recirculation B PXS-PL-V118B  Yes    Yes        Yes    Yes/Yes    Yes    Yes/Yes  Transfer    As Is Squib Valve                                                                    (Position)          Open Containment Recirculation A PXS-PL-V119A  Yes    Yes          No      -/-      No        -/-    Transfer -
Check Valve                                                                                        Open/
Transfer Closed C-126
 
Table 2.2.3-1 ASME                        Class 1E/                                Loss of Code              Remotely  Qual. Safety-    Control            Motive Section Seismic    Operated  Harsh    Related      PMS/    Active      Power Equipment Name            Tag No.      III    Cat. I      Valve  Envir. Display    DAS    Function    Position Containment Recirculation B PXS-PL-V119B  Yes    Yes          No      -/-      No        -/-    Transfer -
Check Valve                                                                                          Open/
Transfer Closed Containment Recirculation A PXS-PL-V120A  Yes    Yes        Yes    Yes/Yes    Yes      Yes/Yes  Transfer    As Is Squib Valve                                                                    (Position)            Open Containment Recirculation B PXS-PL-V120B  Yes    Yes        Yes    Yes/Yes    Yes    Yes/Yes  Transfer    As Is Squib Valve                                                                    (Position)            Open IRWST Injection A          PXS-PL-V122A  Yes    Yes          No      -/-      No        -/-    Transfer      -
Check Valve                                                                                          Open/
Transfer Closed IRWST Injection B          PXS-PL-V122B  Yes    Yes          No      -/-      No        -/-    Transfer      -
Check Valve                                                                                          Open/
Transfer Closed IRWST Injection A Squib    PXS-PL-V123A  Yes    Yes        Yes    Yes/Yes    Yes      Yes/Yes  Transfer    As Is Valve                                                                          (Position)            Open IRWST Injection B Squib    PXS-PL-V123B  Yes    Yes        Yes    Yes/Yes    Yes      Yes/Yes  Transfer    As Is Valve                                                                          (Position)            Open IRWST Injection A          PXS-PL-V124A  Yes    Yes          No      -/-      No        -/-    Transfer      -
Check Valve                                                                                          Open/
Transfer Closed IRWST Injection B          PXS-PL-V124B  Yes    Yes          No      -/-      No        -/-    Transfer      -
Check Valve                                                                                          Open/
Transfer Closed C-127
 
Table 2.2.3-1 ASME                        Class 1E/                              Loss of Code              Remotely  Qual. Safety-  Control          Motive Section Seismic    Operated  Harsh    Related    PMS/    Active    Power Equipment Name        Tag No. III    Cat. I      Valve  Envir. Display    DAS    Function  Position IRWST Injection A Squib PXS-PL-V125A  Yes    Yes        Yes    Yes/Yes    Yes    Yes/Yes  Transfer  As Is Valve                                                                      (Position)          Open IRWST Injection B Squib PXS-PL-V125B  Yes    Yes        Yes    Yes/Yes    Yes    Yes/Yes  Transfer  As Is Valve                                                                      (Position)          Open IRWST Gutter Isolation  PXS-PL-V130A  Yes    Yes        Yes    Yes/Yes    Yes    Yes/Yes  Transfer  Closed Valve                                                                      (Position)          Closed IRWST Gutter Isolation  PXS-PL-V130B  Yes    Yes        Yes    Yes/Yes    Yes    Yes/Yes  Transfer  Closed Valve                                                                      (Position)          Closed CMT A Level Sensor        PXS-011A      -      Yes          -    Yes/Yes    Yes      -/-        -        -
CMT A Level Sensor        PXS-011B      -      Yes          -    Yes/Yes    Yes      -/-        -        -
CMT A Level Sensor        PXS-011C      -      Yes          -    Yes/Yes    Yes      -/-        -        -
CMT A Level Sensor        PXS-011D      -      Yes          -    Yes/Yes    Yes      -/-        -        -
CMT B Level Sensor        PXS-012A      -      Yes          -    Yes/Yes    Yes      -/-        -        -
CMT B Level Sensor        PXS-012B      -      Yes          -    Yes/Yes    Yes      -/-        -        -
CMT B Level Sensor        PXS-012C      -      Yes          -    Yes/Yes    Yes      -/-        -        -
CMT B Level Sensor        PXS-012D      -      Yes          -    Yes/Yes    Yes      -/-        -        -
CMT A Level Sensor        PXS-013A      -      Yes          -    Yes/Yes    Yes      -/-        -        -
CMT A Level Sensor        PXS-013B      -      Yes          -    Yes/Yes    Yes      -/-        -        -
CMT A Level Sensor        PXS-013C      -      Yes          -    Yes/Yes    Yes      -/-        -        -
CMT A Level Sensor        PXS-013D      -      Yes          -    Yes/Yes    Yes      -/-        -        -
CMT B Level Sensor        PXS-014A      -      Yes          -    Yes/Yes    Yes      -/-        -        -
CMT B Level Sensor        PXS-014B      -      Yes          -    Yes/Yes    Yes      -/-        -        -
CMT B Level Sensor        PXS-014C      -      Yes          -    Yes/Yes    Yes      -/-        -        -
C-128
 
Table 2.2.3-1 ASME                        Class 1E/                          Loss of Code              Remotely  Qual. Safety- Control          Motive Section Seismic    Operated  Harsh    Related  PMS/    Active  Power Equipment Name                Tag No. III    Cat. I      Valve  Envir. Display  DAS    Function Position CMT B Level Sensor                PXS-014D    -      Yes          -    Yes/Yes    Yes    -/-      -        -
IRWST Level Sensor                PXS-045    -      Yes          -    Yes/Yes    Yes    -/-      -        -
IRWST Level Sensor                PXS-046    -      Yes          -    Yes/Yes    Yes    -/-      -        -
IRWST Level Sensor                PXS-047    -      Yes          -    Yes/Yes    Yes    -/-      -        -
IRWST Level Sensor                PXS-048    -      Yes          -    Yes/Yes    Yes    -/-      -        -
PRHR HX Flow Sensor              PXS-049A    -      Yes          -    Yes/Yes    Yes    -/-      -        -
PRHR HX Flow Sensor              PXS-049B    -      Yes          -    Yes/Yes    Yes    -/-      -        -
Containment Flood-up Level        PXS-050    -      Yes          -    Yes/Yes    Yes    -/-      -        -
Sensor Containment Flood-up Level        PXS-051    -      Yes          -    Yes/Yes    Yes    -/-      -        -
Sensor Containment Flood-up Level        PXS-052    -      Yes          -    Yes/Yes    Yes    -/-      -        -
Sensor RNS Suction Leak Test          PXS-PL-V208A  Yes    Yes          No      -/-      No      -/-      -        -
Valve Note: Dash (-) indicates not applicable.
C-129
 
Table 2.2.3-2 ASME      Leak  Functional Code      Before Capability Line Name                          Line Number          Section III Break  Required PRHR HX inlet line from hot leg and    RCS-L134, PXS-L102, PXS-L103,      Yes      Yes      Yes outlet line to steam generator channel PXS-L104A, PXS-L104B, PXS-L105, head                                  RCS-L113 PXS-L107                            Yes      Yes      No CMT A inlet line from cold leg C and  RCS-L118A, PXS-L007A, PXS-L015A,    Yes      Yes      Yes outlet line to reactor vessel direct  PXS-L016A, PXS-L017A, PXS-L018A, vessel injection (DVI) nozzle A        PXS-L020A, PXS-L021A PXS-L019A, PXS-L070A                Yes      Yes      No CMT B inlet line from cold leg D and  RCS-L118B, PXS-L007B, PXS-L015B,    Yes      Yes      Yes outlet line to reactor vessel DVI      PXS-L016B, PXS-L017B, PXS-L018B, nozzle B                              PXS-L020B, PXS-L021B PXS-L019B, PXS-L070B                Yes      Yes      No Accumulator A discharge line to DVI    PXS-L025A, PXS-L027A, PXS-L029A    Yes      Yes      Yes line A Accumulator B discharge line to DVI    PXS-L025B, PXS-L027B, PXS-L029B    Yes      Yes      Yes line B IRWST injection line A to DVI line A  PXS-L125A, PXS-L127A                Yes      Yes      Yes PXS-L123A, PXS-L124A, PXS-L118A,    Yes      No      Yes PXS-L117A, PXS-L116A, PXS-L112A IRWST injection line B to DVI line B  PXS-L125B, PXS-L127B                Yes      Yes      Yes PXS-L123B, PXS-L124B, PXS-L118B,    Yes      No      Yes PXS-L117B, PXS-L116B, PXS-L114B, PXS-L112B, PXS-L120 IRWST screen cross-connect line        PXS-L180A, PXS-L180B                Yes      No      Yes Containment recirculation line A      PXS-L113A, PXS-L131A, PXS-L132A    Yes      No      Yes C-130
 
Table 2.2.3-2 ASME      Leak  Functional Code      Before Capability Line Name                            Line Number          Section III Break  Required Containment recirculation line B      PXS-L113B, PXS-L131B, PXS-L132B    Yes      No      Yes IRWST gutter drain line                PXS-L142A, PXS-L142B                Yes      No      Yes PXS-L141A, PXS-L141B                Yes      No      No Downspout drain lines from polar      PXS-L301A, PXS-L302A, PXS-L303A,    Yes      No      Yes crane girder and internal stiffener to PXS-L304A, PXS-L305A, PXS-L306A, collection box A                      PXS-L307A, PXS-L308A, PXS-L309A, PXS-L310A Downspout drain lines from polar      PXS-L301B, PXS-L302B, PXS-L303B,    Yes      No      Yes crane girder and internal stiffener to PXS-L304B, PXS-L305B, PXS-L306B, collection box B                      PXS-L307B, PXS-L308B, PXS-L309B, PXS-L310B C-131
 
Table 2.2.3-3 Equipment                    Tag No.      Display      Control Function CMT A Discharge Isolation Valve (Position) PXS-PL-V014A  Yes (Position)        -
CMT B Discharge Isolation Valve (Position) PXS-PL-V014B  Yes (Position)        -
CMT A Discharge Isolation Valve (Position) PXS-PL-V015A  Yes (Position)        -
CMT B Discharge Isolation Valve (Position) PXS-PL-V015B  Yes (Position)        -
Accumulator A Nitrogen Vent Valve          PXS-PL-V021A  Yes (Position)        -
(Position)
Accumulator B Nitrogen Vent Valve          PXS-PL-V021B  Yes (Position)        -
(Position)
Accumulator A Discharge Isolation Valve    PXS-PL-V027A  Yes (Position)        -
(Position)
Accumulator B Discharge Isolation Valve    PXS-PL-V027B  Yes (Position)        -
(Position)
PRHR HX Control Valve (Position)          PXS-PL-V108A  Yes (Position)        -
PRHR HX Control Valve (Position)          PXS-PL-V108B  Yes (Position)        -
Containment Recirculation A Isolation      PXS-PL-V017A  Yes (Position)        -
Valve Containment Recirculation B Isolation      PXS-PL-V017B  Yes (Position)        -
Valve Containment Recirculation A Isolation      PXS-PL-V118A  Yes (Position)        -
Valve (Position)
Containment Recirculation B Isolation      PXS-PL-V118B  Yes (Position)        -
Valve (Position)
Containment Recirculation A Isolation      PXS-PL-V120A  Yes (Position)        -
Valve (Position)
Containment Recirculation B Isolation      PXS-PL-V120B  Yes (Position)        -
Valve (Position)
IRWST Line A Isolation Valve (Position)    PXS-PL-V121A  Yes (Position)        -
IRWST Line B Isolation Valve (Position)    PXS-PL-V121B  Yes (Position)        -
IRWST Injection A Isolation Squib          PXS-PL-V123A  Yes (Position)        -
(Position)
IRWST Injection B Isolation Squib          PXS-PL-V123B  Yes (Position)        -
(Position)
IRWST Injection A Isolation Squib          PXS-PL-V125A  Yes (Position)        -
(Position)
IRWST Injection B Isolation Squib          PXS-PL-V125B  Yes (Position)        -
(Position)
C-132
 
Table 2.2.3-3 Equipment                  Tag No.      Display      Control Function IRWST Gutter Bypass Isolation Valve    PXS-PL-V130A  Yes (Position)        -
(Position)
IRWST Gutter Bypass Isolation Valve    PXS-PL-V130B  Yes (Position)        -
(Position)
Accumulator A Level Sensor              PXS-JE-L021        Yes              -
Accumulator B Level Sensor              PXS-JE-L022        Yes              -
Accumulator A Level Sensor              PXS-JE-L023        Yes              -
Accumulator B Level Sensor              PXS-JE-L024        Yes              -
PRHR HX Inlet Temperature Sensor        PXS-JE-T064        Yes              -
IRWST Surface Temperature Sensor        PXS-JE-T041        Yes              -
IRWST Surface Temperature Sensor        PXS-JE-T042        Yes              -
IRWST Bottom Temperature Sensor          PXS-JE-T043        Yes              -
IRWST Bottom Temperature Sensor          PXS-JE-T044        Yes              -
Note: Dash (-) indicates not applicable.
C-133
 
Table 2.2.3-4 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No.            Design Commitment                  Inspections, Tests, Analyses          Acceptance Criteria 158  2.2.03.01 1. The functional arrangement of the      Inspection of the as-built system The as-built PXS conforms PXS is as described in the Design          will be performed.                with the functional Description of this Section 2.2.3.                                          arrangement as described in the Design Description of this Section 2.2.3.
159  2.2.03.02a 2.a) The components identified in          Inspection will be conducted of  The ASME Code Section III Table 2.2.3-1 as ASME Code Section        the as-built components as        design reports exist for the III are designed and constructed in        documented in the ASME design    as-built components identified accordance with ASME Code                  reports.                          in Table 2.2.3-1 as ASME Section III requirements.                                                    Code Section III.
160  2.2.03.02b 2.b) The piping identified in              Inspection will be conducted of  The ASME Code Section III Table 2.2.3-2 as ASME Code Section        the as-built piping as            design reports exist for the III is designed and constructed in        documented in the ASME design    as-built piping identified in accordance with ASME Code                  reports.                          Table 2.2.3-2 as ASME Code Section III requirements.                                                    Section III.
161  2.2.03.03a 3.a) Pressure boundary welds in            Inspection of the as-built        A report exists and concludes components identified in Table 2.2.3-      pressure boundary welds will be  that the ASME Code Section 1 as ASME Code Section III meet            performed in accordance with      III requirements are met for ASME Code Section III                      the ASME Code Section III.        non-destructive examination requirements.                                                                of pressure boundary welds.
162  2.2.03.03b 3.b) Pressure boundary welds in            Inspection of the as-built        A report exists and concludes piping identified in Table 2.2.3-2 as      pressure boundary welds will be  that the ASME Code Section ASME Code Section III meet ASME            performed in accordance with      III requirements are met for Code Section III requirements.            the ASME Code Section III.        non-destructive examination of pressure boundary welds.
163  2.2.03.04a 4.a) The components identified in          A hydrostatic test will be        A report exists and concludes Table 2.2.3-1 as ASME Code Section        performed on the components      that the results of the III retain their pressure boundary        required by the ASME Code        hydrostatic test of the integrity at their design pressure.        Section III to be hydrostatically components identified in tested.                          Table 2.2.3-1 as ASME Code Section III conform with the requirements of the ASME Code Section III.
164  2.2.03.04b 4.b) The piping identified in              A hydrostatic test will be        A report exists and concludes Table 2.2.3-2 as ASME Code Section        performed on the piping required  that the results of the III retains its pressure boundary          by the ASME Code Section III to  hydrostatic test of the piping integrity at its design pressure.          be hydrostatically tested.        identified in Table 2.2.3-2 as ASME Code Section III conform with the requirements of the ASME Code Section III.
C-134
 
Table 2.2.3-4 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No.              Design Commitment                    Inspections, Tests, Analyses        Acceptance Criteria 165  2.2.03.05a.i  5.a) The seismic Category I                i) Inspection will be performed    i) The seismic Category I equipment identified in Table 2.2.3-1      to verify that the seismic        equipment identified in can withstand seismic design basis        Category I equipment and valves    Table 2.2.3-1 is located on the loads without loss of safety function. identified in Table 2.2.3-1 are    Nuclear Island.
located on the Nuclear Island.
166 2.2.03.05a.ii  5.a) The seismic Category I                ii) Type tests, analyses, or a    ii) A report exists and equipment identified in Table 2.2.3-1      combination of type tests and      concludes that the seismic can withstand seismic design basis        analyses of seismic Category I    Category I equipment can loads without loss of safety function. equipment will be performed.      withstand seismic design basis dynamic loads without loss of safety function. For the PXS containment recirculation and IRWST screens, a report exists and concludes that the screens can withstand seismic dynamic loads and also post-accident operating loads, including head loss and debris weights.
167 2.2.03.05a.iii 5.a) The seismic Category I                iii) Inspection will be performed  iii) A report exists and equipment identified in Table 2.2.3-1      for the existence of a report      concludes that the as-built can withstand seismic design basis        verifying that the as-built        equipment including loads without loss of safety function. equipment including anchorage      anchorage is seismically is seismically bounded by the      bounded by the tested or tested or analyzed conditions. analyzed conditions. For the PXS containment recirculation and IRWST screens, a report exists and concludes that the as-built screens including their anchorage are bounded by the seismic loads and also post-accident operating loads, including head loss and debris weights.
168  2.2.03.05b    5.b) Each of the lines identified in      Inspection will be performed      A report exists and concludes Table 2.2.3-2 for which functional        verifying that the as-built piping that each of the as-built lines capability is required is designed to      meets the requirements for        identified in Table 2.2.3-2 for withstand combined normal and              functional capability.            which functional capability is seismic design basis loads without a                                          required meets the loss of its functional capability.                                            requirements for functional capability.
C-135
 
Table 2.2.3-4 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No.              Design Commitment                    Inspections, Tests, Analyses        Acceptance Criteria 169  2.2.03.06  6. Each of the as-built lines              Inspection will be performed for  An LBB evaluation report identified in Table 2.2.3-2 as            the existence of an LBB          exists and concludes that the designed for LBB meets the LBB            evaluation report or an          LBB acceptance criteria are criteria, or an evaluation is              evaluation report on the          met by the as-built RCS performed of the protection from the      protection from dynamic effects  piping and piping materials, or dynamic effects of a rupture of the        of a pipe break. Section 3.3,    a pipe break evaluation report line.                                      Nuclear Island Buildings,        exists and concludes that contains the design descriptions  protection from the dynamic and inspections, tests, analyses, effects of a line break is and acceptance criteria for      provided.
protection from the dynamic effects of pipe rupture.
170 2.2.03.07a.i  7.a) The Class 1E equipment                i) Type tests, analyses, or a    i) A report exists and identified in Table 2.2.3-1 as being      combination of type tests and    concludes that the Class 1E qualified for a harsh environment can      analyses will be performed on    equipment identified in Table withstand the environmental                Class 1E equipment located in a  2.2.3-1 as being qualified for a conditions that would exist before,        harsh environment.                harsh environment can during, and following a design basis                                        withstand the environmental accident without loss of safety                                              conditions that would exist function for the time required to                                            before, during, and following perform the safety function.                                                a design basis accident without loss of safety function for the time required to perform the safety function.
171 2.2.03.07a.ii 7.a) The Class 1E equipment                ii) Inspection will be performed  ii) A report exists and identified in Table 2.2.3-1 as being      of the as-built Class 1E          concludes that the as-built qualified for a harsh environment can      equipment and the associated      Class 1E equipment and the withstand the environmental                wiring, cables, and terminations  associated wiring, cables, and conditions that would exist before,        located in a harsh environment. terminations identified in during, and following a design basis                                        Table 2.2.3-1 as being accident without loss of safety                                              qualified for a harsh function for the time required to                                            environment are bounded by perform the safety function.                                                type tests, analyses, or a combination of type tests and analyses.
172  2.2.03.07b  7.b) The Class 1E components              Testing will be performed by      A simulated test signal exists identified in Table 2.2.3-1 are            providing a simulated test signal at the Class 1E equipment powered from their respective              in each Class 1E division.        identified in Table 2.2.3-1 Class 1E division.                                                          when the assigned Class 1E division is provided the test signal.
173  2.2.03.07c  7.c) Separation is provided between        See ITAAC Table 3.3-6, item      See ITAAC Table 3.3-6, PXS Class 1E divisions, and between        7.d.                              item 7.d.
Class 1E divisions and non-Class 1E cable.
C-136
 
Table 2.2.3-4 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No.              Design Commitment                  Inspections, Tests, Analyses          Acceptance Criteria 174  2.2.03.08a    8.a) The PXS provides containment        See ITAAC Table 2.2.1-3, items      See ITAAC Table 2.2.1-3, isolation of the PXS lines penetrating    1 and 7.                            items 1 and 7.
the containment.
175 2.2.03.08b.01  8.b) The PXS provides core decay          1. A heat removal performance      1. A report exists and heat removal during design basis          test and analysis of the PRHR      concludes that the PRHR HX events.                                  HX will be performed to            heat transfer rate with the determine the heat transfer from    design basis number of PRHR the HX. For the test, the reactor  HX tubes plugged is:
coolant hot leg temperature will    1.78 x 108 Btu/hr with be initially at  540&deg;F with the    520&deg;F HL Temp and 80&deg;F reactor coolant pumps stopped.      IRWST temperatures.
The IRWST water level for the 1.11 x 108 Btu/hr with test will be above the top of the 420&deg;F HL Temp and 80&deg;F HX. The IRWST water IRWST temperatures.
temperature is not specified for the test. The test will continue until the hot leg temperature decreases below 420&deg;F.
176 2.2.03.08b.02  8.b) The PXS provides core decay          2. Inspection of the elevation of  2. The elevation of the heat removal during design basis          the PRHR HX will be                centerline of the HXs upper events.                                  conducted.                          channel head is greater than the HL centerline by at least 26.3 ft.
177 2.2.03.08c.i.01 8.c) The PXS provides RCS                i) A low-pressure injection test    i) The injection line flow makeup, boration, and safety              and analysis for each CMT, each    resistance from each source is injection during design basis events. accumulator, each IRWST            as follows:
injection line, and each            1. CMTs:
containment recirculation line      The calculated flow resistance will be conducted. Each test is    between each CMT and the initiated by opening isolation      reactor vessel is valve(s) in the line being tested. 1.81 x 10-5 ft/gpm2 and Test fixtures may be used to        2.25 x 10-5 ft/gpm2.
simulate squib valves.
: 1. CMTs:
Each CMT will be initially filled with water. All valves in these lines will be open during the test.
C-137
 
Table 2.2.3-4 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No.              Design Commitment                  Inspections, Tests, Analyses        Acceptance Criteria 178 2.2.03.08c.i.02 8.c) The PXS provides RCS                i) A low-pressure injection test  i) The injection line flow makeup, boration, and safety            and analysis for each CMT, each    resistance from each source is injection during design basis events. accumulator, each IRWST            as follows:
injection line, and each          2. Accumulators:
containment recirculation line    The calculated flow resistance will be conducted. Each test is    between each accumulator and initiated by opening isolation    the reactor vessel is valve(s) in the line being tested. 1.47 x 10-5 ft/gpm2 and Test fixtures may be used to        1.83 x 10-5 ft/gpm2.
simulate squib valves.
: 2. Accumulators:
Each accumulator will be partially filled with water and pressurized with nitrogen. All valves in these lines will be open during the test. Sufficient flow will be provided to fully open the check valves.
179 2.2.03.08c.i.03 8.c) The PXS provides RCS                i) A low-pressure injection test  i) The injection line flow makeup, boration, and safety            and analysis for each CMT, each    resistance from each source is injection during design basis events. accumulator, each IRWST            as follows:
injection line, and each          3. IRWST Injection:
containment recirculation line    The calculated flow resistance will be conducted. Each test is    for each IRWST injection line initiated by opening isolation    between the IRWST and the valve(s) in the line being tested. reactor vessel is:
Test fixtures may be used to simulate squib valves.
Line A:  5.53 x 10-6 ft/gpm2
: 3. IRWST Injection:                and  9.20x10-6 ft/gpm2 The IRWST will be partially filled with water. All valves in these lines will be open during    and the test. Sufficient flow will be provided to fully open the check  Line B:6.21x10-6 ft/gpm2 and valves.                            1.03 x 10-5 ft/gpm2.
C-138
 
Table 2.2.3-4 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No.              Design Commitment                  Inspections, Tests, Analyses          Acceptance Criteria 180 2.2.03.08c.i.04  8.c) The PXS provides RCS                i) A low-pressure injection test  i) The injection line flow makeup, boration, and safety            and analysis for each CMT, each    resistance from each source is injection during design basis events. accumulator, each IRWST            as follows:
injection line, and each          4. Containment Recirculation:
containment recirculation line    The calculated flow resistance will be conducted. Each test is    for each containment initiated by opening isolation    recirculation line between the valve(s) in the line being tested. containment and the reactor Test fixtures may be used to      vessel is:
simulate squib valves.
: 4. Containment Recirculation:      Line A:  1.11 x 10-5 ft/gpm2 A temporary water supply will be connected to the recirculation lines. All valves in these lines  and will be open during the test.
Sufficient flow will be provided  Line B:  1.04 x 10-5 ft/gpm2.
to fully open the check valves.
181  2.2.03.08c.ii  8.c) The PXS provides RCS                ii) A low-pressure test and        ii) The flow resistance from makeup, boration, and safety            analysis will be conducted for    the cold leg to the CMT is injection during design basis events. each CMT to determine piping        7.21 x 10-6 ft/gpm2.
flow resistance from the cold leg to the CMT. The test will be performed by filling the CMT via the cold leg balance line by operating the normal residual heat removal pumps.
182  2.2.03.08c.iii  8.c) The PXS provides RCS                iii) Inspections of the routing of iii) These lines have no makeup, boration, and safety            the following pipe lines will be  downward sloping sections injection during design basis events. conducted:                        between the connection to the
                                                              - CMT inlet line, cold leg to      RCS and the high point of the high point                    line.
                                                              - PRHR HX inlet line, hot leg to high point 183 2.2.03.08c.iv.01 8.c) The PXS provides RCS                iv) Inspections of the elevation  iv) The maximum elevation makeup, boration, and safety            of the following pipe lines will  of the top inside surface of injection during design basis events. be conducted:                      these lines is less than the
: 1. IRWST injection lines;          elevation of:
IRWST connection to DVI      1. IRWST bottom inside nozzles                            surface 184 2.2.03.08c.iv.02 8.c) The PXS provides RCS                iv) Inspections of the elevation  iv) The maximum elevation makeup, boration, and safety            of the following pipe lines will  of the top inside surface of injection during design basis events. be conducted:                      these lines is less than the
: 2. Containment recirculation      elevation of:
lines; containment to IRWST        2. IRWST bottom inside lines                              surface C-139
 
Table 2.2.3-4 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No.              Design Commitment                  Inspections, Tests, Analyses        Acceptance Criteria 185 2.2.03.08c.iv.03 8.c) The PXS provides RCS                iv) Inspections of the elevation iv) The maximum elevation makeup, boration, and safety            of the following pipe lines will of the top inside surface of injection during design basis events. be conducted:                    these lines is less than the
: 3. CMT discharge lines to DVI    elevation of:
connection                      3. CMT bottom inside surface 186 2.2.03.08c.iv.04 8.c) The PXS provides RCS                iv) Inspections of the elevation iv) The maximum elevation makeup, boration, and safety            of the following pipe lines will of the top inside surface of injection during design basis events. be conducted:                    these lines is less than the
: 4. PRHR HX outlet line to SG    elevation of:
connection                      4. PRHR HX lower channel head top inside surface 187 2.2.03.08c.v.01  8.c) The PXS provides RCS                v) Inspections of the elevation  v) The elevation of the makeup, boration, and safety            of the following tanks will be  bottom inside tank surface is injection during design basis events. conducted:                      higher than the direct vessel
: 1. CMTs                          injection nozzle centerline by the following:
: 1. CMTs  7.5 ft 188 2.2.03.08c.v.02  8.c) The PXS provides RCS                v) Inspections of the elevation  v) The elevation of the makeup, boration, and safety            of the following tanks will be  bottom inside tank surface is injection during design basis events. conducted:                      higher than the direct vessel
: 2. IRWST                        injection nozzle centerline by the following:
: 2. IRWST  3.4 ft 189 2.2.03.08c.vi.01 8.c) The PXS provides RCS                vi) Inspections of each of the  vi) The calculated volume of makeup, boration, and safety            following tanks will be          each of the following tanks is injection during design basis events. conducted:                      as follows:
: 1. CMTs                          1. CMTs  2487 ft3 190 2.2.03.08c.vi.02 8.c) The PXS provides RCS                vi) Inspections of each of the  vi) The calculated volume of makeup, boration, and safety            following tanks will be          each of the following tanks is injection during design basis events. conducted:                      as follows:
: 2. Accumulators                  2. Accumulators  2000 ft3 191 2.2.03.08c.vi.03 8.c) The PXS provides RCS                vi) Inspections of each of the  vi) The calculated volume of makeup, boration, and safety            following tanks will be          each of the following tanks is injection during design basis events. conducted:                      as follows:
3.- IRWST                        3. IRWST > 73,900 ft3 between the tank outlet connection and the tank overflow C-140
 
Table 2.2.3-4 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No.              Design Commitment                  Inspections, Tests, Analyses        Acceptance Criteria 192 2.2.03.08c.vii  8.c) The PXS provides RCS                vii) Inspection of the as-built  vii) Plates located above each makeup, boration, and safety            components will be conducted    containment recirculation injection during design basis events. for plates located above the    screen are no more than 1 ft containment recirculation        above the top of the screen screens.                        and extend out at least 10 ft perpendicular to and at least 7 ft to the side of the screen surface.
193 2.2.03.08c.viii 8.c) The PXS provides RCS                viii) Inspections of the IRWST  viii) The screens utilize makeup, boration, and safety            and containment recirculation    pockets with a frontal face injection during design basis events. screens will be conducted. The  area of  6.2 in2 and a screen inspections will include        surface area  140 in2 per measurements of the pockets and  pocket. IRWST Screens A the number of pockets used in    and B each have a sufficient each screen. The pocket frontal  number of pockets to provide face area is based on a width    a frontal face area  20 ft2, a times a height. The width is the screen surface area  500 ft2, distance between pocket          and a screen mesh size of centerlines for pockets located  0.0625 inch. IRWST Screen beside each other. The height is C has a sufficient number of the distance between pocket      pockets to provide a frontal centerlines for pockets located  face area  40 ft2, a screen above each other. The pocket    surface area  1000 ft2, and a screen area is the total area of screen mesh size  0.0625 perforated plate inside each    inch. Each containment pocket; this area will be        recirculation screen has a determined by inspection of the  sufficient number of pockets screen manufacturing drawings. to provide a frontal face area 105 ft2, a screen surface area 2500 ft2, and a screen mesh size  0.0625 inch.
A debris curb exists in front of the containment recirculation screens which is > 2 ft above the loop compartment floor.
The bottoms of the IRWST screens are located  6 in above the bottom of the IRWST.
C-141
 
Table 2.2.3-4 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No.            Design Commitment                  Inspections, Tests, Analyses          Acceptance Criteria 194 2.2.03.08c.ix 8.c) The PXS provides RCS                ix) Inspections will be          ix) The type of insulation makeup, boration, and safety            conducted of the insulation used  used on these lines and injection during design basis events. inside the containment on the    equipment is a metal reflective ASME Class 1 lines, reactor      type or a suitable equivalent.
vessel, reactor coolant pumps,    If an insulation other than pressurizer and steam generators. metal reflective insulation is used, a report must exist and conclude that the insulation is a suitable equivalent.
Inspections will be conducted of  The type of insulation used on other insulation used inside the  these lines and equipment is a containment within the zone of    metal reflective type or a influence (ZOI).                  suitable equivalent. If an insulation other than metal reflective insulation is used, a report must exist and conclude that the insulation is a suitable equivalent.
Inspection will be conducted of  The type of insulation used on other insulation below the        these lines is metal reflective maximum flood level of a design  insulation, jacketed fiberglass, basis loss-of-coolant accident    or a suitable equivalent. If an (LOCA).                          insulation other than metal reflective or jacketed fiberglass insulation is used, a report must exist and conclude that the insulation is a suitable equivalent.
C-142
 
Table 2.2.3-4 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No.            Design Commitment                  Inspections, Tests, Analyses          Acceptance Criteria 195 2.2.03.08c.x 8.c) The PXS provides RCS                x) Inspections will be conducted  x) A report exists and makeup, boration, and safety            of the as-built nonsafety-related concludes that the coatings injection during design basis events. coatings or of plant records of  used on these surfaces have a the nonsafety-related coatings    dry film density of used inside containment on        100 lb/ft3. If a coating is walls, floors, ceilings, and      used that has a lower dry film structural steel except in the    density, a report must exist CVS room. Inspections will be    and conclude that the coating conducted of the as-built non-    will not transport. A report safety-related coatings or of    exists and concludes that plant records of the non-safety-  inorganic zinc coatings used related coatings used on          on these surfaces are Safety -
components below the maximum      Service Level I.
flood level of a design basis LOCA or located above the maximum flood level and not inside cabinets or enclosures.
Inspections will be conducted on caulking, tags, and signs used    A report exists and concludes inside containment below the      that tags and signs used in maximum flood level of a design  these locations are made of basis LOCA or located above the  steel or another metal with a maximum flood level and not      density  100 lb/ft3. In inside cabinets or enclosures. addition, a report exists and concludes that caulking used in these locations or coatings used on these signs or tags have a dry film density of 100 lb/ft3. If a material is used that has a lower density, a report must exist and conclude that there is insufficient water flow to transport lightweight caulking, signs, or tags.
Inspections will be conducted of  A report exists and concludes ventilation filters and fiber-    that the ventilation filters and producing fire barriers used      fire barriers in these locations inside containment within the    have a density of  100 lb/ft3.
ZOI or below the maximum flood level of a design basis LOCA.
C-143
 
Table 2.2.3-4 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No.              Design Commitment                  Inspections, Tests, Analyses            Acceptance Criteria 196  2.2.03.08c.xi  8.c) The PXS provides RCS                xi) Inspection of the as-built      xi) The CMT inlet diffuser makeup, boration, and safety            CMT inlet diffuser will be          has a flow area  165 in2.
injection during design basis events. conducted.
197 2.2.03.08c.xii  8.c) The PXS provides RCS                xii) Inspections will be            xii) Each upper level tap line makeup, boration, and safety            conducted of the CMT level          has a downward slope of  2.4 injection during design basis events. sensors (PSX-11A/B/D/C, -          degrees from the centerline of 12A/B/C/D, - 13A/B/C/D, -          the connection to the CMT to 14A/B/C/D) upper level tap          the centerline of the lines.                              connection to the standpipe.
198 2.2.03.08c.xiii 8.c) The PXS provides RCS                xiii) Inspections will be          xiii) These surfaces are makeup, boration, and safety            conducted of the surfaces in the    stainless steel.
injection during design basis events. vicinity of the containment recirculation screens. The surfaces in the vicinity of the containment recirculation screens are the surfaces located above the bottom of the recirculation screens up to and including the bottom surface of the plate discussed in Table 2.2.3-4, item 8.c.vii, out at least 10 feet perpendicular to and at least 7 feet perpendicular to the side of the screen face.
199 2.2.03.08c.xiv  8.c) The PXS provides RCS                xiv) Inspections will be            xiv) These surfaces are made makeup, boration, and safety            conducted of the exposed            of stainless steel or titanium.
injection during design basis events. surfaces of the source range, intermediate range, and power range detectors.
200  2.2.03.08d    8.d) The PXS provides pH                Inspections of the pH adjustment    pH adjustment baskets exist, adjustment of water flooding the        baskets will be conducted.          with a total calculated volume containment following design basis                                            560 ft3.
accidents.                                                                  The pH baskets are located below plant elevation 107 ft, 2 in.
201  2.2.03.09a.i  9.a) The PXS provides a function to      i) A flow test and analysis for    i) The calculated flow cool the outside of the reactor vessel  each IRWST drain line to the        resistance for each IRWST during a severe accident.                containment will be conducted.      drain line between the IRWST The test is initiated by opening    and the containment is isolation valves in each line.      4.07 x 10-6 ft/gpm2.
Test fixtures may be used to simulate squib valves.
C-144
 
Table 2.2.3-4 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No.              Design Commitment                  Inspections, Tests, Analyses        Acceptance Criteria 202 2.2.03.09a.ii  9.a) The PXS provides a function to      ii) Inspections of the as-built  ii) The combined total flow cool the outside of the reactor vessel    reactor vessel insulation will be area of the water inlets is not during a severe accident.                performed.                        less than 6 ft2. The combined total flow area of the steam outlet(s) is not less than 12 ft2.
A report exists and concludes that the minimum flow area between the vessel insulation and reactor vessel for the flow path that vents steam is not less than 12 ft2 considering the maximum deflection of the vessel insulation with a static pressure of 12.95 ft of water.
203 2.2.03.09a.iii 9.a) The PXS provides a function to      iii) Inspections will be          iii) A flow path with a flow cool the outside of the reactor vessel    conducted of the flow path(s)    area not less than 6 ft2 exists during a severe accident.                from the loop compartments to    from the loop compartment to the reactor vessel cavity.        the reactor vessel cavity.
204  2.2.03.09b    9.b) The accumulator discharge            An inspection of the accumulator  The accumulator discharge check valves (PXS-PL-V028A/B and          and CMT discharge check valves    check valves are of a different V029A/B) are of a different check        is performed.                    check valve type than the valve type than the CMT discharge                                          CMT discharge check valves.
check valves (PXS-PL-V016A/B and V017A/B).
205  2.2.03.09c  9.c) The equipment listed in              Type tests, analyses, or a        A report exists and concludes Table 2.2.3-6 has sufficient thermal      combination of type tests and    that the thermal lag of this lag to withstand the effects of          analyses will be performed to    equipment is greater than the identified hydrogen burns associated      determine the thermal lag of this value required.
with severe accidents.                    equipment.
206  2.2.03.10    10. Safety-related displays of the        Inspection will be performed for  Safety-related displays parameters identified in Table 2.2.3-1    the retrievability of the safety- identified in Table 2.2.3-1 can can be retrieved in the MCR.              related displays in the MCR.      be retrieved in the MCR.
207  2.2.03.11a.i  11.a) Controls exist in the MCR to        i) Testing will be performed on  i) Controls in the MCR cause the remotely operated valves        the squib valves identified in    operate to cause a signal at the identified in Table 2.2.3-1 to perform    Table 2.2.3-1 using controls in  squib valve electrical leads their active function(s).                the MCR, without stroking the    that is capable of actuating the valve.                            squib valve.
208 2.2.03.11a.ii  11.a) Controls exist in the MCR to        ii) Stroke testing will be        ii) Controls in the MCR cause the remotely operated valves        performed on remotely operated    operate to cause remotely identified in Table 2.2.3-1 to perform    valves other than squib valves    operated valves other than their active function(s).                identified in Table 2.2.3-1 using squib valves to perform their the controls in the MCR.          active functions.
C-145
 
Table 2.2.3-4 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No.              Design Commitment                    Inspections, Tests, Analyses        Acceptance Criteria 209  2.2.03.11b.i  11.b) The valves identified in            i) Testing will be performed on    i) Squib valves receive an Table 2.2.3-1 as having PMS control      the squib valves identified in    electrical signal at the valve perform their active function after      Table 2.2.3-1 using real or        electrical leads that is capable receiving a signal from the PMS.          simulated signals into the PMS    of actuating the valve after a without stroking the valve.        signal is input to the PMS.
210 2.2.03.11b.ii  11.b) The valves identified in            ii) Testing will be performed on  ii) Remotely operated valves Table 2.2.3-1 as having PMS control      the remotely operated valves      other than squib valves perform their active function after      other than squib valves identified perform the active function receiving a signal from the PMS.          in Table 2.2.3-1 using real or    identified in the table after a simulated signals into the PMS. signal is input to the PMS.
211 2.2.03.11b.iii 11.b) The valves identified in            iii) Testing will be performed to  iii) These valves open within Table 2.2.3-1 as having PMS control      demonstrate that remotely          20 seconds after receipt of an perform their active function after      operated PXS isolation valves      actuation signal.
receiving a signal from the PMS.          PXS-V014A/B, V015A/B, V108A/B open within the required response times.
212  2.2.03.11c.i  11.c) The valves identified in            i) Testing will be performed on    i) Squib valves receive an Table 2.2.3-1 as having DAS control      the squib valves identified in    electrical signal at the valve perform their active function after      Table 2.2.3-1 using real or        electrical leads that is capable receiving a signal from the DAS.          simulated signals into the DAS    of actuating the valve after a without stroking the valve.        signal is input to the DAS.
213 2.2.03.11c.ii  11.c) The valves identified in            ii) Testing will be performed on  ii) Remotely operated valves Table 2.2.3-1 as having DAS control      the remotely operated valves      other than squib valves perform their active function after      other than squib valves identified perform the active function receiving a signal from the DAS.          in Table 2.2.3-1 using real or    identified in Table 2.2.3-1 simulated signals into the DAS. after a signal is input to the DAS.
214  2.2.03.12a.i  12.a) The squib valves and check          i) Tests or type tests of squib    i) A test report exists and valves identified in Table 2.2.3-1        valves will be performed that      concludes that each squib perform an active safety-related          demonstrate the capability of the  valve changes position as function to change position as            valve to operate under its design  indicated in Table 2.2.3-1 indicated in the table.                  condition.                        under design conditions.
215 2.2.03.12a.ii  12.a) The squib valves and check          ii) Inspection will be performed  ii) A report exists and valves identified in Table 2.2.3-1        for the existence of a report      concludes that the as-built perform an active safety-related          verifying that the as-built squib  squib valves are bounded by function to change position as            valves are bounded by the tests    the tests or type tests.
indicated in the table.                  or type tests.
216 2.2.03.12a.iv  12.a) The squib valves and check          iv) Exercise testing of the check  iv) Each check valve changes valves identified in Table 2.2.3-1        valves with active safety          position as indicated in perform an active safety-related          functions identified in            Table 2.2.3-1 function to change position as            Table 2.2.3-1 will be performed indicated in the table.                  under preoperational test pressure, temperature, and fluid flow conditions.
C-146
 
Table 2.2.3-4 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No.                Design Commitment                  Inspections, Tests, Analyses            Acceptance Criteria 217  2.2.03.12b      12.b) After loss of motive power, the    Testing of the remotely operated    After loss of motive power, remotely operated valves identified      valves will be performed under      each remotely operated valve in Table 2.2.3-1 assume the indicated    the conditions of loss of motive    identified in Table 2.2.3-1 loss of motive power position.            power.                              assumes the indicated loss of motive power position.
218  2.2.03.13      13. Displays of the parameters            Inspection will be performed for    Displays identified in identified in Table 2.2.3-3 can be        retrievability of the displays      Table 2.2.3-3 can be retrieved retrieved in the MCR.                    identified in Table 2.2.3-3 in the  in the MCR.
MCR.
Table 2.2.3-5 Component Name                                    Tag No.                    Component Location Passive Residual Heat Removal Heat                          PXS-ME-01                    Containment Building Exchanger (PRHR HX)
Accumulator Tank A                                          PXS-MT-01A                    Containment Building Accumulator Tank B                                          PXS-MT-01B                    Containment Building Core Makeup Tank (CMT) A                                    PXS-MT-02A                    Containment Building CMT B                                                      PXS-MT-02B                    Containment Building IRWST                                                        PXS-MT-03                    Containment Building IRWST Screen A                                            PXS-MY-Y01A                    Containment Building IRWST Screen B                                            PXS-MY-Y01B                    Containment Building IRWST Screen C                                            PXS-MY-Y01C                    Containment Building Containment Recirculation Screen A                        PXS-MY-Y02A                    Containment Building Containment Recirculation Screen B                        PXS-MY-Y02B                    Containment Building pH Adjustment Basket 3A                                    PXS-MY-Y03A                    Containment Building pH Adjustment Basket 3B                                    PXS-MY-Y03B                    Containment Building pH Adjustment Basket 4A                                    PXS-MY-Y04A                    Containment Building pH Adjustment Basket 4B                                    PXS-MY-Y04B                    Containment Building C-147
 
Table 2.2.3-6 Equipment                          Tag No.              Function Hot Leg Sample Isolation Valves              PSS-PL-V001A/B          Transfer open Liquid Sample Line Containment Isolation      PSS-PL-V010A/B          Transfer open Valves IRC Containment Pressure Sensors                  PCS-012, 013, 014        Sense pressure RCS Wide Range Pressure Sensors              RCS-191A, B, C, D        Sense pressure SG1 Wide Range Level Sensors              SGS-011, 012, 015, 016      Sense level SG2 Wide Range Level Sensors              SGS-013, 014, 017, 018      Sense level Hydrogen Monitors                            VLS-001, 002, 003    Sense concentration Hydrogen Igniters                          VLS-EH-01 through 64      Ignite hydrogen Containment Electrical Penetrations        P01, P02, P03, P06, P09, Maintain containment P10, P11, P12, P13, P14,      boundary P15, P16, P18, P21, P22, P23, P24, P25, P26, P27, P28, P29, P30, P31, P32 C-148
 
Figure 2.2.3-1 (Sheet 1 of 2)
Passive Core Cooling System C-149
 
Figure 2.2.3-1 (Sheet 2 of 2)
Passive Core Cooling System C-150
 
2.2.4          Steam Generator System Design Description The steam generator system (SGS) and portions of the main and startup feedwater system (FWS) transport and control feedwater from the condensate system to the steam generators during normal operation. The SGS and portions of the main steam system (MSS) and turbine system (MTS) transport and control steam from the steam generators to the turbine generator during normal operations. These systems also isolate the steam generators from the turbine generator and the condensate system during design basis accidents.
The SGS is as shown in Figure 2.2.4-1, sheets 1 and 2, and portions of the FWS, MSS, and MTS are as shown in Figure 2.2.4-1, sheet 3, and the locations of the components in these systems is as shown in Table 2.2.4-5.
: 1. The functional arrangement of the SGS and portions of the FWS, MSS, and MTS are as described in the Design Description of this Section 2.2.4.
: 2. a) The components identified in Table 2.2.4-1 as ASME Code Section III are designed and constructed in accordance with ASME Code Section III requirements.
b) The piping identified in Table 2.2.4-2 as ASME Code Section III is designed and constructed in accordance with ASME Code Section III requirements.
: 3. a) Pressure boundary welds in components identified in Table 2.2.4-1 as ASME Code Section III meet ASME Code Section III requirements.
b) Pressure boundary welds in piping identified in Table 2.2.4-2 as ASME Code Section III meet ASME Code Section III requirements.
: 4. a) The components identified in Table 2.2.4-1 as ASME Code Section III retain their pressure boundary integrity at their design pressure.
b) The piping identified in Table 2.2.4-2 as ASME Code Section III retains its pressure boundary integrity at its design pressure.
: 5. a) The seismic Category I equipment identified in Table 2.2.4-1 can withstand seismic design basis loads without loss of safety function.
b) Each of the lines identified in Table 2.2.4-2 for which functional capability is required is designed to withstand combined normal and seismic design basis loads without a loss of its functional capability.
: 6. Each of the as-built lines identified in Table 2.2.4-2 as designed for leak before break (LBB) meets the LBB criteria, or an evaluation is performed of the protection from the dynamic effects of a rupture of the line.
: 7. a) The Class 1E equipment identified in Table 2.2.4-1 as being qualified for a harsh environment can withstand the environmental conditions that would exist before, during, and following a design basis accident without loss of safety function for the time required to perform the safety function.
C-151
 
b) The Class 1E components identified in Table 2.2.4-1 are powered from their respective Class 1E division.
c) Separation is provided between SGS Class 1E divisions, and between Class 1E divisions and non-Class 1E cable.
: 8. The SGS provides the following safety-related functions:
a) The SGS provides a heat sink for the reactor coolant system (RCS) and provides overpressure protection.
b) During design basis events, the SGS limits steam generator blowdown and feedwater flow to the steam generator.
c) The SGS preserves containment integrity by isolation of the SGS lines penetrating the containment. The inside containment isolation function (isolating the RCS and containment atmosphere from the environment) is provided by the steam generator, tubes, and SGS lines inside containment while isolation outside containment is provided by manual and automatic valves.
: 9. The SGS provides the following nonsafety-related functions:
a) Components within the main steam system, main and startup feedwater system, and the main turbine system identified in Table 2.2.4-3 provide backup isolation of the SGS to limit steam generator blowdown and feedwater flow to the steam generator.
b) During shutdown operations, the SGS removes decay heat by delivery of startup feedwater to the steam generator and venting of steam from the steam generators to the atmosphere.
: 10. Safety-related displays identified in Table 2.2.4-1 can be retrieved in the main control room (MCR).
: 11. a) Controls exist in the MCR to cause the remotely operated valves identified in Table 2.2.4-1 to perform active functions.
b) The valves identified in Table 2.2.4-1 as having PMS control perform an active safety function after receiving a signal from PMS.
: 12. a) The motor-operated valves identified in Table 2.2.4-1 perform an active safety-related function to change position as indicated in the table.
b) After loss of motive power, the remotely operated valves identified in Table 2.2.4-1 assume the indicated loss of motive power position.
C-152
 
Table 2.2.4-1 ASME                                                                Loss of Code          Remotely      Class 1E/  Safety-                  Motive Section Seismic Operated      Qual. for  Related Control  Active    Power Equipment Name      Tag No.      III    Cat. I  Valve      Harsh Envir. Display  PMS    Function  Position Main Steam Safety SGS-PL-V030A  Yes    Yes      -            -/-      No      -    Transfer    -
Valve SG01                                                                                Open/
Transfer Closed Main Steam Safety SGS-PL-V030B  Yes    Yes      -            -/-      No      -    Transfer    -
Valve SG02                                                                                Open/
Transfer Closed Main Steam Safety SGS-PL-V031A  Yes    Yes      -            -/-      No      -    Transfer    -
Valve SG01                                                                                Open/
Transfer Closed Main Steam Safety SGS-PL-V031B  Yes    Yes      -            -/-      No      -    Transfer    -
Valve SG02                                                                                Open/
Transfer Closed Main Steam Safety SGS-PL-V032A  Yes    Yes      -            -/-      No      -    Transfer    -
Valve SG01                                                                                Open/
Transfer Closed Main Steam Safety SGS-PL-V032B  Yes    Yes      -            -/-      No      -    Transfer    -
Valve SG02                                                                                Open/
Transfer Closed Main Steam Safety SGS-PL-V033A  Yes    Yes      -            -/-      No      -    Transfer    -
Valve SG01                                                                                Open/
Transfer Closed C-153
 
Table 2.2.4-1 ASME                                                                  Loss of Code          Remotely      Class 1E/  Safety-                    Motive Section Seismic Operated      Qual. for  Related  Control  Active    Power Equipment Name        Tag No. III    Cat. I  Valve      Harsh Envir. Display    PMS    Function  Position Main Steam Safety  SGS-PL-V033B  Yes    Yes      -            -/-        No        -    Transfer    -
Valve SG02                                                                                    Open/
Transfer Closed Main Steam Safety  SGS-PL-V034A  Yes    Yes      -            -/-        No        -    Transfer    -
Valve SG01                                                                                    Open/
Transfer Closed Main Steam Safety  SGS-PL-V034B  Yes    Yes      -            -/-        No        -    Transfer    -
Valve SG02                                                                                    Open/
Transfer Closed Main Steam Safety  SGS-PL-V035A  Yes    Yes      -            -/-        No        -    Transfer    -
Valve SG01                                                                                    Open/
Transfer Closed Main Steam Safety  SGS-PL-V035B  Yes    Yes      -            -/-        No        -    Transfer    -
Valve SG02                                                                                    Open/
Transfer Closed Power-operated    SGS-PL-V027A  Yes    Yes      Yes          Yes/Yes  Yes (Valve  Yes    Transfer  As Is Relief Valve Block                                                        Position)          Closed Motor-operated Valve Steam Generator 01 Power-operated    SGS-PL-V027B  Yes    Yes      Yes          Yes/Yes  Yes (Valve  Yes    Transfer  As Is Relief Valve Block                                                        Position)          Closed Motor-operated Valve Steam Generator 02 Steam Line        SGS-PL-V036A  Yes    Yes      Yes          Yes/Yes  Yes (Valve  Yes    Transfer  Closed Condensate Drain                                                          Position)          Closed Isolation Valve C-154
 
Table 2.2.4-1 ASME                                                                  Loss of Code          Remotely      Class 1E/  Safety-                    Motive Section Seismic Operated      Qual. for  Related  Control  Active    Power Equipment Name      Tag No.      III    Cat. I  Valve      Harsh Envir. Display    PMS    Function  Position Steam Line        SGS-PL-V036B  Yes    Yes      Yes          Yes/Yes  Yes (Valve  Yes    Transfer  Closed Condensate Drain                                                          Position)          Closed Isolation Valve Main Steam Line    SGS-PL-V040A  Yes    Yes      Yes          Yes/Yes  Yes (Valve  Yes    Transfer  As Is Isolation Valve                                                            Position)          Closed Main Steam Line    SGS-PL-V040B  Yes    Yes      Yes          Yes/Yes  Yes (Valve  Yes    Transfer  As Is Isolation Valve                                                            Position)          Closed Steam Line        SGS-PL-V086A  Yes    Yes      Yes          Yes/Yes      No        Yes    Transfer  Closed Condensate Drain                                                                              Closed Control Valve Steam Line        SGS-PL-V086B  Yes    Yes      Yes          Yes/Yes      No        Yes    Transfer  Closed Condensate Drain                                                                              Closed Control Valve Main Feedwater    SGS-PL-V057A  Yes    Yes      Yes          Yes/Yes  Yes (Valve  Yes    Transfer  As Is Isolation Valve                                                            Position)          Closed Main Feedwater    SGS-PL-V057B  Yes    Yes      Yes          Yes/Yes  Yes (Valve  Yes    Transfer  As Is Isolation Valve                                                            Position)          Closed Startup Feedwater  SGS-PL-V067A  Yes    Yes      Yes          Yes/Yes  Yes (Valve  Yes    Transfer  As Is Isolation Motor-                                                          Position)          Closed operated Valve Startup Feedwater  SGS-PL-V067B  Yes    Yes      Yes          Yes/Yes  Yes (Valve  Yes    Transfer  As Is Isolation Motor-                                                          Position)          Closed operated Valve Steam Generator    SGS-PL-V074A  Yes    Yes      Yes          Yes/Yes  Yes (Valve  Yes    Transfer  Closed Blowdown Isolation                                                        Position)          Closed Valve C-155
 
Table 2.2.4-1 ASME                                                                  Loss of Code          Remotely      Class 1E/  Safety-                    Motive Section Seismic Operated      Qual. for  Related  Control  Active    Power Equipment Name      Tag No.      III    Cat. I  Valve      Harsh Envir. Display    PMS    Function  Position Steam Generator    SGS-PL-V074B  Yes    Yes      Yes          Yes/Yes  Yes (Valve  Yes    Transfer  Closed Blowdown Isolation                                                        Position)          Closed Valve Steam Generator    SGS-PL-V075A  Yes    Yes      Yes          Yes/Yes      No        Yes    Transfer  Closed Blowdown Isolation                                                                            Closed Valve Steam Generator    SGS-PL-V075B  Yes    Yes      Yes          Yes/Yes      No        Yes    Transfer  Closed Blowdown Isolation                                                                            Closed Valve Power-operated    SGS-PL-V233A  Yes    Yes      Yes          Yes/Yes  Yes (Valve  Yes    Transfer  Closed Relief Valve                                                              Position)          Closed Power-operated    SGS-PL-V233B  Yes    Yes      Yes          Yes/Yes  Yes (Valve  Yes    Transfer  Closed Relief Valve                                                              Position)          Closed Main Steam        SGS-PL-V240A  Yes    Yes      Yes          Yes/Yes  Yes (Valve  Yes    Transfer  Closed Isolation Valve                                                            Position)          Closed Bypass Isolation Main Steam        SGS-PL-V240B  Yes    Yes      Yes          Yes/Yes  Yes (Valve  Yes    Transfer  Closed Isolation Valve                                                            Position)          Closed Bypass Isolation Main Feedwater    SGS-PL-V250A  Yes    Yes      Yes          Yes/Yes  Yes (Valve  Yes    Transfer  Closed Control Valve                                                              Position)          Closed Main Feedwater    SGS-PL-V250B  Yes    Yes      Yes          Yes/Yes  Yes (Valve  Yes    Transfer  Closed Control Valve                                                              Position)          Closed Startup Feedwater  SGS-PL-V255A  Yes    Yes      Yes          Yes/Yes  Yes (Valve  Yes    Transfer  Closed Control Valve                                                              Position)          Closed C-156
 
Table 2.2.4-1 ASME                                                                  Loss of Code          Remotely      Class 1E/  Safety-                    Motive Section Seismic Operated      Qual. for  Related  Control  Active    Power Equipment Name      Tag No.      III    Cat. I  Valve      Harsh Envir. Display    PMS    Function  Position Startup Feedwater  SGS-PL-V255B  Yes    Yes      Yes          Yes/Yes  Yes (Valve  Yes    Transfer  Closed Control Valve                                                              Position)          Closed Steam Generator 1    SGS-001      No      Yes      -          Yes/Yes      Yes        -        -        -
Narrow Range Level Sensor Steam Generator 1    SGS-002      No      Yes      -          Yes/Yes      Yes        -        -        -
Narrow Range Level Sensor Steam Generator 1    SGS-003      No      Yes      -          Yes/Yes      Yes        -        -        -
Narrow Range Level Sensor Steam Generator 1    SGS-004      No      Yes      -          Yes/Yes      Yes        -        -        -
Narrow Range Level Sensor Steam Generator 2    SGS-005      No      Yes      -          Yes/Yes      Yes        -        -        -
Narrow Range Level Sensor Steam Generator 2    SGS-006      No      Yes      -          Yes/Yes      Yes        -        -        -
Narrow Range Level Sensor Steam Generator 2    SGS-007      No      Yes      -          Yes/Yes      Yes        -        -        -
Narrow Range Level Sensor Steam Generator 2    SGS-008      No      Yes      -          Yes/Yes      Yes        -        -        -
Narrow Range Level Sensor C-157
 
Table 2.2.4-1 ASME                                                              Loss of Code          Remotely      Class 1E/  Safety-                  Motive Section Seismic Operated      Qual. for  Related Control  Active  Power Equipment Name    Tag No. III    Cat. I  Valve      Harsh Envir. Display  PMS    Function Position Steam Generator 1 SGS-011  No      Yes      -          Yes/Yes    Yes      -      -        -
Wide Range Level Sensor Steam Generator 1 SGS-012  No      Yes      -          Yes/Yes    Yes      -      -        -
Wide Range Level Sensor Steam Generator 2 SGS-013  No      Yes      -          Yes/Yes    Yes      -      -        -
Wide Range Level Sensor Steam Generator 2 SGS-014  No      Yes      -          Yes/Yes    Yes      -      -        -
Wide Range Level Sensor Steam Generator 1 SGS-015  No      Yes      -          Yes/Yes    Yes      -      -        -
Wide Range Level Sensor Steam Generator 1 SGS-016  No      Yes      -          Yes/Yes    Yes      -      -        -
Wide Range Level Sensor Steam Generator 2 SGS-017  No      Yes      -          Yes/Yes    Yes      -      -        -
Wide Range Level Sensor Steam Generator 2 SGS-018  No      Yes      -          Yes/Yes    Yes      -      -        -
Wide Range Level Sensor Main Steam Line  SGS-030  No      Yes      -          Yes/Yes    Yes      -      -        -
Steam Generator 1 Pressure Sensor C-158
 
Table 2.2.4-1 ASME                                                              Loss of Code          Remotely      Class 1E/  Safety-                  Motive Section Seismic Operated      Qual. for  Related Control  Active  Power Equipment Name    Tag No. III    Cat. I  Valve      Harsh Envir. Display  PMS    Function Position Main Steam Line  SGS-031  No      Yes      -          Yes/No      Yes      -      -        -
Steam Generator 1 Pressure Sensor Main Steam Line  SGS-032  No      Yes      -          Yes/Yes    Yes      -      -        -
Steam Generator 1 Pressure Sensor Main Steam Line  SGS-033  No      Yes      -          Yes/No      Yes      -      -        -
Steam Generator 1 Pressure Sensor Main Steam Line  SGS-034  No      Yes      -          Yes/Yes    Yes      -      -        -
Steam Generator 2 Pressure Sensor Main Steam Line  SGS-035  No      Yes      -          Yes/No      Yes      -      -        -
Steam Generator 2 Pressure Sensor Main Steam Line  SGS-036  No      Yes      -          Yes/Yes    Yes      -      -        -
Steam Generator 2 Pressure Sensor Main Steam Line  SGS-037  No      Yes      -          Yes/No      Yes      -      -        -
Steam Generator 2 Pressure Sensor Steam Generator 1 SGS-55A  No      Yes      -          Yes/No      Yes      -      -        -
Startup Feedwater Flow Sensor Steam Generator 1 SGS-55B  No      Yes      -          Yes/No      Yes      -      -        -
Startup Feedwater Flow Sensor C-159
 
Table 2.2.4-1 ASME                                                              Loss of Code          Remotely      Class 1E/  Safety-                  Motive Section Seismic Operated      Qual. for  Related Control  Active  Power Equipment Name            Tag No.        III    Cat. I  Valve      Harsh Envir. Display  PMS    Function Position Steam Generator 2        SGS-56A        No      Yes      -          Yes/No      Yes      -      -        -
Startup Feedwater Flow Sensor Steam Generator 2        SGS-56B        No      Yes      -          Yes/No      Yes      -      -        -
Startup Feedwater Flow Sensor Note: Dash (-) indicates not applicable.
C-160
 
Table 2.2.4-2 Functional ASME Code    Leak Before Capability Line Name                        Line Number            Section III  Break      Required Main Feedwater Line                    SGS-PL-L002A, L002B                Yes          No        No Main Feedwater Line                    SGS-PL-L003A, L003B                Yes          No        No Startup Feedwater Line                  SGS-PL-L004A, L004B                Yes          No        No Startup Feedwater Line                  SGS-PL-L005A, L005B                Yes          No        No Main Steam Line (within containment)    SGS-PL-L006A, L006B                Yes        Yes        Yes Main Steam Line (outside of            SGS-PL-L006A, L006B                Yes          No        Yes containment)
Main Steam Line                        SGS-PL-L007A, L007B                Yes          No        No Safety Valve Inlet Line                SGS-PL-L015A, L015B,              Yes          No        Yes L015C, L015D, L015E, L015F, L015G, L015H, L015J, L015K, L015L, L015M Safety Valve Discharge Line            SGS-PL-L018A, L018B,              Yes          No        Yes L018C, L018D, L018E, L018F, L018G, L018H, L018J, L018K, L018L, L018M Power-operated Relief Block Valve Inlet SGS-PL-L024A, L024B                Yes          No        No Line Power-operated Relief Valve Inlet Line  SGS-PL-L014A, L014B                Yes          No        No Main Steam Isolation Valve Bypass Inlet SGS-PL-L022A, L022B                Yes          No        No Line Main Steam Isolation Valve Bypass      SGS-PL-L023A, L023B                Yes          No        No Outlet Line C-161
 
Table 2.2.4-2 Functional ASME Code    Leak Before Capability Line Name                        Line Number            Section III  Break      Required Main Steam Condensate Drain Line        SGS-PL-L021A, L021B              Yes          No        No Steam Generator Blowdown Line            SGS-PL-L009A, L009B              Yes          No        No Steam Generator Blowdown Line            SGS-PL-L027A, L027B              Yes          No        No Steam Generator Blowdown Line            SGS-PL-L010A, L010B              Yes          No        No Note: Dash (-) indicates not applicable.
C-162
 
Table 2.2.4-3 Equipment Name                            Tag No. Control Function Turbine Stop Valve                                            MTS-PL-V001A      Close Turbine Stop Valve                                            MTS-PL-V001B      Close Turbine Control Valve                                        MTS-PL-V002A      Close Turbine Control Valve                                        MTS-PL-V002B      Close Turbine Stop Valve                                            MTS-PL-V003A      Close Turbine Stop Valve                                            MTS-PL-V003B      Close Turbine Control Valve                                        MTS-PL-V004A      Close Turbine Control Valve                                        MTS-PL-V004B      Close Turbine Bypass Control Valve                                  MSS-PL-V001      Close Turbine Bypass Control Valve                                  MSS-PL-V002      Close Turbine Bypass Control Valve                                  MSS-PL-V003      Close Turbine Bypass Control Valve                                  MSS-PL-V004      Close Turbine Bypass Control Valve                                  MSS-PL-V005      Close Turbine Bypass Control Valve                                  MSS-PL-V006      Close Moisture Separator Reheater 2nd Stage Steam Isolation Valve  MSS-PL-V015A      Close Moisture Separator Reheater 2nd Stage Steam Isolation Valve  MSS-PL-V015B      Close Main Feedwater Pump                                            FWS-MP-02A        Trip Main Feedwater Pump                                            FWS-MP-02B        Trip Main Feedwater Pump                                            FWS-MP-02C        Trip Startup Feedwater Pump                                        FWS-MP-03A        Trip Startup Feedwater Pump                                        FWS-MP-03B        Trip C-163
 
Table 2.2.4-4 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No.              Design Commitment                    Inspections, Tests, Analyses          Acceptance Criteria 219    2.2.04.01 1. The functional arrangement of the          Inspection of the as-built system The as-built SGS and portions SGS and portions of the FWS, MSS,            will be performed.                of the FWS, MSS, and MTS and MTS are as described in the Design                                          conform with the functional Description of this Section 2.2.4.                                              arrangement as defined in the Design Description of this Section 2.2.4.
220  2.2.04.02a 2.a) The components identified in            Inspection will be conducted of  The ASME Code Section III Table 2.2.4-1 as ASME Code Section            the as-built components as        design reports exist for the III are designed and constructed in          documented in the ASME design    as-built components identified accordance with ASME Code Section            reports.                          in Table 2.2.4-1 as ASME III requirements.                                                              Code Section III.
221  2.2.04.02b 2.b) The piping identified in                Inspection will be conducted of  The ASME Code Section III Table 2.2.4-2 as ASME Code Section            the as-built piping as            design reports exist for the as-III is designed and constructed in            documented in the ASME design    built piping identified in accordance with ASME Code Section            reports.                          Table 2.2.4-2 as ASME Code III requirements.                                                              Section III.
222  2.2.04.03a 3.a) Pressure boundary welds in              Inspection of the as-built        A report exists and concludes components identified in Table 2.2.4-1        pressure boundary welds will be  that the ASME Code as ASME Code Section III meet ASME            performed in accordance with      Section III requirements are Code Section III requirements.                the ASME Code Section III.        met for non-destructive examination of pressure boundary welds.
223  2.2.04.03b 3.b) Pressure boundary welds in piping        Inspection of the as-built        A report exists and concludes identified in Table 2.2.4-2 as ASME          pressure boundary welds will be  that the ASME Code Code Section III meet ASME Code              performed in accordance with      Section III requirements are Section III requirements.                    the ASME Code Section III.        met for non-destructive examination of pressure boundary welds.
224  2.2.04.04a 4.a) The components identified in            A hydrostatic test will be        A report exists and concludes Table 2.2.4-1 as ASME Code Section            performed on the components      that the results of the III retain their pressure boundary            required by the ASME Code        hydrostatic test of the integrity at their design pressure.          Section III to be hydrostatically components identified in tested.                          Table 2.2.4-1 as ASME Code Section III conform with the requirements of the ASME Code Section III.
225  2.2.04.04b 4.b) The piping identified in                A hydrostatic test will be        A report exists and concludes Table 2.2.4-2 as ASME Code Section            performed on the piping required  that the results of the III retains its pressure boundary            by the ASME Code Section III to  hydrostatic test of the piping integrity at its design pressure.            be hydrostatically tested.        identified in Table 2.2.4-2 as ASME Code Section III conform with the requirements of the ASME Code Section III.
C-164
 
Table 2.2.4-4 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No.                Design Commitment                    Inspections, Tests, Analyses        Acceptance Criteria 226  2.2.04.05a.i  5.a) The seismic Category I equipment        i) Inspection will be performed    i) The seismic Category I identified in Table 2.2.4-1 can withstand    to verify that the seismic        equipment identified in seismic design basis loads without loss      Category I equipment identified    Table 2.2.4-1 is located on the of safety function.                          in Table 2.2.4-1 is located on the Nuclear Island.
Nuclear Island.
227  2.2.04.05a.ii  5.a) The seismic Category I equipment        ii) Type tests, analyses, or a    ii) A report exists and identified in Table 2.2.4-1 can withstand    combination of type tests and      concludes that the seismic seismic design basis loads without loss      analyses of seismic Category I    Category I equipment can of safety function.                          equipment will be performed.      withstand seismic design basis loads without loss of safety function.
228  2.2.04.05a.iii 5.a) The seismic Category I equipment        iii) Inspection will be performed  iii) A report exists and identified in Table 2.2.4-1 can withstand    for the existence of a report      concludes that the as-built seismic design basis loads without loss      verifying that the as-built        equipment including of safety function.                          equipment including anchorage      anchorage is seismically is seismically bounded by the      bounded by the tested or tested or analyzed conditions. analyzed conditions.
229  2.2.04.05b    5.b) Each of the lines identified in        Inspection will be performed for  A report exists and concludes Table 2.2.4-2 for which functional          the existence of a report          that each of the as-built lines capability is required is designed to        concluding that the as-built      identified in Table 2.2.4-2 for withstand combined normal and seismic        piping meets the requirements      which functional capability is design basis loads without a loss of its    for functional capability.        required meets the functional capability.                                                          requirements for functional capability.
230    2.2.04.06    6. Each of the as-built lines identified    Inspection will be performed for  An LBB evaluation report in Table 2.2.4-2 as designed for LBB        the existence of an LBB            exists and concludes that the meets the LBB criteria, or an evaluation    evaluation report or an            LBB acceptance criteria are is performed of the protection from the      evaluation report on the          met by the as-built RCS dynamic effects of a rupture of the line. protection from effects of a pipe  piping and piping materials, or break. Section 3.3, Nuclear        a pipe break evaluation report Island Buildings, contains the    exists and concludes that design descriptions and            protection from the dynamic inspections, tests, analyses, and  effects of a line break is acceptance criteria for protection provided.
from the dynamic effects of pipe rupture.
C-165
 
Table 2.2.4-4 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No.                Design Commitment                  Inspections, Tests, Analyses        Acceptance Criteria 231  2.2.04.07a.i  7.a) The Class 1E equipment identified      i) Type tests, analyses, or a    i) A report exists and in Table 2.2.4-1 as being qualified for a  combination of type tests and    concludes that the Class 1E harsh environment can withstand the        analyses will be performed on    equipment identified in Table environmental conditions that would        Class 1E equipment located in a  2.2.4-1 as being qualified for a exist before, during, and following a      harsh environment.                harsh environment can design basis accident without loss of                                        withstand the environmental safety function for the time required to                                      conditions that would exist perform the safety function.                                                  before, during, and following a design basis accident without loss of safety function for the time required to perform the safety function.
232  2.2.04.07a.ii 7.a) The Class 1E equipment identified      ii) Inspection will be performed  ii) A report exists and in Table 2.2.4-1 as being qualified for a  of the as-built Class 1E          concludes that the as-built harsh environment can withstand the        equipment and the associated      Class 1E equipment and the environmental conditions that would        wiring, cables, and terminations  associated wiring, cables, and exist before, during, and following a      located in a harsh environment. terminations identified in design basis accident without loss of                                        Table 2.2.4-1 as being safety function for the time required to                                      qualified for a harsh perform the safety function.                                                  environment are bounded by type tests, analyses, or a combination of type tests and analyses.
233  2.2.04.07b  7.b) The Class 1E components                Testing will be performed by      A simulated test signal exists identified in Table 2.2.4-1 are powered    providing a simulated test signal at the Class 1E equipment from their respective Class 1E division. in each Class 1E division.        identified in Table 2.2.4-1 when the assigned Class 1E division is provided the test signal.
234  2.2.04.07c  7.c) Separation is provided between        See ITAAC Table 3.3-6, item      See ITAAC Table 3.3-6, item SGS Class 1E divisions, and between        7.d.                              7.d.
Class 1E divisions and non-Class 1E cable.
235  2.2.04.08a.i  8.a) The SGS provides a heat sink for      i) Inspections will be conducted  i) The sum of the rated the RCS and provides overpressure          to confirm that the value of the  capacities recorded on the protection in accordance with Section      vendor code plate rating of the  valve vendor code plates of III of the ASME Boiler and Pressure        steam generator safety valves is  the steam generator safety Vessel Code.                                greater than or equal to system  valves exceeds 8,240,000 lb/hr relief requirements.              per steam generator.
236  2.2.04.08a.ii 8.a) The SGS provides a heat sink for      ii) Testing and analyses in      ii) A report exists to indicate the RCS and provides overpressure          accordance with ASME Code        the set pressure of the valves protection in accordance with Section      Section III will be performed to  is less than 1305 psig.
III of the ASME Boiler and Pressure        determine set pressure.
Vessel Code.
C-166
 
Table 2.2.4-4 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No.              Design Commitment                    Inspections, Tests, Analyses        Acceptance Criteria 237  2.2.04.08b.i  8.b) During design basis events, the        i) Testing will be performed to    See item 11 in this table.
SGS limits steam generator blowdown          confirm isolation of the main and feedwater flow to the steam              feedwater, startup feedwater, generator.                                  blowdown, and main steam lines. See item 11 in this table.
238  2.2.04.08b.ii 8.b) During design basis events, the        ii) Inspection will be performed  ii) A report exists to indicate SGS limits steam generator blowdown          for the existence of a report      the installed flow limiting and feedwater flow to the steam              confirming that the area of the    orifice within the SG main generator.                                  flow limiting orifice within the  steam line discharge nozzle SG main steam outlet nozzle will  does not exceed 1.4 sq. ft.
limit releases to the containment.
239  2.2.04.08c  8.c) The SGS preserves containment          See ITAAC Table 2.2.1-3,          See ITAAC Table 2.2.1-3, integrity by isolation of the SGS lines      item 7.                            item 7.
penetrating the containment.
240  2.2.04.09a.i  9.a) Components within the main              i) Testing will be performed to    i) The valves identified in steam system, main and startup              confirm closure of the valves      Table 2.2.4-3 close after a feedwater system, and the main turbine      identified in Table 2.2.4-3.      signal is generated by the system identified in Table 2.2.4-3                                              PMS.
provide backup isolation of the SGS to limit steam generator blowdown and feedwater flow to the steam generator.
241  2.2.04.09a.ii 9.a) Components within the main              ii) Testing will be performed to  ii) The pumps identified in steam system, main and startup              confirm the trip of the pumps      Table 2.2.4-3 trip after a signal feedwater system, and the main turbine      identified in Table 2.2.4-3.      is generated by the PMS.
system identified in Table 2.2.4-3 provide backup isolation of the SGS to limit steam generator blowdown and feedwater flow to the steam generator.
242  2.2.04.09b.i  9.b) During shutdown operations, the        i) Tests will be performed to      i) See ITAAC Table 2.4.1-2, SGS removes decay heat by delivery of        demonstrate the ability of the    Item 2.
startup feedwater to the steam generator    startup feedwater system to and venting of steam from the steam          provide feedwater to the steam generators to the atmosphere.                generators.
243  2.2.04.09b.ii 9.b) During shutdown operations, the        ii) Type tests and/or analyses    ii) A report exists and SGS removes decay heat by delivery of        will be performed to demonstrate  concludes that each power-startup feedwater to the steam generator    the ability of the power-operated  operated relief valve will and venting of steam from the steam          relief valves to discharge steam  relieve greater than 300,000 generators to the atmosphere.                from the steam generators to the  lb/hr at 1106 psia +/-10 psi.
atmosphere.
244    2.2.04.10  10. Safety-related displays identified in    Inspection will be performed for  Safety-related displays Table 2.2.4-1 can be retrieved in the        retrievability of the safety-      identified in Table 2.2.4-1 can MCR.                                        related displays in the MCR.      be retrieved in the MCR.
C-167
 
Table 2.2.4-4 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No.                Design Commitment                    Inspections, Tests, Analyses          Acceptance Criteria 245    2.2.04.11a  11.a) Controls exist in the MCR to          Stroke testing will be performed  Controls in the MCR operate cause the remotely operated valves          on the remotely operated valves    to cause the remotely operated identified in Table 2.2.4-1 to perform      listed in Table 2.2.4-1 using      valves to perform active safety active functions.                          controls in the MCR.              functions.
246  2.2.04.11b.i  11.b) The valves identified in Table        i) Testing will be performed on    i) The remotely-operated 2.2.4-1 as having PMS control perform      the remotely operated valves      valves identified in Table an active safety function after receiving  listed in Table 2.2.4-1 using real 2.2.4-1 as having PMS control a signal from PMS.                          or simulated signals into the      perform the active function PMS.                              identified in the table after receiving a signal from the PMS.
247  2.2.04.11b.ii  11.b) The valves identified in Table        ii) Testing will be performed to  ii) These valves close within 2.2.4-1 as having PMS control perform      demonstrate that remotely          the following times after an active safety function after receiving  operated SGS isolation valves      receipt of an actuation signal:
a signal from PMS.                          SGS-V027A/B, V040A/B,              V027A/B                < 44sec V057A/B, V250A/B close            V040A/B, V057A/B < 5 sec within the required response      V250A/B                < 5 sec times.
248  2.2.04.12a.i  12.a) The motor-operated valves            i) Tests or type tests of motor-  i) A test report exists and identified in Table 2.2.4-1 perform an      operated valves will be            concludes that each motor-active safety-related function to change    performed to demonstrate the      operated valve changes position as indicated in the table.        capability of the valve to operate position as indicated in Table under its design conditions.      2.2.4-1 under design conditions.
249  2.2.04.12a.ii  12.a) The motor-operated valves            ii) Inspection will be performed  ii) A report exists and identified in Table 2.2.4-1 perform an      for the existence of a report      concludes that the as-built active safety-related function to change    verifying that the as-built motor- motor-operated valves are position as indicated in the table.        operated valves are bounded by    bounded by the tests or type the tests or type tests.          tests.
250  2.2.04.12a.iii 12.a) The motor-operated valves            iii) Tests of the motor-operated  iii) Each motor-operated valve identified in Table 2.2.4-1 perform an      valves will be performed under    changes position as indicated active safety-related function to change    pre-operational flow, differential in Table 2.2.4-1 under pre-position as indicated in the table.        pressure, and temperature          operational test conditions.
conditions.
251    2.2.04.12b  12.b) After loss of motive power, the      Testing of the remotely operated  After loss of motive power, remotely operated valves identified in      valves will be performed under    each remotely operated valve Table 2.2.4-1 assume the indicated loss    the conditions of loss of motive  identified in Table 2.2.4-1 of motive power position.                  power.                            assumes the indicated loss of motive power position.
Motive power to SGS-PL-V040A/B and SGS-PL-V057A/B is electric power to the actuator from plant services.
C-168
 
Table 2.2.4-5 Component Name            Tag No. Component Location Main Steam Line Isolation Valve  SGS-PL-V040A  Auxiliary Building Main Steam Line Isolation Valve  SGS-PL-V040B  Auxiliary Building Main Feedwater Isolation Valve  SGS-PL-V057A  Auxiliary Building Main Feedwater Isolation Valve  SGS-PL-V057B  Auxiliary Building Main Feedwater Control Valve    SGS-PL-V250A  Auxiliary Building Main Feedwater Control Valve    SGS-PL-V250B  Auxiliary Building Turbine Stop Valves              MTS-PL-V001A  Turbine Building MTS-PL-V001B MTS-PL-V003A MTS-PL-V003B Turbine Control Valves          MTS-PL-V002A  Turbine Building MTS-PL-V002B MTS-PL-V004A MTS-PL-V004B Main Feedwater Pumps              FWS-MP-02A    Turbine Building FWS-MP-02B FWS-MP-02C Feedwater Booster Pumps          FWS-MP-01A    Turbine Building FWS-MP-01B FWS-MP-01C C-169
 
Figure 2.2.4-1 (Sheet 1 of 3)
Steam Generator System C-170
 
Figure 2.2.4-1 (Sheet 2 of 3)
Steam Generator System C-171
 
Figure 2.2.4-1 (Sheet 3 of 3)
Steam Generator System C-172
 
2.2.5          Main Control Room Emergency Habitability System Design Description The main control room emergency habitability system (VES) provides a supply of breathable air for the main control room (MCR) occupants and maintains the MCR at a positive pressure with respect to the surrounding areas whenever ac power is not available to operate the nuclear island nonradioactive ventilation system (VBS) or high radioactivity is detected in the MCR air supply. (See Section 3.5 for Radiation Monitoring). The VES also limits the heatup of the MCR, the 1E instrumentation and control (I&C) equipment rooms, and the Class 1E dc equipment rooms by using the heat capacity of surrounding structures.
The VES is as shown in Figure 2.2.5-1 and the component locations of the VES are as shown in Table 2.2.5-6.
: 1. The functional arrangement of the VES is as described in the Design Description of this Section 2.2.5.
: 2. a) The components identified in Table 2.2.5-1 as ASME Code Section III are designed and constructed in accordance with ASME Code Section III requirements.
b) The piping identified in Table 2.2.5-2 as ASME Code Section III is designed and constructed in accordance with ASME Code Section III requirements.
: 3. a) Pressure boundary welds in components identified in Table 2.2.5-1 as ASME Code Section III meet ASME Code Section III requirements.
b) Pressure boundary welds in piping identified in Table 2.2.5-2 as ASME Code Section III meet ASME Code Section III requirements.
: 4. a) The components identified in Table 2.2.5-1 as ASME Code Section III retain their pressure boundary integrity at their design pressure.
b) The piping identified in Table 2.2.5-2 as ASME Code Section III retains its pressure boundary integrity at its design pressure.
: 5. a) The seismic Category I equipment identified in Table 2.2.5-1 can withstand seismic design basis loads without loss of safety function.
b) Each of the lines identified in Table 2.2.5-2 for which functional capability is required is designed to withstand combined normal and seismic design basis loads without a loss of its functional capability.
: 6. a) The Class 1E components identified in Table 2.2.5-1 are powered from their respective Class 1E division.
b) Separation is provided between VES Class 1E divisions, and between Class 1E divisions and non-Class 1E cable.
: 7. The VES provides the following safety-related functions:
C-173
 
a) The VES provides a 72-hour supply of breathable quality air for the occupants of the MCR.
b) The VES maintains the MCR pressure boundary at a positive pressure with respect to the surrounding areas. There is a discharge of air through the MCR vestibule.
c) The heat loads within the MCR, the I&C equipment rooms, and the Class 1E dc equipment rooms are within design basis assumptions to limit the heatup of the rooms identified in Table 2.2.5-4.
d) The system provides a passive recirculation flow of MCR air to maintain main control room dose rates below an acceptable level during VES operation.
e) The system provides shielding below the VES filter that is sufficient to ensure main control room doses are below an acceptable level during VES operation.
: 8. Safety-related displays identified in Table 2.2.5-1 can be retrieved in the MCR.
: 9. a) Controls exist in the MCR to cause those remotely operated valves identified in Table 2.2.5-1 to perform their active functions.
b) The valves identified in Table 2.2.5-1 as having protection and safety monitoring system (PMS) control perform their active safety function after receiving a signal from the PMS.
: 10. After loss of motive power, the remotely operated valves identified in Table 2.2.5-1 assume the indicated loss of motive power position.
: 11. Displays of the parameters identified in Table 2.2.5-3 can be retrieved in the MCR.
: 12. The background noise level in the MCR does not exceed 65 dB(A) at the operator workstations when the VES is operating.
C-174
 
Table 2.2.5-1 Class 1E/                          Loss of ASME                Remotely Qual. for Safety-                  Motive Code      Seismic    Operated  Harsh    Related Control  Active  Power Equipment Name      Tag No. Section III  Cat. I      Valve  Envir. Display  PMS    Function Position Emergency Air Storage VES-MT-01    No        Yes          -      -/-      -      -      -        -
Tank 01 Emergency Air Storage VES-MT-02    No        Yes          -      -/-      -      -      -        -
Tank 02 Emergency Air Storage VES-MT-03    No        Yes          -      -/-      -      -      -        -
Tank 03 Emergency Air Storage VES-MT-04    No        Yes          -      -/-      -      -      -        -
Tank 04 Emergency Air Storage VES-MT-05    No        Yes          -      -/-      -      -      -        -
Tank 05 Emergency Air Storage VES-MT-06    No        Yes          -      -/-      -      -      -        -
Tank 06 Emergency Air Storage VES-MT-07    No        Yes          -      -/-      -      -      -        -
Tank 07 Emergency Air Storage VES-MT-08    No        Yes          -      -/-      -      -      -        -
Tank 08 Emergency Air Storage VES-MT-09    No        Yes          -      -/-      -      -      -        -
Tank 09 Emergency Air Storage VES-MT-10    No        Yes          -      -/-      -      -      -        -
Tank 10 Emergency Air Storage VES-MT-11    No        Yes          -      -/-      -      -      -        -
Tank 11 Emergency Air Storage VES-MT-12    No        Yes          -      -/-      -      -      -        -
Tank 12 C-175
 
Table 2.2.5-1 Class 1E/                          Loss of ASME                Remotely Qual. for Safety-                  Motive Code      Seismic    Operated  Harsh    Related Control  Active  Power Equipment Name      Tag No. Section III  Cat. I      Valve  Envir. Display  PMS    Function Position Emergency Air Storage VES-MT-13    No        Yes          -      -/-      -      -      -        -
Tank 13 Emergency Air Storage VES-MT-14    No        Yes          -      -/-      -      -      -        -
Tank 14 Emergency Air Storage VES-MT-15    No        Yes          -      -/-      -      -      -        -
Tank 15 Emergency Air Storage VES-MT-16    No        Yes          -      -/-      -      -      -        -
Tank 16 Emergency Air Storage VES-MT-17    No        Yes          -      -/-      -      -      -        -
Tank 17 Emergency Air Storage VES-MT-18    No        Yes          -      -/-      -      -      -        -
Tank 18 Emergency Air Storage VES-MT-19    No        Yes          -      -/-      -      -      -        -
Tank 19 Emergency Air Storage VES-MT-20    No        Yes          -      -/-      -      -      -        -
Tank 20 Emergency Air Storage VES-MT-21    No        Yes          -      -/-      -      -      -        -
Tank 21 Emergency Air Storage VES-MT-22    No        Yes          -      -/-      -      -      -        -
Tank 22 Emergency Air Storage VES-MT-23    No        Yes          -      -/-      -      -      -        -
Tank 23 Emergency Air Storage VES-MT-24    No        Yes          -      -/-      -      -      -        -
Tank 24 C-176
 
Table 2.2.5-1 Class 1E/                          Loss of ASME                Remotely Qual. for Safety-                  Motive Code      Seismic    Operated  Harsh    Related Control  Active  Power Equipment Name          Tag No. Section III  Cat. I      Valve  Envir. Display  PMS    Function Position Emergency Air Storage    VES-MT-25      No        Yes          -      -/-      -      -        -      -
Tank 25 Emergency Air Storage    VES-MT-26      No        Yes          -      -/-      -      -        -      -
Tank 26 Emergency Air Storage    VES-MT-27      No        Yes          -      -/-      -      -        -      -
Tank 27 Emergency Air Storage    VES-MT-28      No        Yes          -      -/-      -      -        -      -
Tank 28 Emergency Air Storage    VES-MT-29      No        Yes          -      -/-      -      -        -      -
Tank 29 Emergency Air Storage    VES-MT-30      No        Yes          -      -/-      -      -        -      -
Tank 30 Emergency Air Storage    VES-MT-31      No        Yes          -      -/-      -      -        -      -
Tank 31 Emergency Air Storage    VES-MT-32      No        Yes          -      -/-      -      -        -      -
Tank 32 Air Delivery Alternate  VES-PL-V001    Yes        Yes          No      -/-      No      -    Transfer    -
Isolation Valve                                                                                  Open Eductor Flow Path        VES-PL-V045    Yes        Yes          No      -/-      No      -    Transfer    -
Isolation Valve                                                                                  Close Eductor Bypass Isolation VES-PL-V046    Yes        Yes          No      -/-      No      -    Transfer    -
Valve                                                                                            Open Pressure Regulating      VES-PL-V002A    Yes        Yes          No      -/-      No      -    Throttle    -
Valve A                                                                                          Flow C-177
 
Table 2.2.5-1 Class 1E/                          Loss of ASME                Remotely Qual. for Safety-                  Motive Code      Seismic    Operated  Harsh    Related Control  Active  Power Equipment Name        Tag No. Section III  Cat. I      Valve  Envir. Display  PMS    Function Position Pressure Regulating    VES-PL-V002B    Yes        Yes          No      -/-      No      -    Throttle    -
Valve B                                                                                        Flow MCR Air Delivery      VES-PL-V005A    Yes        Yes        Yes    Yes/No    No      Yes  Transfer  Open Isolation Valve A                                                                              Open MCR Air Delivery      VES-PL-V005B    Yes        Yes        Yes    Yes/No    No      Yes  Transfer  Open Isolation Valve B                                                                              Open Temporary Instrument  VES-PL-V018    Yes        Yes          No      -/-      No      No    Transfer    -
Isolation Valve A                                                                              Open Temporary Instrument  VES-PL-V019    Yes        Yes          No      -/-      No      No    Transfer    -
Isolation Valve B                                                                              Open MCR Pressure Relief    VES-PL-V022A    Yes        Yes        Yes    Yes/No    No      Yes  Transfer  Open Isolation Valve A                                                                              Open MCR Pressure Relief    VES-PL-V022B    Yes        Yes        Yes    Yes/No    No      Yes  Transfer  Open Isolation Valve B                                                                              Open Air Tank Safety Relief VES-PL-V040A    Yes        Yes          No      -/-      No      -    Transfer    -
Valve A                                                                                        Open Air Tank Safety Relief VES-PL-V040B    Yes        Yes          No      -/-      No      -    Transfer    -
Valve B                                                                                        Open Air Tank Safety Relief VES-PL-V040C    Yes        Yes          No      -/-      No      -    Transfer    -
Valve C                                                                                        Open Air Tank Safety Relief VES-PL-V040D    Yes        Yes          No      -/-      No      -    Transfer    -
Valve D                                                                                        Open Main Air Flow Path    VES-PL-V044    Yes        Yes          No      -/-      No      -    Transfer    -
Isolation Valve                                                                                Close C-178
 
Table 2.2.5-1 Class 1E/                          Loss of ASME                Remotely Qual. for Safety-                  Motive Code      Seismic    Operated  Harsh    Related Control  Active  Power Equipment Name          Tag No. Section III  Cat. I      Valve  Envir. Display  PMS    Function Position MCR Air Filtration Line  VES-PY-N01    Yes        Yes          -      -        -      -      -        -
Eductor MCR Air Filtration Line  VES-MY-F01      No        Yes          -      -        -      -      -        -
Charcoal Filter MCR Air Filtration Line  VES-MY-F02      No        Yes          -      -        -      -      -        -
HEPA Filter MCR Air Filtration Line  VES-MY-F03      No        Yes          -      -        -      -      -        -
Postfilter MCR Filter Shielding      12401-NS-01    No        Yes          -      -        -      -      -        -
MCR Gravity Relief      VES-MD-D001A      No        Yes          -      -        -      -      -        -
Dampers MCR Gravity Relief      VES-MD-D001B      No        Yes          -      -        -      -      -        -
Dampers MCR Air Filtration Line  VES-MD-D002      No        Yes          -      -        -      -      -        -
Supply Damper MCR Air Filtration Line  VES-MD-D003      No        Yes          -      -        -      -      -        -
Supply Damper MCR Air Filtration Line  VES-MY-Y01      No        Yes          -      -        -      -      -        -
Silencer MCR Air Filtration Line  VES-MY-Y02      No        Yes          -      -        -      -      -        -
Silencer MCR Air Delivery Line      VES-003A      No        Yes          -    Yes/No    Yes      -      -        -
Flow Sensor C-179
 
Table 2.2.5-1 Class 1E/                          Loss of ASME                Remotely Qual. for Safety-                  Motive Code      Seismic    Operated  Harsh    Related Control  Active  Power Equipment Name                Tag No. Section III  Cat. I      Valve  Envir. Display  PMS    Function Position MCR Air Delivery Line            VES-003B      No        Yes          -    Yes/No    Yes      -      -        -
Flow Sensor MCR Differential                VES-004A        No        Yes          -    Yes/No    Yes      -      -        -
Pressure Sensor A MCR Differential                VES-004B      No        Yes          -    Yes/No    Yes      -      -        -
Pressure Sensor B Note: Dash (-) indicates not applicable.
C-180
 
Table 2.2.5-2 ASME Code                  Functional Capability Line Name                Line Number                  Section III                    Required MCR Relief Line                  VES-PL-022A                      Yes                            Yes MCR Relief Line                  VES-PL-022B                      Yes                            Yes Table 2.2.5-3 Equipment                                  Tag No.                            Display Air Storage Tank Pressure                                VES-001A                              Yes Air Storage Tank Pressure                                VES-001B                              Yes Table 2.2.5-4 Heat Load 0 to 24 Hours          Heat Load 24 to 72 Hours Room Name              Room Numbers                      (Btu/s)                        (Btu/s)
MCR Envelope                      12401              26.1 (hour 0 through 0.5)                  2.9 15.6 (hour 0.5 through 3.5) 5.8 (hour 3.5 through 24)
I&C Rooms                      12301, 12305                      8.8                              0 I&C Rooms                      12302, 12304                      13.0                            4.2 dc Equipment Rooms              12201, 12205            3.7 (hour 0 through 1)                    0 2.4 (hour 2 through 24) dc Equipment Rooms              12203, 12207            5.8 (hour 0 through 1)                    2.0 4.5 (hour 2 through 24)
Table 2.2.5-5 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No.              Design Commitment                    Inspections, Tests, Analyses          Acceptance Criteria 252  2.2.05.01    1. The functional arrangement of the        Inspection of the as-built system  The as-built VES conforms VES is as described in the Design          will be performed.                  with the functional Description of this Section 2.2.5.                                              arrangement described in the Design Description of this Section 2.2.5.
C-181
 
Table 2.2.5-5 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No.              Design Commitment                    Inspections, Tests, Analyses          Acceptance Criteria 253  2.2.05.02a  2.a) The components identified in            Inspection will be conducted of  The ASME Code Section III Table 2.2.5-1 as ASME Code Section            the as-built components as        design reports exist for the as-III are designed and constructed in          documented in the ASME design    built components identified in accordance with ASME Code Section            reports.                          Table 2.2.5-1 as ASME Code III requirements.                                                              Section III.
254  2.2.05.02b  2.b) The piping identified in                Inspection will be conducted of  The ASME Code Section III Table 2.2.5-2 as ASME Code Section            the as-built piping as            design reports exist for the as-III is designed and constructed in            documented in the ASME design    built piping identified in accordance with ASME Code Section            reports.                          Table 2.2.5-2 as ASME Code III requirements.                                                              Section III.
255  2.2.05.03a  3.a) Pressure boundary welds in              Inspection of the as-built        A report exists and concludes components identified in Table 2.2.5-1        pressure boundary welds will be  that the ASME Code Section as ASME Code Section III meet ASME            performed in accordance with      III requirements are met for Code Section III requirements.                the ASME Code Section III.        non-destructive examination of pressure boundary welds.
256  2.2.05.03b  3.b) Pressure boundary welds in piping        Inspection of the as-built        A report exists and concludes identified in Table 2.2.5-2 as ASME          pressure boundary welds will be  that the ASME Code Section Code Section III meet ASME Code              performed in accordance with      III requirements are met for Section III requirements.                    the ASME Code Section III.        non-destructive examination of pressure boundary welds.
257  2.2.05.04a  4.a) The components identified in            A hydrostatic test will be        A report exists and concludes Table 2.2.5-1 as ASME Code Section            performed on the components      that the results of the III retain their pressure boundary            required by the ASME Code        hydrostatic test of the integrity at their design pressure.          Section III to be hydrostatically components identified in tested.                          Table 2.2.5-1 as ASME Code Section III conform with the requirements of the ASME Code Section III.
258  2.2.05.04b  4.b) The piping identified in                A hydrostatic test will be        A report exists and concludes Table 2.2.5-2 as ASME Code Section            performed on the piping required  that the results of the III retains its pressure boundary            by the ASME Code Section III to  hydrostatic test of the piping integrity at its design pressure.            be hydrostatically tested.        identified in Table 2.2.5-2 as ASME Code Section III conform with the requirements of the ASME Code Section III.
259  2.2.05.05a.i 5.a) The seismic Category I equipment        i) Inspection will be performed  i) The seismic Category I identified in Table 2.2.5-1 can withstand    to verify that the seismic        equipment identified in seismic design basis loads without loss      Category I equipment and valves  Table 2.2.5-1 is located on the of safety function.                          identified in Table 2.2.5-1 are  Nuclear Island.
located on the Nuclear Island.
C-182
 
Table 2.2.5-5 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No.                Design Commitment                    Inspections, Tests, Analyses        Acceptance Criteria 260  2.2.05.05a.ii  5.a) The seismic Category I equipment        ii) Type tests, analyses, or a    ii) A report exists and identified in Table 2.2.5-1 can withstand    combination of type tests and      concludes that the seismic seismic design basis loads without loss      analyses of seismic Category I    Category I equipment can of safety function.                          equipment will be performed.      withstand seismic design basis loads without loss of safety function.
261  2.2.05.05a.iii 5.a) The seismic Category I equipment        iii) Inspection will be performed  iii) A report exists and identified in Table 2.2.5-1 can withstand    for the existence of a report      concludes that the as-built seismic design basis loads without loss      verifying that the as-built        equipment including of safety function.                          equipment including anchorage      anchorage is seismically is seismically bounded by the      bounded by the tested or tested or analyzed conditions. analyzed conditions.
262  2.2.05.05b    5.b) Each of the lines identified in        Inspection will be performed for  A report exists and concludes Table 2.2.5-2 for which functional          the existence of a report          that each of the as-built lines capability is required is designed to        verifying that the as-built piping identified in Table 2.2.5-2 for withstand combined normal and seismic        meets the requirements for        which functional capability is design basis loads without a loss of its    functional capability.            required meets the functional capability.                                                          requirements for functional capability.
263    2.2.05.06a  6.a) The Class 1E components                Testing will be performed by      A simulated test signal exists identified in Table 2.2.5-1 are powered      providing a simulated test signal  at the Class 1E equipment from their respective Class 1E division. in each Class 1E division.        identified in Table 2.2.5-1 when the assigned Class 1E division is provided the test signal.
264  2.2.05.06b    6.b) Separation is provided between          See ITAAC Table 3.3-6,            See ITAAC Table 3.3-6, VES Class 1E divisions, and between          item 7.d.                          item 7.d.
Class 1E divisions and non-Class 1E cable.
265  2.2.05.07a.i  7.a) The VES provides a 72-hour              i) Testing will be performed to    i) The air flow rate from the supply of breathable quality air for the    confirm that the required amount  VES is at least 60 scfm and occupants of the MCR.                        of air flow is delivered to the    not more than 70 scfm.
MCR.
266  2.2.05.07a.ii  7.a) The VES provides a 72-hour              ii) Analysis of storage capacity  ii) The calculated storage supply of breathable quality air for the    will be performed based on        capacity is greater than or occupants of the MCR.                        manufacturers data.                equal to 327,574 scf.
267  2.2.05.07a.iii 7.a) The VES provides a 72-hour              iii) MCR air samples will be      iii) The MCR air is of supply of breathable quality air for the    taken during VES testing and      breathable quality.
occupants of the MCR.                        analyzed for quality.
C-183
 
Table 2.2.5-5 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No.              Design Commitment                    Inspections, Tests, Analyses          Acceptance Criteria 268  2.2.05.07b.i  7.b) The VES maintains the MCR              i) Testing will be performed      i) The MCR pressure pressure boundary at a positive pressure    with VES flow rate between 60      boundary is pressurized to with respect to the surrounding areas.      and 70 scfm to confirm that the    greater than or equal to 1/8-in.
MCR is capable of maintaining      water gauge with respect to the required pressurization of the the surrounding area.
pressure boundary.
269  2.2.05.07b.ii 7.b) The VES maintains the MCR              ii) Air leakage into the MCR      ii) Air leakage into the MCR pressure boundary at a positive pressure    will be measured during VES        is less than or equal to 10 cfm.
with respect to the surrounding areas.      testing using a tracer gas.
270  2.2.05.07c  7.c) The heat loads within the MCR,          An analysis will be performed to  A report exists and concludes the I&C equipment rooms, and the            determine that the heat loads      that: the heat loads within Class 1E dc equipment rooms are              from as-built equipment within    rooms identified in Table within design basis assumptions to limit    the rooms identified in            2.2.5-4 are less than or equal the heatup of the rooms identified in        Table 2.2.5-4 are less than or    to the specified values or that Table 2.2.5-4.                              equal to the design basis          an analysis report exists that assumptions.                      concludes:
                                                                                                  - The temperature and humidity in the MCR remain within limits for reliable human performance for the 72-hour period.
                                                                                                  - The maximum temperature for the 72-hour period for the I&C rooms is less than or equal to 120&deg;F.
                                                                                                  - The maximum temperature for the 72-hour period for the Class 1E dc equipment rooms is less than or equal to 120&deg;F.
271  2.2.05.07d  7d) The system provides a passive            Testing will be performed to      The air flow rate at the outlet recirculation flow of MCR air to            confirm that the required amount  of the MCR passive filtration maintain main control room dose rates        of air flow circulates through the system is at least 600 cfm below an acceptable level during VES        MCR passive filtration system,    greater than the flow operation.                                                                      measured by VES-003A/B.
272  C.2.2.05.07e  7e) Shielding below the VES Filter is        Inspection will be performed for  A report exists and concludes capable of providing attenuation that is    the existence of a report          that the as-built shielding sufficient to ensure main control room      verifying that the as-built        identified in Table 2.2.5-1 doses are below an acceptable level          shielding meets the requirements  meets the functional during VES operation.                        for functional capability.        requirements and exists below the filtration unit, and within its vertical projection.
C-184
 
Table 2.2.5-5 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No.                Design Commitment                    Inspections, Tests, Analyses            Acceptance Criteria 273    2.2.05.08    8. Safety-related displays identified in    Inspection will be performed for    Safety-related displays Table 2.2.5-1 can be retrieved in the        retrievability of the safety-        identified in Table 2.2.5-1 can MCR.                                        related displays in the MCR.        be retrieved in the MCR.
274  2.2.05.09a    9.a) Controls exist in the MCR to cause      Stroke testing will be performed    Controls in the MCR operate remotely operated valves identified in      on remotely operated valves          to cause remotely operated Table 2.2.5-1 to perform their active        identified in Table 2.2.5-1 using    valves identified in Table functions.                                  the controls in the MCR.            2.2.5-1 to perform their active safety functions.
275  2.2.05.09b    9.b) The valves identified in                Testing will be performed on        The remotely operated valves Table 2.2.5-1 as having PMS control          remotely operated valves listed      identified in Table 2.2.5-1 as perform their active safety function        in Table 2.2.5-1 using real or      having PMS control perform after receiving a signal from the PMS.      simulated signals into the PMS.      the active safety function identified in the table after receiving a signal from the PMS.
276    2.2.05.10    10. After loss of motive power, the          Testing of the remotely operated    After loss of motive power, remotely operated valves identified in      valves will be performed under      each remotely operated valve Table 2.2.5-1 assume the indicated loss      the conditions of loss of motive    identified in Table 2.2.5-1 of motive power position.                    power.                              assumes the indicated loss of motive power position.
277    2.2.05.11    11. Displays of the parameters              Inspection will be performed for    The displays identified in identified in Table 2.2.5-3 can be          retrievability of the parameters    Table 2.2.5-3 can be retrieved retrieved in the MCR.                        in the MCR.                          in the MCR.
278    2.2.05.12    12. The background noise level in the        The as-built VES will be            The background noise level in MCR does not exceed 65 dB(A) at the          operated, and background noise      the MCR does not exceed 65 operator workstations when VES is            levels in the MRC will be            dB(A) at the operator work operating.                                  measured at the operator work        stations when the VES is stations with the plant not          operating.
operating.
Table 2.2.5-6 Component Name                              Tag Number                      Component Location Emergency Air Storage Tank 01                    VES-MT-01                        Auxiliary Building Emergency Air Storage Tank 02                    VES-MT-02                        Auxiliary Building Emergency Air Storage Tank 03                    VES-MT-03                        Auxiliary Building Emergency Air Storage Tank 04                    VES-MT-04                        Auxiliary Building Emergency Air Storage Tank 05                    VES-MT-05                        Auxiliary Building Emergency Air Storage Tank 06                    VES-MT-06                        Auxiliary Building C-185
 
Table 2.2.5-6 Component Name              Tag Number Component Location Emergency Air Storage Tank 07    VES-MT-07  Auxiliary Building Emergency Air Storage Tank 08    VES-MT-08  Auxiliary Building Emergency Air Storage Tank 09    VES-MT-09  Auxiliary Building Emergency Air Storage Tank 10    VES-MT-10  Auxiliary Building Emergency Air Storage Tank 11    VES-MT-11  Auxiliary Building Emergency Air Storage Tank 12    VES-MT-12  Auxiliary Building Emergency Air Storage Tank 13    VES-MT-13  Auxiliary Building Emergency Air Storage Tank 14    VES-MT-14  Auxiliary Building Emergency Air Storage Tank 15    VES-MT-15  Auxiliary Building Emergency Air Storage Tank 16    VES-MT-16  Auxiliary Building Emergency Air Storage Tank 17    VES-MT-17  Auxiliary Building Emergency Air Storage Tank 18    VES-MT-18  Auxiliary Building Emergency Air Storage Tank 19    VES-MT-19  Auxiliary Building Emergency Air Storage Tank 20    VES-MT-20  Auxiliary Building Emergency Air Storage Tank 21    VES-MT-21  Auxiliary Building Emergency Air Storage Tank 22    VES-MT-22  Auxiliary Building Emergency Air Storage Tank 23    VES-MT-23  Auxiliary Building Emergency Air Storage Tank 24    VES-MT-24  Auxiliary Building Emergency Air Storage Tank 25    VES-MT-25  Auxiliary Building Emergency Air Storage Tank 26    VES-MT-26  Auxiliary Building Emergency Air Storage Tank 27    VES-MT-27  Auxiliary Building Emergency Air Storage Tank 28    VES-MT-28  Auxiliary Building Emergency Air Storage Tank 29    VES-MT-29  Auxiliary Building Emergency Air Storage Tank 30    VES-MT-30  Auxiliary Building Emergency Air Storage Tank 31    VES-MT-31  Auxiliary Building Emergency Air Storage Tank 32    VES-MT-32  Auxiliary Building C-186
 
Figure 2.2.5-1 Main Control Room Emergency Habitability System C-187
 
2.3            Auxiliary Systems 2.3.1          Component Cooling Water System Design Description The component cooling water system (CCS) removes heat from various plant components and transfers this heat to the service water system (SWS) during normal modes of plant operation including power generation, shutdown and refueling. The CCS has two pumps and two heat exchangers.
The CCS is as shown in Figure 2.3.1-1 and the CCS component locations are as shown in Table 2.3.1-3.
: 1. The functional arrangement of the CCS is as described in the Design Description of this Section 2.3.1.
: 2. The CCS preserves containment integrity by isolation of the CCS lines penetrating the containment.
: 3. The CCS provides the nonsafety-related functions of transferring heat from the normal residual heat removal system (RNS) during shutdown and the spent fuel pool cooling system during all modes of operation to the SWS.
: 4. Controls exist in the main control room (MCR) to cause the pumps identified in Table 2.3.1-1 to perform the listed functions.
: 5. Displays of the parameters identified in Table 2.3.1-1 can be retrieved in the MCR.
C-188
 
Table 2.3.1-1 Equipment Name                  Tag No.        Display    Control Function CCS Pump A                              CCS-MP-01A          Yes          Start (Run Status)
CCS Pump B                              CCS-MP-01B          Yes          Start (Run Status)
CCS Discharge Header Flow Sensor          CCS-101          Yes              -
CCS to Normal Residual Heat Removal        CCS-301          Yes              -
System Heat Exchanger (RNS HX) A Flow Sensor CCS to RNS HX B Flow Sensor                CCS-302          Yes              -
CCS to Spent Fuel Pool Cooling System      CCS-341          Yes              -
(SFS) HX A Flow Sensor CCS to SFS HX B Flow Sensor                CCS-342          Yes              -
CCS Surge Tank Level Sensor A              CCS-130          Yes              -
CCS Surge Tank Level Sensor B              CCS-131          Yes              -
CCS Heat Exchanger Inlet Temperature      CCS-121          Yes              -
Sensor CCS Heat Exchanger Outlet Temperature      CCS-122          Yes              -
Sensor CCS Flow to Reactor Coolant Pump        CCS-PL-V256A        Yes              -
(RCP) 1A Valve (Position Indicator)
CCS Flow to RCP 1B Valve (Position      CCS-PL-V256B        Yes              -
Indicator)
CCS Flow to RCP 2A Valve (Position      CCS-PL-V256C        Yes              -
Indicator)
CCS Flow to RCP 2B Valve (Position      CCS-PL-V256D        Yes              -
Indicator)
Note: Dash (-) indicates not applicable.
C-189
 
Table 2.3.1-2 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No.              Design Commitment                    Inspections, Tests, Analyses            Acceptance Criteria 279    2.3.01.01  1. The functional arrangement of the        Inspection of the as-built system    The as-built CCS conforms CCS is as described in the Design            will be performed.                    with the functional Description of this Section 2.3.1.                                                arrangement described in the Design Description of this Section 2.3.1.
280    2.3.01.02  2. The CCS preserves containment            See ITAAC Table 2.2.1-3,              See ITAAC Table 2.2.1-3, integrity by isolation of the CCS lines      items 1 and 7.                        items 1 and 7.
penetrating the containment.
281  2.3.01.03.i  3. The CCS provides the nonsafety-          i) Inspection will be performed      i) A report exists and related functions of transferring heat      for the existence of a report that    concludes that the UA of each from the RNS during shutdown and the        determines the heat transfer          CCS heat exchanger is greater spent fuel pool cooling system during        capability of the CCS heat            than or equal to 14.0 million all modes of operation to the SWS.          exchangers.                          Btu/hr-&deg;F.
282  2.3.01.03.ii 3. The CCS provides the nonsafety-          ii) Testing will be performed to      ii) Each pump of the CCS can related functions of transferring heat      confirm that the CCS can              provide at least 2685 gpm of from the RNS during shutdown and the        provide cooling water to the          cooling water to one RNS HX spent fuel pool cooling system during        RNS HXs while providing              and at least 1200 gpm of all modes of operation to the SWS.          cooling water to the SFS HXs.        cooling water to one SFS HX while providing at least 4415 gpm to other users of cooling water.
283    2.3.01.04  4. Controls exist in the MCR to cause        Testing will be performed to          Controls in the MCR operate the pumps identified in Table 2.3.1-1 to    actuate the pumps identified in      to cause pumps listed in perform the listed functions.                Table 2.3.1-1 using controls in      Table 2.3.1-1 to perform the the MCR.                              listed functions.
284    2.3.01.05  5. Displays of the parameters identified    Inspection will be performed for      Displays identified in Table in Table 2.3.1-1 can be retrieved in the    retrievability of the parameters      2.3.1-1 can be retrieved in the MCR.                                        in the MCR.                          MCR.
Table 2.3.1-3 Component Name                                      Tag No.                Component Location CCS Pump A                                                      CCS-MP-01A                  Turbine Building CCS Pump B                                                        CCS-MP-01B                  Turbine Building CCS Heat Exchanger A                                            CCS-ME-01A                  Turbine Building CCS Heat Exchanger B                                            CCS-ME-01B                  Turbine Building C-190
 
Figure 2.3.1-1 Component Cooling Water System C-191
 
2.3.2          Chemical and Volume Control System Design Description The chemical and volume control system (CVS) provides reactor coolant system (RCS) purification, RCS inventory control and makeup, chemical shim and chemical control, oxygen control, and auxiliary pressurizer spray. The CVS performs these functions during normal modes of operation including power generation and shutdown.
The CVS is as shown in Figure 2.3.2-1 and the component locations of the CVS are as shown in Table 2.3.2-5.
: 1. The functional arrangement of the CVS is as described in the Design Description of this Section 2.3.2.
: 2. a) The components identified in Table 2.3.2-1 as ASME Code Section III are designed and constructed in accordance with ASME Code Section III requirements.
b) The piping identified in Table 2.3.2-2 as ASME Code Section III is designed and constructed in accordance with ASME Code Section III requirements.
: 3. a) Pressure boundary welds in components identified in Table 2.3.2-1 as ASME Code Section III meet ASME Code Section III requirements.
b) Pressure boundary welds in piping identified in Table 2.3.2-2 as ASME Code Section III meet ASME Code Section III requirements.
: 4. a) The components identified in Table 2.3.2-1 as ASME Code Section III retain their pressure boundary integrity at their design pressure.
b) The piping identified in Table 2.3.2-2 as ASME Code Section III retains its pressure boundary integrity at its design pressure.
: 5. The seismic Category I equipment identified in Table 2.3.2-1 can withstand seismic design basis loads without loss of safety function.
: 6. a) The Class 1E equipment identified in Table 2.3.2-1 as being qualified for a harsh environment can withstand the environmental conditions that would exist before, during, and following a design basis accident without loss of safety function for the time required to perform the safety function.
b) The Class 1E components identified in Table 2.3.2-1 are powered from their respective Class 1E division.
c) Separation is provided between CVS Class 1E divisions, and between Class 1E divisions and non-Class 1E cable.
: 7. The CVS provides the following safety-related functions:
a) The CVS preserves containment integrity by isolation of the CVS lines penetrating the containment.
C-192
 
b) The CVS provides termination of an inadvertent RCS boron dilution by isolating demineralized water from the RCS.
c) The CVS provides isolation of makeup to the RCS.
: 8. The CVS provides the following nonsafety-related functions:
a) The CVS provides makeup water to the RCS.
b) The CVS provides the pressurizer auxiliary spray.
: 9. Safety-related displays in Table 2.3.2-1 can be retrieved in the main control room (MCR).
: 10. a) Controls exist in the MCR to cause the remotely operated valves identified in Table 2.3.2-1 to perform active functions.
b) The valves identified in Table 2.3.2-1 as having protection and safety monitoring system (PMS) control perform an active safety function after receiving a signal from the PMS.
: 11. a) The motor-operated and check valves identified in Table 2.3.2-1 perform an active safety-related function to change position as indicated in the table.
b) After a loss of motive power, the remotely operated valves identified in Table 2.3.2-1 assume the indicated loss of motive power position.
: 12. a) Controls exist in the MCR to cause the pumps identified in Table 2.3.2-3 to perform the listed function.
b) The pumps identified in Table 2.3.2-3 start after receiving a signal from the PLS.
: 13. Displays of the parameters identified in Table 2.3.2-3 can be retrieved in the MCR.
: 14. The nonsafety-related piping located inside containment and designated as reactor coolant pressure boundary, as identified in Table 2.3.2-2 (pipe lines with "No" in the ASME Code column), has been designed to withstand a seismic design basis event and maintain structural integrity.
C-193
 
Table 2.3.2-1 Class 1E/                            Loss of ASME                  Remotely Qual. for  Safety-                  Motive Code      Seismic      Operated  Harsh    Related  Control  Active  Power Equipment Name          Tag No. Section III  Cat. I        Valve  Envir. Display    PMS    Function Position RCS Purification Motor-    CVS-PL-V001    Yes        Yes          Yes    Yes/Yes    Yes      Yes  Transfer  As Is operated Isolation Valve                                                            (Valve            Closed Position)
RCS Purification Motor-    CVS-PL-V002    Yes        Yes          Yes    Yes/Yes    Yes      Yes  Transfer  As Is operated Isolation Valve                                                            (Valve            Closed Position)
RCS Purification Motor-    CVS-PL-V003    Yes        Yes          Yes    Yes/Yes    Yes      Yes  Transfer  As Is operated Isolation Valve                                                            (Valve            Closed Position)
CVS Resin Flush Line        CVS-PL-V040    Yes        Yes            No      -/-        -        -        -        -
Containment Isolation Valve CVS Resin Flush Line        CVS-PL-V041    Yes        Yes            No      -/-        -        -        -        -
Containment Isolation Valve CVS Demineralizer Resin    CVS-PL-V042    Yes        Yes            No      -/-        -        -    Transfer    -
Flush Line Containment                                                                                Open/
Isolation Thermal Relief                                                                              Transfer Valve                                                                                                  Closed CVS Letdown Containment    CVS-PL-V045    Yes        Yes          Yes    Yes/Yes    Yes      Yes  Transfer  Closed Isolation Valve                                                                      (Valve            Closed Position)
CVS Letdown Containment    CVS-PL-V047    Yes        Yes          Yes    Yes/No    Yes      Yes  Transfer  Closed Isolation Valve                                                                      (Valve            Closed Position)
C-194
 
Table 2.3.2-1 Class 1E/                            Loss of ASME                  Remotely Qual. for  Safety-                  Motive Code      Seismic      Operated  Harsh    Related  Control  Active  Power Equipment Name          Tag No. Section III  Cat. I        Valve  Envir. Display    PMS    Function Position CVS Letdown Line            CVS-PL-V058    Yes        Yes            No      -/-        -        -    Transfer    -
Containment Isolation                                                                                  Open/
Thermal Relief Valve                                                                                  Transfer Closed CVS Purification Return Line CVS-PL-V080    Yes        Yes            No      -/-        -        -    Transfer    -
Pressure Boundary Check                                                                                Closed Valve CVS Purification Return Line CVS-PL-V081    Yes        Yes            No      -/-      No        -    Transfer    -
Pressure Boundary Isolation                                                                            Closed Check Valve CVS Purification Return Line CVS-PL-V082    Yes        Yes            No      -/-        -        -    Transfer    -
Pressure Boundary Check                                                                                Closed Valve CVS Auxiliary Pressurizer    CVS-PL-V084    Yes        Yes          Yes    Yes/Yes    Yes      Yes  Transfer  Closed Spray Line Pressure                                                                  (Valve            Closed Boundary Valve                                                                      Position)
CVS Auxiliary Pressurizer    CVS-PL-V085    Yes        Yes            No    Yes/Yes      -        -    Transfer    -
Spray Line Pressure                                                                                    Closed Boundary Check Valve CVS Makeup Line              CVS-PL-V090    Yes        Yes          Yes    Yes/No    Yes      Yes  Transfer  As Is Containment Isolation Motor-                                                          (Valve            Closed operated Valve                                                                      Position)
CVS Makeup Line              CVS-PL-V091    Yes        Yes          Yes    Yes/Yes    Yes      Yes  Transfer  As Is Containment Isolation Motor-                                                          (Valve            Closed operated Valve                                                                      Position)
C-195
 
Table 2.3.2-1 Class 1E/                            Loss of ASME                  Remotely Qual. for  Safety-                  Motive Code      Seismic      Operated  Harsh    Related  Control  Active  Power Equipment Name                Tag No. Section III  Cat. I        Valve  Envir. Display    PMS    Function Position CVS Hydrogen Addition Line      CVS-PL-V092    Yes        Yes          Yes    Yes/No    Yes      Yes  Transfer  Closed Containment Isolation Valve                                                              (Valve            Closed Position)
CVS Hydrogen Addition Line      CVS-PL-V094    Yes        Yes            No      -/-        -        -    Transfer    -
Containment Isolation Check                                                                                Closed Valve CVS Makeup Line                  CVS-PL-V100    Yes        Yes            No      -/-        -        -    Transfer    -
Containment Isolation                                                                                      Open/
Thermal Relief Valve                                                                                      Transfer Closed CVS Demineralized Water        CVS-PL-V136A    Yes        Yes          Yes    Yes/No    Yes      Yes  Transfer  Closed Isolation Valve                                                                          (Valve            Closed Position)
CVS Demineralized Water        CVS-PL-V136B    Yes        Yes          Yes    Yes/No    Yes      Yes  Transfer  Closed Isolation Valve                                                                          (Valve            Closed Position)
Note: Dash (-) indicates not applicable.
C-196
 
Table 2.3.2-2 Line Name                            Line Number ASME Code Section III CVS Purification Line                                    L001              Yes L040              Yes CVS Resin Flush Containment Penetration Line            L026              Yes CVS Purification Line Return                            L038              Yes CVS Pressurizer Auxiliary Spray Connection              L070              Yes L071              Yes CVS Letdown Containment Penetration Line                L051              Yes CVS Makeup Containment Penetration Line                  L053              Yes CVS Hydrogen Addition Containment Penetration            L061              Yes Line CVS Supply Line to Regenerative Heat Exchanger          L002              No CVS Return Line from Regenerative Heat                  L018              No Exchanger                                                L036              Yes L073              No CVS Line from Regenerative Heat Exchanger to            L003              No Letdown Heat Exchanger CVS Lines from Letdown Heat Exchanger to                L004              No Demin. Tanks                                            L005              No L072              No CVS Lines from Demin Tanks to RC Filters and            L006(1)          No Connected Lines                                          L007(1)          No L010(1)          No L011(1)          No L012              No L015(1)          No L016(1)          No L020              No L021              No L022              No L023(1)          No L024(1)          No L029              No L037              No CVS Lines from RC Filters to Regenerative Heat          L030              No Exchanger                                                L031              No L034              No L050              No CVS Resin Fill Lines to Demin. Tanks                    L008(1)          No L013(1)          No L025(1)          No C-197
 
Note:
: 1. Special seismic requirements include only the portion of piping normally exposed to RCS pressure. Piping beyond the first normally closed isolation valve is evaluated as seismic Category II piping extending to either an interface anchor, a rigid support following a six-way anchor, or the last seismic support of a rigidly supported region of the piping system as necessary to satisfy analysis requirements for piping connected to seismic Category I piping systems.
C-198
 
Table 2.3.2-3 Equipment                            Tag No.                Display        Control Function CVS Makeup Pump A                                  CVS-MP-01A                  Yes                Start (Run Status)
CVS Makeup Pump B                                  CVS-MP-01B                  Yes                Start (Run Status)
Purification Flow Sensor                              CVS-001                    Yes                  -
Purification Return Flow Sensor                      CVS-025                    Yes                  -
CVS Purification Return Line (Position              CVS-PL-V081                  Yes                  -
Indicator)
Auxiliary Spray Line Isolation Valve              CVS-PL-V084                  Yes                  -
(Position Indicator)
Boric Acid Storage Tank Level Sensor                  CVS-109                    Yes                  -
Boric Acid Flow Sensor                                CVS-115                    Yes                  -
Makeup Blend Valve (Position Indicator)            CVS-PL-V115                  Yes                  -
CVS Demineralized Water Isolation Valve            CVS-PL-136A                  Yes                  -
(Position Indicator)
CVS Demineralized Water Isolation Valve            CVS-PL-136B                  Yes                  -
(Position Indicator)
Makeup Pump Discharge Flow Sensor                    CVS-157                    Yes                  -
Makeup Flow Control Valve (Position                CVS-PL-V157                  Yes                  -
Indicator)
Note: Dash (-) indicates not applicable.
Table 2.3.2-4 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No.                Design Commitment                  Inspections, Tests, Analyses        Acceptance Criteria 285  2.3.02.01      1. The functional arrangement of the        Inspection of the as-built system The as-built CVS conforms CVS is as described in the Design          will be performed.                with the functional Description of this Section 2.3.2.                                            arrangement as described in the Design Description of this Section 2.3.2.
286  2.3.02.02a    2.a) The components identified in          Inspection will be conducted of  The ASME Code Section III Table 2.3.2-1 as ASME Code Section          the as-built components as        design reports exist for the as-III are designed and constructed in        documented in the ASME design    built components identified in accordance with ASME Code Section          reports.                          Table 2.3.2-1 as ASME Code III requirements.                                                            Section III.
C-199
 
Table 2.3.2-4 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No.                Design Commitment                    Inspections, Tests, Analyses          Acceptance Criteria 287  2.3.02.02b  2.b) The piping identified in                Inspection will be conducted of    The ASME Code Section III Table 2.3.2-2 as ASME Code Section            the as-built piping as            design reports exist for the as-III is designed and constructed in            documented in the ASME design      built piping identified in accordance with ASME Code Section            reports.                          Table 2.3.2-2 as ASME Code III requirements.                                                                Section III.
288  2.3.02.03a  3.a) Pressure boundary welds in              Inspection of the as-built        A report exists and concludes components identified in Table 2.3.2-1        pressure boundary welds will be    that the ASME Code Section as ASME Code Section III meet ASME            performed in accordance with      III requirements are met for Code Section III requirements.                the ASME Code Section III.        non-destructive examination of pressure boundary welds.
289  2.3.02.03b  3.b) Pressure boundary welds in piping        Inspection of the as-built        A report exists and concludes identified in Table 2.3.2-2 as ASME          pressure boundary welds will be    that the ASME Code Section Code Section III meet ASME Code              performed in accordance with      III requirements are met for Section III requirements.                    the ASME Code Section III.        non-destructive examination of pressure boundary welds.
290  2.3.02.04a  4.a) The components identified in            A hydrostatic test will be        A report exists and concludes Table 2.3.2-1 as ASME Code Section            performed on the components        that the results of the III retain their pressure boundary            required by the ASME Code          hydrostatic test of the integrity at their design pressure.          Section III to be hydrostatically  components identified in tested.                            Table 2.3.2-1 as ASME Code Section III conform with the requirements of the ASME Code Section III.
291  2.3.02.04b  4.b) The piping identified in                A hydrostatic test will be        A report exists and concludes Table 2.3.2-2 as ASME Code Section            performed on the piping required  that the results of the III retains its pressure boundary            by the ASME Code Section III to    hydrostatic test of the piping integrity at its design pressure.            be hydrostatically tested.        identified in Table 2.3.2-2 as ASME Code Section III conform with the requirements of the ASME Code Section III.
292  2.3.02.05.i  5. The seismic Category I equipment          i) Inspection will be performed    i) The seismic Category I identified in Table 2.3.2-1 can withstand    to verify that the seismic        equipment identified in seismic design basis loads without loss      Category I equipment identified    Table 2.3.2-1 is located on the of safety function.                          in Table 2.3.2-1 is located on the Nuclear Island.
Nuclear Island.
293  2.3.02.05.ii 5. The seismic Category I equipment          ii) Type tests, analyses, or a    ii) A report exists and identified in Table 2.3.2-1 can withstand    combination of type tests and      concludes that the seismic seismic design basis loads without loss      analyses of seismic Category I    Category I equipment can of safety function.                          equipment will be performed.      withstand seismic design basis dynamic loads without loss of safety function.
C-200
 
Table 2.3.2-4 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No.              Design Commitment                    Inspections, Tests, Analyses        Acceptance Criteria 294  2.3.02.05.iii 5. The seismic Category I equipment          iii) Inspection will be performed iii) A report exists and identified in Table 2.3.2-1 can withstand    for the existence of a report    concludes that the as-built seismic design basis loads without loss      verifying that the as-built      equipment including of safety function.                          equipment including anchorage    anchorage is seismically is seismically bounded by the    bounded by the tested or tested or analyzed conditions. analyzed conditions.
295  2.3.02.06a.i  6.a) The Class 1E equipment identified      i) Type tests, analyses, or a    i) A report exists and in Table 2.3.2-1 as being qualified for a    combination of type tests and    concludes that the Class 1E harsh environment can withstand the          analyses will be performed on    equipment identified in Table environmental conditions that would          Class 1E equipment located in a  2.3.2-1 as being qualified for a exist before, during, and following a        harsh environment.                harsh environment can design basis accident without loss of                                          withstand the environmental safety function for the time required to                                      conditions that would exist perform the safety function.                                                  before, during, and following a design basis accident without loss of safety function for the time required to perform the safety function.
296  2.3.02.06a.ii 6.a) The Class 1E equipment identified      ii) Inspection will be performed  ii) A report exists and in Table 2.3.2-1 as being qualified for a    of the as-built Class 1E          concludes that the as-built harsh environment can withstand the          equipment and the associated      Class 1E equipment and the environmental conditions that would          wiring, cables, and terminations  associated wiring, cables, and exist before, during, and following a        located in a harsh environment. terminations identified in design basis accident without loss of                                          Table 2.3.2-1 as being safety function for the time required to                                      qualified for a harsh perform the safety function.                                                  environment are bounded by type tests, analyses, or a combination of type tests and analyses.
297  2.3.02.06b  6.b) The Class 1E components                Testing will be performed on the  A simulated test signal exists identified in Table 2.3.2-1 are powered      CVS by providing a simulated      at the Class 1E equipment from their respective Class 1E division. test signal in each Class 1E      identified in Table 2.3.2-1 division.                        when the assigned Class 1E division is provided the test signal.
298  2.3.02.06c  6.c) Separation is provided between          See ITAAC Table 3.3-6,            See ITAAC Table 3.3-6, CVS Class 1E divisions, and between          item 7.d.                        item 7.d.
Class 1E divisions and non-Class 1E cable.
299  2.3.02.07a  7.a) The CVS preserves containment          See ITAAC Table 2.2.1-3,          See ITAAC Table 2.2.1-3, integrity by isolation of the CVS lines      item 7.                          item 7.
penetrating the containment.
C-201
 
Table 2.3.2-4 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No.                Design Commitment                    Inspections, Tests, Analyses        Acceptance Criteria 300  2.3.02.07b    7.b) The CVS provides termination of        See item 10b in this table.        See item 10b in this table.
an inadvertent RCS boron dilution by isolating demineralized water from the RCS.
301    2.3.02.07c  7.c) The CVS provides isolation of          See item 10b in this table.        See item 10b in this table.
makeup to the RCS.
302  2.3.02.08a.i  8.a) The CVS provides makeup water          i) Testing will be performed by    i) Each CVS makeup pump to the RCS.                                  aligning a flow path from each    provides a flow rate of greater CVS makeup pump, actuating        than or equal to 100 gpm.
makeup flow to the RCS at pressure greater than or equal to 2000 psia, and measuring the flow rate in the makeup pump discharge line with each pump suction aligned to the boric acid storage tank.
303  2.3.02.08a.ii  8.a) The CVS provides makeup water          ii) Inspection of the boric acid  ii) The volume in the boric to the RCS.                                  storage tank volume will be        acid storage tank is at least performed.                        70,000 gallons between the tank outlet connection and the tank overflow.
304  2.3.02.08a.iii 8.a) The CVS provides makeup water          iii) Testing will be performed to  iii) The total CVS makeup to the RCS.                                  measure the delivery rate from    flow to the RCS is less than or the DWS to the RCS. Both CVS      equal to 200 gpm.
makeup pumps will be operating and the RCS pressure will be below 6 psig.
305  2.3.02.08b    8.b) The CVS provides the pressurizer        Testing will be performed by      Each CVS makeup pump auxiliary spray.                            aligning a flow path from each    provides spray flow to the CVS makeup pump to the            pressurizer.
pressurizer auxiliary spray and measuring the flow rate in the makeup pump discharge line with each pump suction aligned to the boric acid storage tank and with RCS pressure greater than or equal to 2000 psia.
306    2.3.02.09    9. Safety-related displays identified in    Inspection will be performed for  Safety-related displays Table 2.3.2-1 can be retrieved in the        retrievability of the safety-      identified in Table 2.3.2-1 can MCR.                                        related displays in the MCR.      be retrieved in the MCR.
C-202
 
Table 2.3.2-4 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No.                Design Commitment                    Inspections, Tests, Analyses        Acceptance Criteria 307    2.3.02.10a  10.a) Controls exist in the MCR to          Stroke testing will be performed  Controls in the MCR operate cause the remotely operated valves          on the remotely operated valves    to cause the remotely operated identified in Table 2.3.2-1 to perform      identified in Table 2.3.2-1 using  valves identified in Table active functions.                          the controls in the MCR.          2.3.2-1 to perform active functions.
308  2.3.02.10b.i  10.b) The valves identified in              i) Testing will be performed      i) The valves identified in Table 2.3.2-1 as having PMS control        using real or simulated signals    Table 2.3.2-1 as having PMS perform an active safety function after    into the PMS.                      control perform the active receiving a signal from the PMS.                                              function identified in the table after receiving a signal from the PMS.
309  2.3.02.10b.ii  10.b) The valves identified in              ii) Testing will be performed to  ii) These valves close within Table 2.3.2-1 as having PMS control        demonstrate that the remotely      the following times after perform an active safety function after    operated CVS isolation valves      receipt of an actuation signal:
receiving a signal from the PMS.            CVS-V090, V091, V136A/B            V090, V091        < 30 sec close within the required          V136A/B            < 20 sec response time.
310  2.3.02.11a.i  11.a) The motor-operated and check          i) Tests or type tests of          i) A test report exists and valves identified in Table 2.3.2-1          motor-operated valves will be      concludes that each motor-perform an active safety-related            performed that demonstrate the    operated valve function to change position as indicated    capability of the valve to operate changes position as indicated in the table.                              under its design conditions.      in Table 2.3.2-1 under design conditions.
311  2.3.02.11a.ii  11.a) The motor-operated and check          ii) Inspection will be performed  ii) A report exists and valves identified in Table 2.3.2-1          for the existence of a report      concludes that the as-built perform an active safety-related            verifying that the as-built motor- motor-operated valves are function to change position as indicated    operated valves are bounded by    bounded by the tests or type in the table.                              the tested conditions.            tests.
312  2.3.02.11a.iii 11.a) The motor-operated and check          iii) Tests of the motor-operated  iii) Each motor-operated valves identified in Table 2.3.2-1          valves will be performed under    valve changes position as perform an active safety-related            pre-operational flow, differential indicated in Table 2.3.2-1 function to change position as indicated    pressure, and temperature          under pre-operational test in the table.                              conditions.                        conditions.
313  2.3.02.11a.iv  11.a) The motor-operated and check          iv) Exercise testing of the check  iv) Each check valve changes valves identified in Table 2.3.2-1          valves with active safety          position as indicated in perform an active safety-related            functions identified in            Table 2.3.2-1.
function to change position as indicated    Table 2.3.2-1 will be performed in the table.                              under pre-operational test pressure, temperature and fluid flow conditions.
C-203
 
Table 2.3.2-4 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No.            Design Commitment                    Inspections, Tests, Analyses          Acceptance Criteria 314  2.3.02.11b 11.b) After loss of motive power, the        Testing of the remotely operated  Upon loss of motive power, remotely operated valves identified in        valves will be performed under    each remotely operated valve Table 2.3.2-1 assume the indicated loss      the conditions of loss of motive  identified in Table 2.3.2-1 of motive power position.                    power.                            assumes the indicated loss of motive power position.
315  2.3.02.12a 12.a) Controls exist in the MCR to            Testing will be performed to      Controls in the MCR cause cause the pumps identified in                actuate the pumps identified in    pumps identified in Table 2.3.2-3 to perform the listed          Table 2.3.2-3 using controls in    Table 2.3.2-3 to perform the function.                                    the MCR.                          listed function.
316  2.3.02.12b 12.b) The pumps identified in Table          Testing will be performed to      The pumps identified in 2.3.2-3 start after receiving a signal        confirm starting of the pumps      Table 2.3.2-3 start after a from the PLS.                                identified in Table 2.3.2-3.      signal is generated by the PLS.
317    2.3.02.13 13. Displays of the parameters                Inspection will be performed for  Displays identified in Table identified in Table 2.3.2-3 can be            retrievability of the displays    2.3.2-3 can be retrieved in the retrieved in the MCR.                        identified in Table 2.3.2-3 in the MCR.
MCR.
318    2.3.02.14 14. The nonsafety-related piping              Inspection will be conducted of    The CVS Seismic Analysis located inside containment and                the as-built components as        Reports exist for the non-designated as reactor coolant pressure        documented in the CVS Seismic      safety related piping located boundary, as identified in Table 2.3.2-2,    Analysis Report.                  inside containment and has been designed to withstand a                                                designated as reactor coolant seismic design basis event and maintain                                          pressure boundary as structural integrity.                                                            identified in Table 2.3.2-2.
C-204
 
Table 2.3.2-5 Component Name        Tag No. Component Location CVS Makeup Pump A          CVS-MP-01A    Auxiliary Building CVS Makeup Pump B          CVS-MP-01B    Auxiliary Building Boric Acid Storage Tank      CVS-MT-01            Yard Regenerative Heat Exchanger  CVS-ME-01      Containment Letdown Heat Exchanger      CVS-ME-02      Containment Mixed Bed Demineralizer A  CVS-MV-01A      Containment Mixed Bed Demineralizer B  CVS-MV-01B      Containment Cation Bed Demineralizer    CVS-MV-02        Containment Reactor Coolant Filter A    CVS-MV-03A      Containment Reactor Coolant Filter B    CVS-MV-03B      Containment C-205
 
Figure 2.3.2-1 Chemical and Volume Control System C-206
 
2.3.3              Standby Diesel Fuel Oil System Design Description The standby diesel fuel oil system (DOS) supplies diesel fuel oil for the onsite standby power system. The diesel fuel oil is supplied by two above-ground fuel oil storage tanks. The DOS also provides fuel oil for the ancillary diesel generators. A single fuel oil storage tank services both ancillary diesel generators.
The DOS is as shown in Figure 2.3.3-1 and the component locations of the DOS are as shown in Table 2.3.3-3.
: 1. The functional arrangement of the DOS is as described in the Design Description of this Section 2.3.3.
: 2. The ancillary diesel generator fuel tank can withstand a seismic event.
: 3. The DOS provides the following nonsafety-related functions:
a) Each fuel oil storage tank provides for at least 7 days of continuous operation of the associated standby diesel generator.
b) Each fuel oil day tank provides for at least four hours of continuous operation of the associated standby diesel engine generator.
c) The fuel oil flow rate to the day tank of each standby diesel generator provides for continuous operation of the associated diesel generator.
d) The ancillary diesel generator fuel tank is sized to supply power to long-term safety-related post-accident monitoring loads and control room lighting through a regulating transformer and one PCS recirculation pump for a period of 4 days.
: 4. Controls exist in the main control room (MCR) to cause the components identified in Table 2.3.3-1 to perform the listed function.
: 5. Displays of the parameters identified in Table 2.3.3-1 can be retrieved in the MCR.
Table 2.3.3-1 Equipment Name                      Tag No.          Display      Control Function Diesel Fuel Oil Pump 1A (Motor)                  DOS-MP-01A            Yes              Start (Run Status)
Diesel Fuel Oil Pump 1B (Motor)                  DOS-MP-01B            Yes              Start (Run Status)
Diesel Generator Fuel Oil Day Tank A Level          DOS-016A            Yes                -
Diesel Generator Fuel Oil Day Tank B Level          DOS-016B            Yes                -
Note: Dash (-) indicates not applicable.
C-207
 
Table 2.3.3-2 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No.            Design Commitment                    Inspections, Tests, Analyses          Acceptance Criteria 319    2.3.03.01 1. The functional arrangement of the        Inspection of the as-built system  The as-built DOS conforms DOS is as described in the Design            will be performed.                with the functional Description of this Section 2.3.3.                                              arrangement described in the Design Description of this Section 2.3.3.
320    2.3.03.02 2. The ancillary diesel generator fuel      Inspection will be performed for  A report exists and concludes tank can withstand a seismic event.          the existence of a report          that the as-built ancillary verifying that the as-built        diesel generator fuel tank and ancillary diesel generator fuel    its anchorage are designed tank and its anchorage are        using seismic Category II designed using seismic            methods and criteria.
Category II methods and criteria.
321  2.3.03.03a 3.a) Each fuel oil storage tank provides    Inspection of each fuel oil        The volume of each fuel oil for at least 7 days of continuous            storage tank will be performed. storage tank available to the operation of the associated standby                                            standby diesel generator is diesel generator.                                                              greater than or equal to 55,000 gallons.
322  2.3.03.03b 3.b) Each fuel oil storage day tank          Inspection of the fuel oil day    The volume of each fuel oil provides for at least 4 hours of            tank will be performed.            day tank is greater than or operation of the associated standby                                            equal to 1300 gallons.
diesel generator.
323  2.3.03.03c 3.c) The fuel oil flow rate to the day      Testing will be performed to      The flow rate delivered to tank of each standby diesel generator        determine the flow rate.          each day tank is 8 gpm or provides for continuous operation of the                                        greater.
associated diesel generator.
324  2.3.03.03d 3.d) The ancillary diesel generator fuel    Inspection of the ancillary diesel The volume of the ancillary tank is sized to supply power to long-      generator fuel tank will be        diesel generator fuel tank is term safety-related post accident            performed.                        greater than or equal to monitoring loads and control room                                              650 gallons.
lighting through a regulating transformer and one PCS recirculation pump for four days.
325    2.3.03.04 4. Controls exist in the MCR to cause        Testing will be performed on the  Controls in the MCR operate the components identified in Table          components in Table 2.3.3-1        to cause the components listed 2.3.3-1 to perform the listed function.      using controls in the MCR.        in Table 2.3.3-1 to perform the listed functions.
326    2.3.03.05 5. Displays of the parameters identified    Inspection will be performed for  The displays identified in in Table 2.3.3-1 can be retrieved in the    retrievability of parameters in    Table 2.3.3-1 can be retrieved MCR.                                        the MCR.                          in the MCR.
C-208
 
Table 2.3.3-3 Component Name                  Tag No. Component Location Diesel Oil Transfer Package A            DOS-MS-01A        Yard Diesel Oil Transfer Package B            DOS-MS-01B        Yard Fuel Oil Storage Tank A                  DOS-MT-01A        Yard Fuel Oil Storage Tank B                  DOS-MT-01B        Yard Diesel Generator A Fuel Oil Day Tank      DOS-MT-02A    Diesel Building Diesel Generator B Fuel Oil Day Tank      DOS-MT-02B    Diesel Building Ancillary Diesel Fuel Oil Storage Tank    DOS-MT-03    Annex Building C-209
 
Figure 2.3.3-1 Standby Diesel Fuel Oil System C-210
 
2.3.4            Fire Protection System Design Description The fire protection system (FPS) detects and suppresses fires in the plant. The FPS consists of water distribution systems, automatic and manual suppression systems, a fire detection and alarm system, and portable fire extinguishers. The FPS provides fire protection for the nuclear island, the annex building, the turbine building, the radwaste building and the diesel generator building.
The FPS is as shown in Figure 2.3.4-1 and the component locations of the FPS are as shown in Table 2.3.4-3.
: 1. The functional arrangement of the FPS is as described in the Design Description of this Section 2.3.4.
: 2. The FPS piping identified in Table 2.3.4-4 remains functional following a safe shutdown earthquake.
: 3. The FPS provides the safety-related function of preserving containment integrity by isolation of the FPS line penetrating the containment.
: 4. The FPS provides for manual fire fighting capability in plant areas containing safety-related equipment.
: 5. Displays of the parameters identified in Table 2.3.4-1 can be retrieved in the main control room (MCR).
: 6. The FPS provides nonsafety-related containment spray for severe accident management.
: 7. The FPS provides two fire water storage tanks, each capable of holding at least 300,000 gallons of water.
: 8. Two FPS fire pumps provide at least 2000 gpm each at a total head of at least 300 ft.
: 9. The fuel tank for the diesel-driven fire pump is capable of holding at least 240 gallons.
: 10. Individual fire detectors provide fire detection capability and can be used to initiate fire alarms in areas containing safety-related equipment.
: 11. The FPS seismic standpipe subsystem can be supplied from the FPS fire main by opening the normally closed cross-connect valve to the FPS plant fire main.
Table 2.3.4-1 Equipment Name                Tag No.                  Display        Control Function Motor-driven Fire Pump            FPS-MP-01A              Yes (Run Status)          Start Diesel-driven Fire Pump          FPS-MP-01B              Yes (Run Status)          Start Jockey Pump                        FPS-MP-02              Yes (Run Status)          Start C-211
 
Table 2.3.4-2 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No.              Design Commitment                    Inspections, Tests, Analyses        Acceptance Criteria 327    2.3.04.01  1. The functional arrangement of the        Inspection of the as-built system The as-built FPS conforms FPS is as described in the Design            will be performed.                with the functional Description of this Section 2.3.4.                                            arrangement described in the Design Description of this Section 2.3.4.
328  2.3.04.02.i  2. The FPS piping identified in              i) Inspection will be performed  i) The piping identified in Table 2.3.4-4 remains functional            to verify that the piping        Table 2.3.4-4 is located on following a safe shutdown earthquake.        identified in Table 2.3.4-4 is    the Nuclear Island.
located on the Nuclear Island.
329  2.3.04.02.ii 2. The FPS piping identified in              ii) A reconciliation analysis    ii) The as-built piping stress Table 2.3.4-4 remains functional            using the as-designed and as-    report exists and concludes following a safe shutdown earthquake.        built piping information will be  that the piping remains performed, or an analysis of the  functional following a safe as-built piping will be          shutdown earthquake.
performed.
330    2.3.04.03  3. The FPS provides the safety-related      See ITAAC Table 2.2.1-3,          See ITAAC Table 2.2.1-3, function of preserving containment          items 1 and 7.                    items 1 and 7.
integrity by isolation of the FPS line penetrating the containment.
331  2.3.04.04.i  4. The FPS provides for manual fire          i) Inspection of the passive      i) The volume of the PCS fighting capability in plant areas          containment cooling system        tank above the standpipe containing safety-related equipment.        (PCS) storage tank will be        feeding the FPS and below the performed.                        overflow is at least 18,000 gal.
332  2.3.04.04.ii 4. The FPS provides for manual fire          ii) Testing will be performed by  ii) Water is simultaneously fighting capability in plant areas          measuring the water flow rate as  discharged from each of the containing safety-related equipment.        it is simultaneously discharged  two highest fire-hose stations from the two highest fire-hose    in plant areas containing stations and when the water for  safety-related equipment at the fire is supplied from the PCS not less than 75 gpm.
storage tank.
333    2.3.04.05  5. Displays of the parameters identified    Inspection will be performed for  The displays identified in in Table 2.3.4-1 can be retrieved in the    retrievability of the parameters  Table 2.3.4-1 can be retrieved MCR.                                        in the MCR.                      in the MCR.
334    2.3.04.06  6. The FPS provides nonsafety-related        Inspection of the containment    The FPS has spray headers containment spray for severe accident        spray headers will be performed. and nozzles as follows:
management.                                                                    At least 44 nozzles at plant elevation of at least 260 feet, and 24 nozzles at plant elevation of at least 275 feet.
335    2.3.04.07  7. The FPS provides two fire water          Inspection of each fire water    The volume of each fire water storage tanks, each capable of holding      storage tank will be performed. storage tank supplying the at least 300,000 gallons of water.                                            FPS is at least 300,000 gallons.
C-212
 
Table 2.3.4-2 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No.                Design Commitment                    Inspections, Tests, Analyses              Acceptance Criteria 336  2.3.04.08    8. Two FPS fire pumps provide at least        Testing and/or analysis of each      The tests and/or analysis 2000 gpm each at a total head of at least    fire pump will be performed.          concludes that each fire pump 300 ft.                                                                            provides a flow rate of at least 2000 gpm at a total head of at least 300 ft.
337  2.3.04.09    9. The fuel tank for the diesel-driven        Inspection of the diesel-driven      The volume of the diesel fire pump is capable of holding at least      fire pump fuel tank will be          driven fire pump fuel tank is 240 gallons.                                  performed.                            at least 240 gallons.
338  2.3.04.10    10. Individual fire detectors provide        Testing will be performed on the      The tested individual fire fire detection capability and can be used    as-built individual fire detectors    detectors respond to simulated to initiate fire alarms in areas containing  in the fire areas identified in      fire conditions.
safety-related equipment.                    subsection 3.3, Table 3.3-3.
(Individual fire detectors will be tested using simulated fire conditions.)
339  2.3.04.11    11. The FPS seismic standpipe                Inspection for the existence of a    Valve FPS-PL-V101 exists subsystem can be supplied from the            cross-connect valve from the          and can connect the FPS FPS fire main by opening the normally        FPS seismic standpipe                seismic standpipe subsystem closed cross-connect valve to the FPS        subsystem to FPS plant fire main      to the FPS plant fire main.
plant fire main.                              will be performed.
Table 2.3.4-3 Component Name                                  Tag No.                        Location Motor-driven Fire Pump                                      FPS-MP-01A                      Turbine Building Diesel-driven Fire Pump                                      FPS-MP-01B                            Yard Jockey Pump                                                  FPS-MP-02                      Turbine Building Primary Fire Water Tank                                      FPS-MT-01A                            Yard Secondary Fire Water/Clearwell Storage Tank                  FPS-MT-01B                            Yard Fire Pump Diesel Fuel Day Tank                                FPS-MT-02                            Yard C-213
 
Table 2.3.4-4 FPS Piping Which Must Remain Functional Following a Safe Shutdown Earthquake L049                    L114                    L142                    L188 L090A                    L115                    L143                    L189 L090B                    L116                    L144                    L190 L091A                    L117                    L145                    L191 L091B                    L118                    L146                    L192 L091C                    L119                    L147                    L193 L092A                    L120                    L148                    L194 L092B                    L121                    L149                    L195 L092C                    L122                    L150                    L196 L093                    L123                    L151                    L197 L094                    L124                    L152                    L198 L095                    L125                    L153                    L199 L096                    L126                    L154                    L301 L102                    L127                    L155                    L701 L103                    L128                    L156                    L702 L105                    L129                    L159                    L703 L106                    L130                    L180                    L704 L107                    L131                    L181                    L705 L108                    L132                    L182                    L706 L109                  L133A                    L183                    L707 L110                  L133B                    L184                    L708 L111                  L133C                    L185                    L709 L112                    L140                    L186 L113                    L141                    L187 C-214
 
Figure 2.3.4-1 (Sheet 1 of 2)
Fire Protection System C-215
 
Figure 2.3.4-1 (Sheet 2 of 2)
Fire Protection System C-216
 
2.3.5          Mechanical Handling System Design Description The mechanical handling system (MHS) provides for lifting heavy loads. The MHS equipment can be operated during shutdown and refueling.
The component locations of the MHS are as shown in Table 2.3.5-3.
: 1. The functional arrangement of the MHS is as described in the Design Description of this Section 2.3.5.
: 2. The seismic Category I equipment identified in Table 2.3.5-1 can withstand seismic design basis loads without loss of safety function.
: 3. The MHS components listed below are single failure proof:
a) Polar crane b) Cask handling crane c) Equipment hatch hoist d) Maintenance hatch hoist
: 4. The cask handling crane cannot move over the spent fuel pool.
Table 2.3.5-1 Class 1E/
Seismic      Qual. for Equipment Name            Tag No.        Cat. I    Harsh Envir.      Safety Function Containment Polar Crane    MHS-MH-01          Yes        No/No      Avoid uncontrolled lowering of heavy load.
Cask Handling Crane        MHS-MH-02          Yes        No/No      Avoid uncontrolled lowering of heavy load.
Equipment Hatch Hoist      MHS-MH-05          Yes        No/No      Avoid uncontrolled lowering of heavy load.
Maintenance Hatch Hoist    MHS-MH-06          Yes        No/No      Avoid uncontrolled lowering of heavy load.
C-217
 
Table 2.3.5-2 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No.                Design Commitment                    Inspections, Tests, Analyses          Acceptance Criteria 340    2.3.05.01    1. The functional arrangement of the        Inspection of the as-built system  The as-built MHS conforms MHS is as described in the Design          will be performed.                with the functional Description of this Section 2.3.5.                                            arrangement as described in the Design Description of this Section 2.3.5.
341  2.3.05.02.i  2. The seismic Category I equipment        i) Inspection will be performed    i) The seismic Category I identified in Table 2.3.5-1 can withstand  to verify that the seismic        equipment identified in seismic design basis loads without loss    Category I equipment identified    Table 2.3.5-1 is located on the of safety function.                        in Table 2.3.5-1 is located on the Nuclear Island.
Nuclear Island.
342  2.3.05.02.ii  2. The seismic Category I equipment        ii) Type tests, analyses, or a    ii) A report exists and identified in Table 2.3.5-1 can            combination of type tests and      concludes that the seismic withstand seismic design basis loads        analyses of seismic Category I    Category I equipment can without loss of safety function.            equipment will be performed.      withstand seismic design basis loads without loss of safety function.
343  2.3.05.02.iii  2. The seismic Category I equipment        iii) Inspection will be performed  iii) A report exists and identified in Table 2.3.5-1 can            for the existence of a report      concludes that the as-built withstand seismic design basis loads        verifying that the as-built        equipment including without loss of safety function.            equipment including anchorage      anchorage is seismically is seismically bounded by the      bounded by the tested or tested or analyzed conditions. analyzed conditions.
344  2.3.05.03a.i  3.a) The polar crane is single failure      i) Validation of double design    i) A report exists and proof.                                      factors is provided for hooks      concludes that the polar crane where used as load bearing        is single failure proof. A components. Validation of          certificate of conformance redundant factors is provided for  from the vendor exists and load bearing components such      concludes that the polar crane as:                                is single failure proof.
* Hoisting ropes
* Sheaves
* Equalizer assembly
* Holding brakes 345  2.3.05.03a.ii  3.a) The polar crane is single failure      ii) Testing of the polar crane is  ii) The polar crane shall be proof.                                      performed.                        static-load tested to 125% of the rated load.
346  2.3.05.03a.iii 3.a) The polar crane is single failure      iii) Testing of the polar crane is iii) The polar crane shall lift a proof.                                      performed.                        test load that is 100% of the rated load. Then it shall lower, stop, and hold the test load.
C-218
 
Table 2.3.5-2 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No.                Design Commitment                    Inspections, Tests, Analyses        Acceptance Criteria 347  2.3.05.03b.i  3.b) The cask handling crane is single      i) Validation of double design    i) A report exists and failure proof.                              factors is provided for hooks    concludes that the cask where used as load bearing        handling crane is single failure components. Validation of        proof. A certificate of redundant factors is provided for conformance from the vendor load bearing components such      exists and concludes that the as:                              cask handling crane is single
* Hoisting ropes              failure proof.
* Sheaves
* Equalizer assembly
* Holding brakes 348  2.3.05.03b.ii  3.b) The cask handling crane is single      ii) Testing of the cask handling  ii) The cask handling crane failure proof.                              crane is performed.              shall be static load tested to 125% of the rated load.
349  2.3.05.03b.iii 3.b) The cask handling crane is single      iii) Testing of the cask handling iii) The cask handling crane failure proof.                              crane is performed.              shall lift a test load that is 100% of the rated load. Then it shall lower, stop, and hold the test load.
350  2.3.05.03c.i  3.c) The equipment hatch hoist is            i) Validation of double design    i) A report exists and single failure proof.                        factors is provided for hooks    concludes that the equipment where used as load bearing        hatch hoist is single failure components. Validation of        proof. A certificate of redundant factors is provided for conformance from the vendor load bearing components such      exists and concludes that the as:                              equipment hatch hoist is
* Hoisting ropes              single failure proof.
* Sheaves
* Equalizer assembly
* Holding brakes 351  2.3.05.03c.ii  3.c) The equipment hatch hoist is            ii) Testing of the equipment      ii) The equipment hatch hoist single failure proof.                        hatch hoist is performed.        holding mechanism shall stop and hold the hatch.
352  2.3.05.03d.i  3.d) The maintenance hatch hoist is          i) Validation of double design    i) A report exists and single failure proof.                        factors is provided for hooks    concludes that the where used as load bearing        maintenance hatch hoist is components. Validation of        single failure proof. A redundant factors is provided for certificate of conformance load bearing components such      from the vendor exists and as:                              concludes that the
* Hoisting ropes              maintenance hatch hoist is
* Sheaves                      single failure proof.
* Equalizer assembly
* Holding brakes C-219
 
Table 2.3.5-2 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No.                Design Commitment                    Inspections, Tests, Analyses          Acceptance Criteria 353  2.3.05.03d.ii  3.d) The maintenance hatch hoist is          ii) Testing of the maintenance      ii) The maintenance hatch single failure proof.                        hatch hoist is performed.          hoist holding mechanism shall stop and hold the hatch.
354    2.3.05.04    4. The cask handling crane cannot            Testing of the cask handling        The cask handling crane does move over the spent fuel pool.              crane is performed.                not move over the spent fuel pool.
Table 2.3.5-3 Component Name                            Tag No.                      Component Location Containment Polar Crane                          MHS-MH-01                            Containment Cask Handling Crane                              MHS-MH-02                        Auxiliary Building Equipment Hatch Hoist                            MHS-MH-05                            Containment Maintenance Hatch Hoist                          MHS-MH-06                            Containment C-220
 
2.3.6          Normal Residual Heat Removal System Design Description The normal residual heat removal system (RNS) removes heat from the core and reactor coolant system (RCS) and provides RCS low temperature over-pressure (LTOP) protection at reduced RCS pressure and temperature conditions after shutdown. The RNS also provides a means for cooling the in-containment refueling water storage tank (IRWST) during normal plant operation.
The RNS is as shown in Figure 2.3.6-1 and the RNS component locations are as shown in Table 2.3.6-5.
: 1. The functional arrangement of the RNS is as described in the Design Description of this Section 2.3.6.
: 2. a) The components identified in Table 2.3.6-1 as ASME Code Section III are designed and constructed in accordance with ASME Code Section III requirements.
b) The piping identified in Table 2.3.6-2 as ASME Code Section III is designed and constructed in accordance with ASME Code Section III requirements.
: 3. a) Pressure boundary welds in components identified in Table 2.3.6-1 as ASME Code Section III meet ASME Code Section III requirements.
b) Pressure boundary welds in piping identified in Table 2.3.6-2 as ASME Code Section III meet ASME Code Section III requirements.
: 4. a) The components identified in Table 2.3.6-1 as ASME Code Section III retain their pressure boundary integrity at their design pressure.
b) The piping identified in Table 2.3.6-2 as ASME Code Section III retains its pressure boundary integrity at its design pressure.
: 5. a) The seismic Category I equipment identified in Table 2.3.6-1 can withstand seismic design basis loads without loss of safety function.
b) Each of the lines identified in Table 2.3.6-2 for which functional capability is required is designed to withstand combined normal and seismic design basis loads without a loss of its functional capability.
: 6. Each of the as-built lines identified in Table 2.3.6-2 as designed for leak before break (LBB) meets the LBB criteria, or an evaluation is performed of the protection from the dynamic effects of a rupture of the line.
: 7. a) The Class 1E equipment identified in Table 2.3.6-1 as being qualified for a harsh environment can withstand the environmental conditions that would exist before, during, and following a design basis accident without loss of safety function for the time required to perform the safety function.
b) The Class 1E components identified in Table 2.3.6-1 are powered from their respective Class 1E division.
C-221
 
c) Separation is provided between RNS Class 1E divisions, and between Class 1E divisions and non-Class 1E cable.
: 8. The RNS provides the following safety-related functions:
a) The RNS preserves containment integrity by isolation of the RNS lines penetrating the containment.
b) The RNS provides a flow path for long-term, post-accident makeup to the RCS.
: 9. The RNS provides the following nonsafety-related functions:
a) The RNS provides low temperature overpressure protection (LTOP) for the RCS during shutdown operations.
b) The RNS provides heat removal from the reactor coolant during shutdown operations.
c) The RNS provides low pressure makeup flow from the SFS cask loading pit to the RCS for scenarios following actuation of the automatic depressurization system (ADS).
d) The RNS provides heat removal from the in-containment refueling water storage tank.
: 10. Safety-related displays identified in Table 2.3.6-1 can be retrieved in the main control room (MCR).
: 11. a) Controls exist in the MCR to cause those remotely operated valves identified in Table 2.3.6-1 to perform active functions.
b) The valves identified in Table 2.3.6-1 as having protection and safety monitoring system (PMS) control perform active safety functions after receiving a signal from the PMS.
: 12. a) The motor-operated and check valves identified in Table 2.3.6-1 perform an active safety-related function to change position as indicated in the table.
b) After loss of motive power, the remotely operated valves identified in Table 2.3.6-1 assume the indicated loss of motive power position.
: 13. Controls exist in the MCR to cause the pumps identified in Table 2.3.6-3 to perform the listed function.
: 14. Displays of the RNS parameters identified in Table 2.3.6-3 can be retrieved in the MCR.
C-222
 
Table 2.3.6-1 Class 1E
                                                                            / Qual.                            Loss of ASME                Remotely    for    Safety-                  Motive Code      Seismic Operated Harsh      Related  Control  Active  Power Equipment Name              Tag No. Section III Cat. I      Valve  Envir. Display    PMS    Function Position RNS Pump A (Pressure            RNS-MP-01A    Yes        Yes          -      -/-      -        -      No        -
Boundary)
RNS Pump B (Pressure            RNS-MP-01B    Yes        Yes          -      -/-      -        -      No        -
Boundary)
RNS Heat Exchanger A (Tube      RNS-ME-01A    Yes        Yes          -      -/-      -        -        -      -
Side)
RNS Heat Exchanger B (Tube      RNS-ME-01B    Yes        Yes          -      -/-      -        -        -      -
Side)
RCS Inner Hot Leg Suction      RNS-PL-V001A    Yes        Yes        Yes  Yes/Yes    Yes      Yes  Transfer  As Is Motor-operated Isolation Valve                                                      (Valve            Closed Position)
RCS Inner Hot Leg Suction      RNS-PL-V001B    Yes        Yes        Yes  Yes/Yes    Yes      Yes  Transfer  As Is Motor-operated Isolation Valve                                                      (Valve            Closed Position)
RCS Outer Hot Leg Suction      RNS-PL-V002A    Yes        Yes        Yes  Yes/Yes    Yes      Yes  Transfer  As Is Motor-operated Isolation Valve                                                      (Valve            Closed Position)
RCS Outer Hot Leg Suction      RNS-PL-V002B    Yes        Yes        Yes  Yes/Yes    Yes      Yes  Transfer  As Is Motor-operated Isolation Valve                                                      (Valve            Closed Position)
RCS Pressure Boundary          RNS-PL-V003A    Yes        Yes        No      -/-    No        -    Transfer    -
Thermal Relief Check Valve                                                                            Open/
Transfer Closed C-223
 
Table 2.3.6-1 Class 1E
                                                                          / Qual.                            Loss of ASME                Remotely    for    Safety-                  Motive Code      Seismic Operated Harsh      Related  Control  Active  Power Equipment Name          Tag No. Section III Cat. I      Valve  Envir. Display    PMS    Function Position RCS Pressure Boundary        RNS-PL-V003B    Yes        Yes        No      -/-    No        -    Transfer    -
Thermal Relief Check Valve                                                                          Open/
Transfer Closed RNS Discharge Motor-operated  RNS-PL-V011    Yes        Yes        Yes  Yes/No    Yes      Yes  Transfer  As Is Containment Isolation Valve                                                        (Valve            Closed Position)
RNS Discharge Containment    RNS-PL-V012    Yes        Yes        No      -/-    No      No    Transfer    -
Isolation Test Connection                                                                            Open RNS Discharge Header          RNS-PL-V013    Yes        Yes        No      -/-    No        -    Transfer    -
Containment Isolation Check                                                                          Open/
Valve                                                                                              Transfer Closed RNS Discharge RCS Pressure  RNS-PL-V015A    Yes        Yes        No      -/-    No        -    Transfer    -
Boundary Check Valve                                                                                Open/
Transfer Closed RNS Discharge RCS Pressure  RNS-PL-V015B    Yes        Yes        No      -/-    No        -    Transfer    -
Boundary Check Valve                                                                                Open/
Transfer Closed RNS Discharge RCS Pressure  RNS-PL-V017A    Yes        Yes        No      -/-    No        -    Transfer    -
Boundary Check Valve                                                                                Open/
Transfer Closed C-224
 
Table 2.3.6-1 Class 1E
                                                                            / Qual.                            Loss of ASME                Remotely    for    Safety-                  Motive Code      Seismic Operated Harsh      Related  Control  Active  Power Equipment Name            Tag No. Section III Cat. I      Valve  Envir. Display    PMS    Function Position RNS Discharge RCS Pressure    RNS-PL-V017B    Yes        Yes        No      -/-    No        -    Transfer    -
Boundary Check Valve                                                                                  Open/
Transfer Closed RNS Hot Leg Suction Pressure    RNS-PL-V021    Yes        Yes        No      -/-    No        -    Transfer    -
Relief Valve                                                                                          Open/
Transfer Closed RNS Suction Header              RNS-PL-V022    Yes        Yes        Yes  Yes/No    Yes      Yes  Transfer  As Is Motor-operated Containment                                                          (Valve            Closed Isolation Valve                                                                    Position)
RNS Suction from IRWST          RNS-PL-V023    Yes        Yes        Yes  Yes/Yes    Yes      Yes  Transfer  As Is Motor-operated Isolation Valve                                                      (Valve            Closed Position)
RNS Discharge to IRWST          RNS-PL-V024    Yes        Yes        Yes      -/-    No      No      No      As Is Motor-operated Isolation Valve RNS Discharge Header Relief    RNS-PL-V045    Yes        Yes        No      -/-    No        -    Transfer    -
Valve                                                                                                  Open/
Transfer Closed RNS Suction from Cask Loading  RNS-PL-V055    Yes        Yes        Yes  No/No      No      No      No      As Is Pit Motor-operated Isolation Valve RNS Suction from Cask Loading  RNS-PL-V056    Yes        Yes        No      -/-    No        -      No        -
Pit Check Valve C-225
 
Table 2.3.6-1 Class 1E
                                                                                      / Qual.                                  Loss of ASME                Remotely      for    Safety-                        Motive Code      Seismic Operated Harsh        Related    Control    Active      Power Equipment Name                  Tag No. Section III Cat. I      Valve      Envir. Display      PMS    Function    Position RNS Pump Miniflow                  RNS-PL-V057A      Yes        Yes        Yes      No/No      No        No      No        Open Air-Operated Isolation Valve RNS Pump Miniflow                  RNS-PL-V057B      Yes        Yes        Yes      No/No      No        No      No        Open Air-Operated Isolation Valve RNS Return from Chemical and        RNS-PL-V061      Yes        Yes        Yes      Yes/No    Yes        Yes    Transfer    Closed Volume Control System (CVS)                                                                    (Valve              Closed Containment Isolation Valve                                                                    Position)
Note: Dash (-) indicates not applicable.
Table 2.3.6-2 ASME Code        Leak Before    Functional Capability Line Name                            Line No.            Section III        Break            Required RNS Suction Lines, from the RCS Hot Leg Connection          RNS-L001                  Yes              Yes                No to the RCS Side of Valves RNS PL-V001A and                RNS-L002A RNS-PL-V001B                                              RNS-L002B RNS Suction Lines, from the RCS Pressure Boundary          RNS-L004A                  Yes              No                Yes Valves, RNS-PL-V001A and RNS-PL-V001B, to the              RNS-L004B                                                      Yes RNS pumps                                                  RNS-L005                                                      Yes RNS-L006                                                      No RNS-L007A                                                      No RNS-L007B                                                      No RNS-L009A                                                      No RNS-L009B                                                      No RNS Suction Line from CVS                                  RNS-L061                  Yes              No                No RNS Suction Line from IRWST                                RNS-L029                  Yes              No                No C-226
 
Table 2.3.6-2 ASME Code    Leak Before Functional Capability Line Name                      Line No.      Section III  Break          Required RNS Suction Line LTOP Relief                        RNS-L040          Yes          No              Yes RNS Discharge Lines, from the RNS Pumps to the RNS RNS-L011A          Yes          No              Yes Heat Exchangers RNS-ME-01A and RNS-ME-01B          RNS-L011B RNS Discharge Lines, from RNS Heat Exchanger      RNS-L012A          Yes          No              Yes RNS-ME-01A to Containment Isolation Valve          RNS-L014 RNS-PL-V011 RNS Discharge Line, from RNS Heat Exchanger        RNS-L012B          Yes          No              Yes RNS-ME-01B to Common Discharge Header RNS-DBC-L014 RNS Discharge Lines, Containment Isolation Valve    RNS-L016          Yes          No              Yes RNS-PL-V011 to Containment Isolation Valve RNS-PL-V013 RNS Suction Line from Cask Loading Pit              RNS-L065          Yes          No              No RNS Discharge Lines, from Containment Isolation    RNS-L017          Yes          No              Yes Valve RNS-PL-V013 to RCS Pressure Boundary        RNS-L018A Isolation Valves RNS-PL-V015A and RNS-PL-V015B    RNS-L018B RNS Discharge Lines, from Direct Vessel Injection  RNS-L020          Yes          No              No (DVI) Line RNS-BBC-L018A to Passive Core Cooling System (PXS) IRWST Return Isolation Valve RNS-PL-V024 RNS Discharge Lines, from RCS Pressure Boundary    RNS-L019A          Yes          No              Yes Isolation Valves RNS-PL-V015A and RNS-PL-V015B    RNS-L019B to Reactor Vessel DVI Nozzles RNS Heat Exchanger Bypass                          RNS-L008A          Yes          No              No RNS-L008B RNS Suction from Spent Fuel Pool                    RNS-L052          Yes          No              No C-227
 
Table 2.3.6-2 ASME Code    Leak Before Functional Capability Line Name      Line No.      Section III  Break          Required RNS Pump Miniflow Return          RNS-L030A          Yes          No              No RNS-L030B RNS Discharge to Spent Fuel Pool  RNS-L051          Yes          No              No RNS Discharge to CVS Purification  RNS-L021          Yes          No              No C-228
 
Table 2.3.6-3 Equipment Name                        Tag No.              Display                Control Function RNS Pump 1A (Motor)                          RNS-MP-01A                Yes                      Start (Run Status)
RNS Pump 1B (Motor)                          RNS-MP-01B                Yes                      Start (Run Status)
RNS Flow Sensor                                RNS-01A                  Yes                          -
RNS Flow Sensor                                RNS-01B                  Yes                          -
RNS Suction from Cask Loading                RNS-PL-V055                Yes                          -
Pit Isolation Valve (Position Indicator)
RNS Pump Miniflow Isolation                RNS-PL-V057A                Yes                          -
Valve (Position Indicator)
RNS Pump Miniflow Isolation                RNS-PL-V057B                Yes                          -
Valve (Position Indicator)
Note: Dash (-) indicates not applicable.
Table 2.3.6-4 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No.                  Design Commitment                  Inspections, Tests, Analyses            Acceptance Criteria 355    2.3.06.01      1. The functional arrangement of the        Inspection of the as-built system    The as-built RNS conforms RNS is as described in the Design            will be performed.                  with the functional Description of this Section 2.3.6.                                                arrangement described in the Design Description of this Section 2.3.6.
356  2.3.06.02a      2.a) The components identified in            Inspection will be conducted of      The ASME Code Section III Table 2.3.6-1 as ASME Code Section          the as-built components as          design reports exist for the as-III are designed and constructed in          documented in the ASME design        built components identified in accordance with ASME Code                    reports.                            Table 2.3.6-1 as ASME Code Section III requirements.                                                        Section III.
357  2.3.06.02b      2.b) The piping identified in                Inspection will be conducted of      The ASME Code Section III Table 2.3.6-2 as ASME Code Section          the as-built piping as              design reports exist for the as-III is designed and constructed in          documented in the ASME design        built piping identified in accordance with ASME Code                    reports.                            Table 2.3.6-2 as ASME Code Section III requirements.                                                        Section III.
358  2.3.06.03a      3.a) Pressure boundary welds in              Inspection of the as-built          A report exists and concludes components identified in Table 2.3.6-1      pressure boundary welds will be      that the ASME Code Section as ASME Code Section III meet ASME          performed in accordance with        III requirements are met for Code Section III requirements.              the ASME Code Section III.          non-destructive examination of pressure boundary welds.
C-229
 
Table 2.3.6-4 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No.                Design Commitment                      Inspections, Tests, Analyses          Acceptance Criteria 359  2.3.06.03b    3.b) Pressure boundary welds in piping        Inspection of the as-built        A report exists and concludes identified in Table 2.3.6-2 as ASME          pressure boundary welds will be    that the ASME Code Section Code Section III meet ASME Code              performed in accordance with      III requirements are met for Section III requirements.                    the ASME Code Section III.        non-destructive examination of pressure boundary welds.
360    2.3.06.04a  4.a) The components identified in            A hydrostatic test will be        A report exists and concludes Table 2.3.6-1 as ASME Code                    performed on the components        that the results of the Section III retain their pressure            required by the ASME Code          hydrostatic test of the boundary integrity at their design            Section III to be hydrostatically  components identified in pressure.                                    tested.                            Table 2.3.6-1 as ASME Code Section III conform with the requirements of the ASME Code Section III.
361  2.3.06.04b    4.b) The piping identified in                A hydrostatic test will be        A report exists and concludes Table 2.3.6-2 as ASME Code                    performed on the piping required  that the results of the Section III retains its pressure boundary    by the ASME Code Section III to    hydrostatic test of the piping integrity at its design pressure.            be hydrostatically tested.        identified in Table 2.3.6-2 as ASME Code Section III conform with the requirements of the ASME Code Section III.
362  2.3.06.05a.i  5.a) The seismic Category I equipment        i) Inspection will be performed    i) The seismic Category I identified in Table 2.3.6-1 can withstand    to verify that the seismic        equipment identified in seismic design basis loads without loss      Category I equipment identified    Table 2.3.6-1 is located on the of safety function.                          in Table 2.3.6-1 is located on the Nuclear Island.
Nuclear Island.
363  2.3.06.05a.ii  5.a) The seismic Category I equipment        ii) Type tests, analyses, or a    ii) A report exists and identified in Table 2.3.6-1 can withstand    combination of type tests and      concludes that the seismic seismic design basis loads without loss      analyses of seismic Category I    Category I equipment can of safety function.                          equipment will be performed.      withstand seismic design basis loads without loss of safety function.
364  2.3.06.05a.iii 5.a) The seismic Category I equipment        iii) Inspection will be performed  iii) A report exists and identified in Table 2.3.6-1 can withstand    for the existence of a report      concludes that the as-built seismic design basis loads without loss      verifying that the as-built        equipment including of safety function.                          equipment including anchorage      anchorage is seismically is seismically bounded by the      bounded by the tested or tested or analyzed conditions. analyzed conditions.
C-230
 
Table 2.3.6-4 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No.              Design Commitment                    Inspections, Tests, Analyses        Acceptance Criteria 365  2.3.06.05b  5.b) Each of the lines identified in        Inspection will be performed for  A report exists and concludes Table 2.3.6-2 for which functional          the existence of a report          that each of the as-built lines capability is required is designed to        verifying that the as-built piping identified in Table 2.3.6-2 for withstand combined normal and seismic        meets the requirements for        which functional capability is design basis loads without a loss of its    functional capability.            required meets the functional capability.                                                          requirements for functional capability.
366    2.3.06.06  6. Each of the as-built lines identified    Inspection will be performed for  An LBB evaluation report in Table 2.3.6-2 as designed for LBB        the existence of an LBB            exists and concludes that the meets the LBB criteria, or an evaluation    evaluation report or an            LBB acceptance criteria are is performed of the protection from the      evaluation report on the          met by the as-built RCS dynamic effects of a rupture of the line. protection from dynamic effects    piping and piping materials, or of a pipe break. Section 3.3,      a pipe break evaluation report Nuclear Island Buildings,          exists and concludes that contains the design descriptions  protection from the dynamic and inspections, tests, analyses,  effects of a line break is and acceptance criteria for        provided.
protection from the dynamic effects of pipe rupture.
367  2.3.06.07a.i  7.a) The Class 1E equipment identified      i) Type tests, analyses, or a      i) A report exists and in Tables 2.3.6-1 as being qualified for a  combination of type tests and      concludes that the Class 1E harsh environment can withstand the          analyses will be performed on      equipment identified in Table environmental conditions that would          Class 1E equipment located in a    2.3.6-1 as being qualified for a exist before, during, and following a        harsh environment.                harsh environment can design basis accident without loss of                                          withstand the environmental safety function for the time required to                                        conditions that would exist perform the safety function.                                                    before, during, and following a design basis accident without loss of safety function for the time required to perform the safety function.
368  2.3.06.07a.ii 7.a) The Class 1E equipment identified      ii) Inspection will be performed  ii) A report exists and in Tables 2.3.6-1 as being qualified for a  of the as-built Class 1E          concludes that the as-built harsh environment can withstand the          equipment and the associated      Class 1E equipment and the environmental conditions that would          wiring, cables, and terminations  associated wiring, cables, and exist before, during, and following a        located in a harsh environment. terminations identified in design basis accident without loss of                                          Table 2.3.6-1 as being safety function for the time required to                                        qualified for a harsh perform the safety function.                                                    environment are bounded by type tests, analyses, or a combination of type tests and analyses.
369  2.3.06.07b  7.b) The Class 1E components                Testing will be performed on the  A simulated test signal exists identified in Table 2.3.6-1 are powered      RNS by providing a simulated      at the Class 1E equipment from their respective Class 1E division. test signal in each Class 1E      identified in Table 2.3.6-1 division.                          when the assigned Class 1E division is provided the test signal.
C-231
 
Table 2.3.6-4 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No.              Design Commitment                    Inspections, Tests, Analyses        Acceptance Criteria 370  2.3.06.07c  7.c) Separation is provided between          See ITAAC Table 3.3-6,            See ITAAC Table 3.3-6, RNS Class 1E divisions, and between          item 7.d.                          item 7.d.
Class 1E divisions and non-Class 1E cable.
371  2.3.06.08a  8.a) The RNS preserves containment          See ITAAC Table 2.2.1-3,          See ITAAC Table 2.2.1-3, integrity by isolation of the RNS lines      item 7.                            item 7.
penetrating the containment.
372  2.3.06.08b  8.b) The RNS provides a flow path for        See item 1 in this table.          See item 1 in this table.
long-term, post-accident makeup to the RCS.
373  2.3.06.09a.i  9.a) The RNS provides LTOP for the          i) Inspections will be conducted  i) The rated capacity recorded RCS during shutdown operations.              on the low temperature            on the valve vendor code plate overpressure protection relief    is not less than the flow valve to confirm that the          required to provide low-capacity of the vendor code plate  temperature overpressure rating is greater than or equal to protection for the RCS, as system relief requirements.        determined by the LTOPS evaluation based on the pressure-temperature curves developed for the as-procured reactor vessel material.
374  2.3.06.09a.ii 9.a) The RNS provides LTOP for the          ii) Testing and analysis in        ii) A report exists and RCS during shutdown operations.              accordance with the ASME Code      concludes that the relief valve Section III will be performed to  opens at a pressure not greater determine set pressure.            than the set pressure required to provide low-temperature overpressure protection for the RCS, as determined by the LTOPS evaluation based on the pressure-temperature curves developed for the as-procured reactor vessel material.
375  2.3.06.09b.i  9.b) The RNS provides heat removal          i) Inspection will be performed    i) A report exists and from the reactor coolant during              for the existence of a report that concludes that the product of shutdown operations.                        determines the heat removal        the overall heat transfer capability of the RNS heat        coefficient and the effective exchangers.                        heat transfer area, UA, of each RNS heat exchanger is greater than or equal to 2.2 million Btu/hr-&deg;F.
C-232
 
Table 2.3.6-4 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No.                Design Commitment                    Inspections, Tests, Analyses        Acceptance Criteria 376  2.3.06.09b.ii  9.b) The RNS provides heat removal          ii) Testing will be performed to  ii) Each RNS pump provides from the reactor coolant during            confirm that the RNS can          at least 1400 gpm net flow to shutdown operations.                        provide flow through the RNS      the RCS when the hot leg heat exchangers when the pump      water level is at an elevation suction is aligned to the RCS hot  15.5 inches +/- 2 inches above leg and the discharge is aligned  the bottom of the hot leg.
to both PXS DVI lines with the RCS at atmospheric pressure.
377  2.3.06.09b.iii 9.b) The RNS provides heat removal          iii) Inspection will be performed  iii) The RCS cold legs piping from the reactor coolant during            of the reactor coolant loop        centerline is 17.5 inches +/- 2 shutdown operations.                        piping.                            inches above the hot legs piping centerline.
378  2.3.06.09b.iv  9.b) The RNS provides heat removal          iv) Inspection will be performed  iv) The RNS pump suction from the reactor coolant during            of the RNS pump suction piping. piping from the hot leg to the shutdown operations.                                                          pump suction piping low point does not form a local high point (defined as an upward slope with a vertical rise greater than 3 inches).
379  2.3.06.09b.v  9.b) The RNS provides heat removal          v) Inspection will be performed    v) The RNS suction line from the reactor coolant during            of the RNS pump suction nozzle    connection to the RCS is shutdown operations.                        connection to the RCS hot leg. constructed from 20-inch Schedule 140 pipe.
380  2.3.06.09c    9.c) The RNS provides low pressure          Testing will be performed to      Each RNS pump provides at makeup flow from the cask loading pit      confirm that the RNS can          least 1100 gpm net flow to the to the RCS for scenarios following          provide low pressure makeup        RCS when the water level actuation of the ADS.                      flow from the cask loading pit to  above the bottom of the cask the RCS when the pump suction      loading pit is 1 foot is aligned to the cask loading pit +/- 6 inches.
and the discharge is aligned to both PXS DVI lines with RCS at atmospheric pressure.
381  2.3.06.09d    9.d) The RNS provides heat removal          Testing will be performed to      Two operating RNS pumps from the in-containment refueling water    confirm that the RNS can          provide at least 2000 gpm to storage tank (IRWST).                      provide flow through the RNS      the IRWST.
heat exchangers when the pump suction is aligned to the IRWST and the discharge is aligned to the IRWST.
382    2.3.06.10    10. Safety-related displays identified in  Inspection will be performed for  Safety-related displays Table 2.3.6-1 can be retrieved in the      retrievability of the safety-      identified in Table 2.3.6-1 can MCR.                                        related displays in the MCR.      be retrieved in the MCR.
C-233
 
Table 2.3.6-4 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No.                Design Commitment                    Inspections, Tests, Analyses        Acceptance Criteria 383    2.3.06.11a  11.a) Controls exist in the MCR to          Stroke testing will be performed  Controls in the MCR operate cause those remotely operated valves        on the remotely operated valves    to cause those remotely identified in Table 2.3.6-1 to perform      identified in Table 2.3.6-1 using  operated valves identified in active functions.                          the controls in the MCR.          Table 2.3.6-1 to perform active functions.
384  2.3.06.11b    11.b) The valves identified in              Testing will be performed using    The valves identified in Table 2.3.6-1 as having PMS control        real or simulated signals into the Table 2.3.6-1 as having PMS perform active safety functions after      PMS.                              control perform the active receiving a signal from the PMS.                                              function identified in the table after receiving a signal from the PMS.
385  2.3.06.12a.i  12.a) The motor-operated and check          i) Tests or type tests of          i) A test report exists and valves identified in Table 2.3.6-1          motor-operated valves will be      concludes that each motor-perform an active safety-related            performed that demonstrate the    operated valve changes function to change position as indicated    capability of the valve to operate position as indicated in in the table.                              under its design conditions.      Table 2.3.6-1 under design conditions.
386  2.3.06.12a.ii  12.a) The motor-operated and check          ii) Inspection will be performed  ii) A report exists and valves identified in Table 2.3.6-1          for the existence of a report      concludes that the as-built perform an active safety-related            verifying that the as-built motor- motor-operated valves are function to change position as indicated    operated valves are bounded by    bounded by the tested in the table.                              the tested conditions.            conditions.
387  2.3.06.12a.iii 12.a) The motor-operated and check          iii) Tests of the motor-operated  iii) Each motor-operated valves identified in Table 2.3.6-1          valves will be performed under    valve changes position as perform an active safety-related            preoperational flow, differential  indicated in Table 2.3.6-1 function to change position as indicated    pressure and temperature          under preoperational test in the table.                              conditions.                        conditions.
388  2.3.06.12a.iv  12.a) The motor-operated and check          iv) Exercise testing of the check  iv) Each check valve changes valves identified in Table 2.3.6-1          valves active safety functions    position as indicated in perform an active safety-related            identified in Table 2.3.6-1 will  Table 2.3.6-1.
function to change position as indicated    be performed under in the table.                              preoperational test pressure, temperature and fluid flow conditions.
389  2.3.06.12b    12.b) After loss of motive power, the      Testing of the remotely operated  Upon loss of motive power, remotely operated valves identified in      valves will be performed under    each remotely operated valve Table 2.3.6-1 assume the indicated loss    the conditions of loss of motive  identified in Table 2.3.6-1 of motive power position.                  power.                            assumes the indicated loss of motive power position.
390    2.3.06.13    13. Controls exist in the MCR to cause      Testing will be performed to      Controls in the MCR cause the pumps identified in Table 2.3.6-3 to    actuate the pumps identified in    pumps identified in perform the listed function.                Table 2.3.6-3 using controls in    Table 2.3.6-3 to perform the the MCR.                          listed action.
C-234
 
Table 2.3.6-4 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No.              Design Commitment                    Inspections, Tests, Analyses          Acceptance Criteria 391  2.3.06.14  14. Displays of the RNS parameters          Inspection will be performed for    Displays of the RNS identified in Table 2.3.6-3 can be          retrievability in the MCR of the    parameters identified in retrieved in the MCR.                        displays identified in              Table 2.3.6-3 are retrieved in Table 2.3.6-3.                      the MCR.
Table 2.3.6-5 Component Name                              Tag No.                    Component Location RNS Pump A                                          RNS-MP-01A                      Auxiliary Building RNS Pump B                                          RNS-MP-01B                      Auxiliary Building RNS Heat Exchanger A                                RNS-ME-01A                      Auxiliary Building RNS Heat Exchanger B                                RNS-ME-01B                      Auxiliary Building C-235
 
Figure 2.3.6-1 Normal Residual Heat Removal System C-236
 
2.3.7          Spent Fuel Pool Cooling System Design Description The spent fuel pool cooling system (SFS) removes decay heat from spent fuel by transferring heat from the water in the spent fuel pool to the component cooling water system during normal modes of operation. The SFS purifies the water in the spent fuel pool, fuel transfer canal, and in-containment refueling water storage tank during normal modes of operation. Following events such as earthquakes, or fires, if the normal heat removal method is not available, decay heat is removed from spent fuel by boiling water in the pool. In the event of long-term station blackout, makeup water is supplied to the spent fuel pool from onsite storage tanks.
The SFS is as shown in Figure 2.3.7-1 and the component locations of the SFS are as shown in Table 2.3.7-5.
: 1. The functional arrangement of the SFS is as described in the Design Description of this Section 2.3.7.
: 2. a) The components identified in Table 2.3.7-1 as ASME Code Section III are designed and constructed in accordance with ASME Code Section III requirements.
b) The piping lines identified in Table 2.3.7-2 as ASME Code Section III are designed and constructed in accordance with ASME Code Section III requirements.
: 3. Pressure boundary welds in piping lines identified in Table 2.3.7-2 as ASME Code Section III meet ASME Code Section III requirements.
: 4. The piping lines identified in Table 2.3.7-2 as ASME Code Section III retain their pressure boundary integrity at their design pressure.
: 5. The seismic Category I components identified in Table 2.3.7-1 can withstand seismic design basis loads without loss of safety function.
: 6. a) The Class 1E components identified in Table 2.3.7-1 are powered from their respective Class 1E division.
b) Separation is provided between SFS Class 1E divisions, and between Class 1E divisions and non-Class 1E cable.
: 7. The SFS performs the following safety-related functions:
a) The SFS preserves containment integrity by isolating the SFS piping lines penetrating the containment.
b) The SFS provides spent fuel cooling for 7 days by boiling the spent fuel pool water and makeup water from on-site water storage tanks.
c) The SFS provides check valves in the drain line from the refueling cavity to prevent flooding of the refueling cavity during containment flooding.
: 8. The SFS provides the nonsafety-related function of removing spent fuel decay heat using pumped flow through a heat exchanger.
C-237
: 9. Safety-related displays identified in Table 2.3.7-1 can be retrieved in the main control room (MCR).
: 10. Controls exist in the MCR to cause the pumps identified in Table 2.3.7-3 to perform their listed functions.
11.Displays of the SFS parameters identified in Table 2.3.7-3 can be retrieved in the MCR.
C-238
 
Table 2.3.7-1 Class 1E/                          Loss of ASME                Remotely Qual for  Safety-                  Motive Component                      Code      Seismic    Operated  Harsh    Related Control  Active  Power Name            Tag No. Section III  Cat 1      Valve  Envir. Display  PMS    Function Position Spent Fuel Pool Level    SFS-019A      No        Yes          -    Yes/No    Yes      -        -      -
Sensor Spent Fuel Pool Level    SFS-019B      No        Yes          -    Yes/No    Yes      -        -      -
Sensor Spent Fuel Pool Level    SFS-019C      No        Yes          -    Yes/No    Yes      -        -      -
Sensor Refueling Cavity Drain  SFS-PL-V031    Yes        Yes          No      -/-      Yes      -        -      -
to SGS Compartment Isolation Valve Refueling Cavity to SFS SFS-PL-V032    Yes        Yes          No      -/-      No      -        -      -
Pump Suction Isolation Valve Refueling Cavity Drain  SFS-PL-V033    Yes        Yes          No      -/-      Yes      -        -      -
to Containment Sump Isolation Valve IRWST to SFS Pump      SFS-PL-V039    Yes        Yes          No      -/-      No      -        -      -
Suction Line Isolation Valve Fuel Transfer Canal to  SFS-PL-V040    Yes        Yes          No      -/-      No      -        -      -
SFS Pump Suction Iso.
Valve Cask Loading Pit to SFS SFS-PL-V041    Yes        Yes          No      -/-      No      -        -      -
Pump Suction Isolation Valve Cask Loading Pit to SFS SFS-PL-V042    Yes        Yes          No      -/-      No      -    Transfer    -
Pump Suction Isolation                                                                        Closed Valve C-239
 
Table 2.3.7-1 Class 1E/                          Loss of ASME                Remotely Qual for  Safety-                  Motive Component                            Code      Seismic    Operated  Harsh    Related Control  Active  Power Name                    Tag No. Section III  Cat 1      Valve  Envir. Display  PMS    Function Position SFS Pump Discharge            SFS-PL-V045    Yes        Yes          No      -/-      No      -    Transfer    -
Line to Cask Loading                                                                                  Closed Pit Isolation Valve Cask Loading Pit to            SFS-PL-V049    Yes        Yes          No      -/-      No      -    Transfer    -
WLS Isolation Valve                                                                                  Closed Spent Fuel Pool to Cask        SFS-PL-V066    Yes        Yes          No      -/-      No      -    Transfer    -
Washdown Pit Isolation                                                                                Open Valve Cask Washdown Pit              SFS-PL-V068    Yes        Yes          No      -/-      No      -    Transfer    -
Drain Isolation Valve                                                                                Open Refueling Cavity Drain        SFS-PL-V071    Yes        Yes          No      -/-      No      -    Transfer    -
Line Check Valve                                                                                      Open Transfer Closed Refueling Cavity Drain        SFS-PL-V072    Yes        Yes          No      -/-      No      -    Transfer    -
Line Check Valve                                                                                      Open Transfer Closed SFS Containment                SFS-PL-V075    Yes        Yes          No      -/-      Yes      -        -      -
Floodup Isolation Valve Note: Dash (-) indicates not applicable.
C-240
 
Table 2.3.7-2 Piping Line Name                    Line Number              ASME Code Section III Spent Fuel Pool to RNS Pump Suction                L014                        Yes Cask Loading Pit to RNS Pump Suction                L015                        Yes Refueling Cavity Drain                              L033                        Yes PXS IRWST to SFS Pump Suction                      L035                        Yes Refueling Cavity Skimmer to SFS Pump                L036                        Yes Suction Refueling Cavity Drain                              L037                        Yes Refueling Cavity Drain                              L044                        Yes Fuel Transfer Canal Drain                          L047                        Yes Cask Washdown Pit Drain                            L068                        Yes Cask Loading Pit Drain                              L043                        Yes Cask Pit Transfer Branch Line                      L045                        Yes Refueling Cavity Drain                              L030                        Yes Refueling Cavity Drain                              L040                        Yes Spent Fuel Pool Drain                              L066                        Yes Cask Loading Pit to WLS                            L067                        Yes RNS Return to Spent Fuel Pool                      L100                        Yes SFS Containment Floodup Line                        L120                        Yes Table 2.3.7-3 Component Name                  Tag No.            Display      Control Function SFS Pump 1A                            SFS-MP-01A            Yes              Start (Run Status)
SFS Pump 1B                            SFS-MP-01B            Yes              Start (Run Status)
SFS Flow Sensor                          SFS-13A              Yes                -
SFS Flow Sensor                          SFS-13B              Yes                -
Spent Fuel Pool Temperature Sensor        SFS-018              Yes                -
Cask Loading Pit Level Sensor            SFS-022              Yes                -
Note: Dash (-) indicates not applicable.
C-241
 
Table 2.3.7-4 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No.              Design Commitment                    Inspections, Tests, Analyses        Acceptance Criteria 392    2.3.07.01  1. The functional arrangement of the        Inspection of the as-built system The as-built SFS conforms SFS is as described in the Design            will be performed.                with the functional Description of this Section 2.3.7.                                            arrangement as described in the Design Description of this Section 2.3.7.
393  2.3.07.02a  2.a) The components identified in            Inspection will be conducted of  The ASME Code Section III Table 2.3.7-1 as ASME Code                  the ASME as-built components      design reports exist for the as-Section III are designed and constructed    as documented in the ASME        built components identified in in accordance with ASME Code                design reports.                  Table 2.3.7-1 as ASME Code Section III requirements.                                                      Section III.
394  2.3.07.02b  2.b) The piping lines identified in          Inspection will be conducted of  The ASME Code Section III Table 2.3.7-2 as ASME Code                  the as-built piping lines as      design reports exist for the as-Section III are designed and constructed    documented in the ASME design    built piping lines identified in in accordance with ASME Code                reports.                          Table 2.3.7-2 as ASME Code Section III requirements.                                                      Section III.
395    2.3.07.03  3. Pressure boundary welds in piping        Inspection of the as-built        A report exists and concludes lines identified in Table 2.3.7-2 as        pressure boundary welds will be  that the ASME Code ASME Code Section III meet ASME              performed in accordance with      Section III requirements are Code Section III requirements.              the ASME Code Section III.        met for non-destructive examination of pressure boundary welds.
396    2.3.07.04  4. The piping lines identified in            A hydrostatic test will be        A report exists and concludes Table 2.3.7-2 as ASME Code                  performed on the piping lines    that the results of the Section III retain their pressure            required by the ASME Code        hydrostatic test of the piping boundary integrity at their design          Section III to be hydrostatically lines identified in pressure.                                    tested.                          Table 2.3.7-2 as ASME Code Section III conform with the requirements of the ASME Code Section III.
397  2.3.07.05.i 5. The seismic Category I components        i) Inspection will be performed  i) The seismic Category I identified in Table 2.3.7-1 can withstand    to verify that the seismic        components identified in seismic design basis loads without loss      Category I components            Table 2.3.7-1 are located on of safety functions.                        identified in Table 2.3.7-1 are  the Nuclear Island.
located on the Nuclear Island.
398  2.3.07.05.ii 5. The seismic Category I components        ii) Type tests, analyses, or a    ii) A report exists and identified in Table 2.3.7-1 can withstand    combination of type tests and    concludes that the seismic seismic design basis loads without loss      analyses of seismic Category I    Category I equipment can of safety functions.                        equipment will be performed.      withstand seismic design basis loads without loss of safety function.
C-242
 
Table 2.3.7-4 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No.                Design Commitment                    Inspections, Tests, Analyses        Acceptance Criteria 399  2.3.07.05.iii 5. The seismic Category I components        iii) Inspection will be performed  iii) A report exists and identified in Table 2.3.7-1 can withstand    for the existence of a report      concludes that the as-built seismic design basis loads without loss      verifying that the as-built        equipment including of safety functions.                        equipment including anchorage      anchorage is seismically is seismically bounded by the      bounded by the tested or tested or analyzed conditions. analyzed conditions.
400    2.3.07.06a  6.a) The Class 1E components                Testing will be performed on the  A simulated test signal exists identified in Table 2.3.7-1 are powered      SFS by providing a simulated      at the Class 1E components from their respective Class 1E division. test signal in each Class 1E      identified in Table 2.3.7-1 division.                          when the assigned Class 1E division is provided the test signal.
401    2.3.07.06b  6.b) Separation is provided between          See ITAAC Table 3.3-6,            See ITAAC Table 3.3-6, SFS Class 1E divisions, and between          item 7.d.                          item 7.d.
Class 1E divisions and non-Class 1E cable.
402    2.3.07.07a  7.a) The SFS preserves containment          See ITAAC Table 2.2.1-3,          See ITAAC Table 2.2.1-3, integrity by isolation of the SFS lines      items 1 and 7.                    items 1 and 7.
penetrating the containment.
403  2.3.07.07b.i  7.b) The SFS provides spent fuel            i) Inspection will be performed    i) The volume of the spent cooling for 7 days by boiling the spent      to verify that the spent fuel pool fuel pool and fuel transfer fuel pool water and makeup water from        includes a sufficient volume of    canal above the fuel and to the on-site storage tanks.                      water.                            elevation 6 feet below the operating deck is greater than or equal to 129,500 gallons.
404  2.3.07.07b.ii  7.b) The SFS provides spent fuel            ii) Inspection will be performed  ii) The water volume of the cooling for 7 days by boiling the spent      to verify the cask washdown pit    cask washdown pit is greater fuel pool water and makeup water from        includes sufficient volume of      than or equal to on-site storage tanks.                      water.                            30,900 gallons.
405  2.3.07.07b.iii 7.b) The SFS provides spent fuel            iii) A safety-related flow path    iii) See item 1 of this table.
cooling for 7 days by boiling the spent      exists from the cask washdown fuel pool water and makeup water from        pit to the spent fuel pool.
on-site storage tanks.
406  2.3.07.07b.iv  7.b) The SFS provides spent fuel            iv) See ITAAC Table 2.2.2-3,      iv) See ITAAC Table 2.2.2-3, cooling for 7 days by boiling the spent      item 7.f for inspection, testing,  item 7.f for inspection, testing, fuel pool water and makeup water from        and acceptance criteria for the    and acceptance criteria for the on-site storage tanks.                      makeup water supply from the      makeup water supply from the passive containment cooling        PCS water storage tank to the system (PCS) water storage tank    spent fuel pool.
to the spent fuel pool.
C-243
 
Table 2.3.7-4 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No.              Design Commitment                    Inspections, Tests, Analyses        Acceptance Criteria 407  2.3.07.07b.v  7.b) The SFS provides spent fuel            v) Inspection will be performed    v) See ITAAC Table 2.2.2-3, cooling for 7 days by boiling the spent      to verify that the passive        item 7.f for the volume of the fuel pool water and makeup water from        containment cooling system        passive containment cooling on-site storage tanks.                      water storage tank includes a      system water storage tank.
sufficient volume of water.
408  2.3.07.07b.vi 7.b) The SFS provides spent fuel            vi) See ITAAC Table 2.2.2-3,      vi) See ITAAC Table 2.2.2-3, cooling for 7 days by boiling the spent      items 8.a and 8.b for inspection,  items 8.a and 8.b for fuel pool water and makeup water from        testing, and acceptance criteria  inspection, testing, and on-site storage tanks.                      to verify that the passive        acceptance criteria for the containment cooling system        volume of the passive ancillary water storage tank      containment cooling system includes a sufficient volume of    ancillary water storage tank.
water.
409  2.3.07.07c  7c) The SFS provides check valves in        Exercise testing of the check      Each check valve changes the drain line from the refueling cavity    valves with active safety-        position as indicated on to prevent flooding of the refueling        functions identified in Table      Table 2.3.7-1.
cavity during containment flooding.          2.3.7-1 will be performed under pre-operational test pressure, temperature and flow conditions.
410  2.3.07.08.i  8. The SFS provides the nonsafety-          i) Inspection will be performed    i) A report exists and related function of removing spent fuel      for the existence of a report that concludes that the heat decay heat using pumped flow through        determines the heat removal        transfer characteristic, UA, of a heat exchanger.                            capability of the SFS heat        each SFS heat exchanger is exchangers.                        greater than or equal to 2.2 million Btu/hr-&deg;F.
411  2.3.07.08.ii 8. The SFS provides the nonsafety-          ii) Testing will be performed to  ii) Each SFS pump produces related function of removing spent fuel      confirm that each SFS pump        at least 900 gpm through its decay heat using pumped flow through        provides flow through its heat    heat exchanger.
a heat exchanger.                            exchanger when taking suction from the SFP and returning flow to the SFP.
412    2.3.07.09  9. Safety-related displays identified in    Inspection will be performed for  Safety-related displays Table 2.3.7-1 can be retrieved in the        retrievability of the safety-      identified in Table 2.3.7-1 can MCR.                                        related displays in the MCR.      be retrieved in the MCR.
413    2.3.07.10  10. Controls exist in the MCR to cause      Testing will be performed to      Controls in the MCR cause the pumps identified in Table 2.3.7-3 to    actuate the pumps identified in    pumps identified in perform their listed functions.              Table 2.3.7-3 using controls in    Table 2.3.7-3 to perform the the MCR.                          listed functions.
414    2.3.07.11  11. Displays of the SFS parameters          Inspection will be performed for  Displays of the SFS identified in Table 2.3.7-3 can be          retrievability in the MCR of the  parameters identified in retrieved in the MCR.                        displays identified in            Table 2.3.7-3 are retrieved in Table 2.3.7-3.                    the MCR.
C-244
 
Table 2.3.7-5 Component Name                Tag No. Component Location SFS Pump A                                  SFS-MP-01A  Auxiliary Building SFS Pump B                                  SFS-MP-01B  Auxiliary Building SFS Heat Exchanger A                        SFS-ME-01A  Auxiliary Building SFS Heat Exchanger B                        SFS-ME-01B  Auxiliary Building C-245
 
Figure 2.3.7-1 Spent Fuel Pool Cooling System C-246
 
2.3.8          Service Water System Design Description The service water system (SWS) transfers heat from the component cooling water heat exchangers to the atmosphere. The SWS operates during normal modes of plant operation, including startup, power operation (full and partial loads), cooldown, shutdown, and refueling.
The SWS is as shown in Figure 2.3.8-1 and the component locations of the SWS are as shown Table 2.3.8-3.
: 1. The functional arrangement of the SWS is as described in the Design Description of this Section 2.3.8.
: 2. The SWS provides the nonsafety-related function of transferring heat from the component cooling water system (CCS) to the surrounding atmosphere to support plant shutdown and spent fuel pool cooling.
: 3. Controls exist in the main control room (MCR) to cause the components identified in Table 2.3.8-1 to perform the listed function.
: 4. Displays of the parameters identified in Table 2.3.8-1 can be retrieved in the MCR.
C-247
 
Table 2.3.8-1 Equipment Name                            Tag No.              Display      Control Function Service Water Pump A (Motor)                          SWS-MP-01A                Yes                Start (Run Status)
Service Water Pump B (Motor)                          SWS-MP-01B                Yes                Start (Run Status)
Service Water Cooling Tower Fan A (Motor)              SWS-MA-01A                Yes                Start (Run Status)
Service Water Cooling Tower Fan B (Motor)              SWS-MA-01B                Yes                Start (Run Status)
Service Water Pump 1A Flow Sensor                      SWS-004A                  Yes                  -
Service Water Pump 1B Flow Sensor                      SWS-004B                  Yes                  -
Service Water Pump A Discharge Valve                  SWS-PL-V002A                Yes              Open (Valve Position)
Service Water Pump B Discharge Valve                  SWS-PL-V002B                Yes              Open (Valve Position)
Service Water Pump A Discharge Temperature              SWS-005A                  Yes                  -
Sensor Service Water Pump B Discharge Temperature              SWS-005B                  Yes                  -
Sensor Service Water Cooling Tower Basin Level                  SWS-009                  Yes                  -
Note: Dash (-) indicates not applicable.
Table 2.3.8-2 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No.                Design Commitment                    Inspections, Tests, Analyses        Acceptance Criteria 415    2.3.08.01    1. The functional arrangement of the        Inspection of the as-built system The as-built SWS conforms SWS is as described in the Design            will be performed.                with the functional Description of this Section 2.3.8.                                            arrangement as described in the Design Description of this Section 2.3.8.
416  2.3.08.02.i    2. The SWS provides the nonsafety-          i) Testing will be performed to  i) Each SWS pump can related function of transferring heat        confirm that the SWS can          provide at least 10,000 gpm of from the component cooling water            provide cooling water to the      cooling water through its CCS system to the surrounding atmosphere        CCS heat exchangers.              heat exchanger.
to support plant shutdown and spent fuel pool cooling.
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Table 2.3.8-2 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No.                Design Commitment                    Inspections, Tests, Analyses          Acceptance Criteria 417  2.3.08.02.ii  2. The SWS provides the nonsafety-          ii) Inspection will be performed    ii) A report exists and related function of transferring heat        for the existence of a report that  concludes that the heat from the component cooling water            determines the heat transfer        transfer rate of each cooling system to the surrounding atmosphere        capability of each cooling tower    tower cell is greater than or to support plant shutdown and spent          cell.                                equal to 170 million Btu/hr at fuel pool cooling.                                                                a 80.1&deg;F ambient wet bulb temperature and a cold water temperature of 90&deg;F.
418  2.3.08.02.iii  2. The SWS provides the nonsafety-          iii) Testing will be performed to    iii) The SWS tower basin related function of transferring heat        confirm that the SWS cooling        contains a usable volume of at from the component cooling water            tower basin has adequate reserve    least 230,000 gallons at the system to the surrounding atmosphere        volume.                              basin low level alarm setpoint.
to support plant shutdown and spent fuel pool cooling.
419    2.3.08.03    3. Controls exist in the MCR to cause        Testing will be performed on the    Controls in the MCR operate the components identified in Table          components in Table 2.3.8-1          to cause the components listed 2.3.8-1 to perform the listed function.      using controls in the MCR.          in Table 2.3.8-1 to perform the listed functions.
420    2.3.08.04    4. Displays of the parameters identified    Inspection will be performed for    The displays identified in in Table 2.3.8-1 can be retrieved in the    retrievability of parameters in      Table 2.3.8-1 can be retrieved MCR.                                        the MCR.                            in the MCR.
Table 2.3.8-3 Component Name                              Tag No.                          Component Location Service Water Pump A                            SWS-MP-01A                          Turbine Building or yard Service Water Pump B                            SWS-MP-01B                          Turbine Building or yard Service Water Cooling Tower                      SWS-ME-01                                    Yard C-249
 
Figure 2.3.8-1 Service Water System C-250
 
2.3.9            Containment Hydrogen Control System Design Description The containment hydrogen control system (VLS) limits hydrogen gas concentration in containment during accidents.
The VLS has catalytic hydrogen recombiners (VLS-MY-E01A and VLS-MY-E01B) that are located inside containment. The VLS has hydrogen igniters located as shown on Table 2.3.9-2.
: 1. The functional arrangement of the VLS is as described in the Design Description of this Section 2.3.9.
: 2. a) The hydrogen monitors identified in Table 2.3.9-1 are powered by the non-Class 1E dc and UPS system.
b) The components identified in Table 2.3.9-2 are powered from their respective non-Class 1E power group.
: 3. The VLS provides the non-safety related function to control the containment hydrogen concentration for beyond design basis accidents.
: 4. a) Controls exist in the MCR to cause the components identified in Table 2.3.9-2 to perform the listed function.
b) The components identified in Table 2.3.9-2 perform the listed function after receiving a manual signal from the diverse actuation system (DAS).
: 5. Displays of the parameters identified in Table 2.3.9-1 can be retrieved in the MCR.
Table 2.3.9-1 Equipment                            Tag No.                  Display Containment Hydrogen Monitor                          VLS-001                    Yes Containment Hydrogen Monitor                          VLS-002                    Yes Containment Hydrogen Monitor                          VLS-003                    Yes C-251
 
Table 2.3.9-2 Power Group                                            Room Equipment Name    Tag Number Function  Number                    Location                  No.
Hydrogen Igniter 01 VLS-EH-01  Energize      1      Tunnel connection loop compartments    11204 Hydrogen Igniter 02 VLS-EH-02  Energize      2      Tunnel connection loop compartments    11204 Hydrogen Igniter 03 VLS-EH-03  Energize      1      Tunnel connection loop compartments    11204 Hydrogen Igniter 04 VLS-EH-04  Energize      2      Tunnel connection loop compartments    11204 Hydrogen Igniter 05 VLS-EH-05  Energize      1      Loop compartment 02                    11402 Hydrogen Igniter 06 VLS-EH-06  Energize      2      Loop compartment 02                    11502 Hydrogen Igniter 07 VLS-EH-07  Energize      2      Loop compartment 02                    11402 Hydrogen Igniter 08 VLS-EH-08  Energize      1      Loop compartment 02                    11502 Hydrogen Igniter 09 VLS-EH-09  Energize      1      In-containment refueling water storage 11305 tank (IRWST)
Hydrogen Igniter 10 VLS-EH-10  Energize      2      IRWST                                  11305 Hydrogen Igniter 11 VLS-EH-11  Energize      2      Loop compartment 01                    11401 Hydrogen Igniter 12 VLS-EH-12  Energize      1      Loop compartment 01                    11501 Hydrogen Igniter 13 VLS-EH-13  Energize      1      Loop compartment 01                    11401 Hydrogen Igniter 14 VLS-EH-14  Energize      2      Loop compartment 01                    11501 Hydrogen Igniter 15 VLS-EH-15  Energize      2      IRWST                                  11305 Hydrogen Igniter 16 VLS-EH-16  Energize      1      IRWST                                  11305 Hydrogen Igniter 17 VLS-EH-17  Energize      2      Northeast valve room                  11207 Hydrogen Igniter 18 VLS-EH-18  Energize      1      Northeast accumulator room            11207 Hydrogen Igniter 19 VLS-EH-19  Energize      2      East valve room                        11208 Hydrogen Igniter 20 VLS-EH-20  Energize      2      Southeast accumulator room            11206 Hydrogen Igniter 21 VLS-EH-21  Energize      1      Southeast valve room                  11206 Hydrogen Igniter 22 VLS-EH-22  Energize      1      Lower compartment area (core makeup    11400 tank [CMT] and valve area)
Hydrogen Igniter 23 VLS-EH-23  Energize      2      Lower compartment area (CMT and        11400 valve area)
Hydrogen Igniter 24 VLS-EH-24  Energize      2      Lower compartment area (CMT and        11400 valve area)
Hydrogen Igniter 25 VLS-EH-25  Energize      2      Lower compartment area (CMT and        11400 valve area)
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Table 2.3.9-2 Power Group                                      Room Equipment Name    Tag Number Function  Number                    Location          No.
Hydrogen Igniter 26 VLS-EH-26  Energize      2      Lower compartment area (CMT and 11400 valve area)
Hydrogen Igniter 27 VLS-EH-27  Energize      1      Lower compartment area (CMT and 11400 valve area)
Hydrogen Igniter 28 VLS-EH-28  Energize      1      Lower compartment area (CMT and 11400 valve area)
Hydrogen Igniter 29 VLS-EH-29  Energize      1      Lower compartment area (CMT and 11400 valve area)
Hydrogen Igniter 30 VLS-EH-30  Energize      2      Lower compartment area (CMT and 11400 valve area)
Hydrogen Igniter 31 VLS-EH-31  Energize      1      Lower compartment area (CMT and 11400 valve area)
Hydrogen Igniter 32 VLS-EH-32  Energize      1      Lower compartment area (CMT and 11400 valve area)
Hydrogen Igniter 33 VLS-EH-33  Energize      2      North CVS equipment room        11209 Hydrogen Igniter 34 VLS-EH-34  Energize      1      North CVS equipment room        11209 Hydrogen Igniter 35 VLS-EH-35  Energize      1      IRWST                          11305 Hydrogen Igniter 36 VLS-EH-36  Energize      2      IRWST                          11305 Hydrogen Igniter 37 VLS-EH-37  Energize      1      IRWST                          11305 Hydrogen Igniter 38 VLS-EH-38  Energize      2      IRWST                          11305 Hydrogen Igniter 39 VLS-EH-39  Energize      1      Upper compartment lower region  11500 Hydrogen Igniter 40 VLS-EH-40  Energize      2      Upper compartment lower region  11500 Hydrogen Igniter 41 VLS-EH-41  Energize      2      Upper compartment lower region  11500 Hydrogen Igniter 42 VLS-EH-42  Energize      1      Upper compartment lower region  11500 Hydrogen Igniter 43 VLS-EH-43  Energize      1      Upper compartment lower region  11500 Hydrogen Igniter 44 VLS-EH-44  Energize      1      Upper compartment lower region  11500 Hydrogen Igniter 45 VLS-EH-45  Energize      2      Upper compartment lower region  11500 Hydrogen Igniter 46 VLS-EH-46  Energize      2      Upper compartment lower region  11500 Hydrogen Igniter 47 VLS-EH-47  Energize      1      Upper compartment lower region  11500 Hydrogen Igniter 48 VLS-EH-48  Energize      2      Upper compartment lower region  11500 Hydrogen Igniter 49 VLS-EH-49  Energize      1      Pressurizer compartment        11503 Hydrogen Igniter 50 VLS-EH-50  Energize      2      Pressurizer compartment        11503 C-253
 
Table 2.3.9-2 Power Group                                                Room Equipment Name      Tag Number      Function      Number                      Location                  No.
Hydrogen Igniter 51    VLS-EH-51        Energize        1        Upper compartment mid-region            11500 Hydrogen Igniter 52    VLS-EH-52        Energize        2        Upper compartment mid-region            11500 Hydrogen Igniter 53    VLS-EH-53        Energize        2        Upper compartment mid-region            11500 Hydrogen Igniter 54    VLS-EH-54        Energize        1        Upper compartment mid-region            11500 Hydrogen Igniter 55    VLS-EH-55        Energize        1        Refueling cavity                        11504 Hydrogen Igniter 56    VLS-EH-56        Energize        2        Refueling cavity                        11504 Hydrogen Igniter 57    VLS-EH-57        Energize        2        Refueling cavity                        11504 Hydrogen Igniter 58    VLS-EH-58        Energize        1        Refueling cavity                        11504 Hydrogen Igniter 59    VLS-EH-59        Energize        2        Pressurizer compartment                  11503 Hydrogen Igniter 60    VLS-EH-60        Energize        1        Pressurizer compartment                  11503 Hydrogen Igniter 61    VLS-EH-61        Energize        1        Upper compartment-upper region          11500 Hydrogen Igniter 62    VLS-EH-62        Energize        2        Upper compartment-upper region          11500 Hydrogen Igniter 63    VLS-EH-63        Energize        1        Upper compartment-upper region          11500 Hydrogen Igniter 64    VLS-EH-64        Energize        2        Upper compartment-upper region          11500 Table 2.3.9-3 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No.              Design Commitment                    Inspections, Tests, Analyses          Acceptance Criteria 421  2.3.09.01    1. The functional arrangement of the        Inspection of the as-built system The as-built VLS conforms VLS is as described in the Design          will be performed.                with the functional Description of this Section 2.3.9.                                            arrangement as described in the Design Description of this Section 2.3.9.
422  2.3.09.02a  2.a) The hydrogen monitors identified      Testing will be performed by      A simulated test signal exists in Table 2.3.9-1 are powered by the        providing a simulated test signal at the hydrogen monitors non-Class 1E dc and UPS system.            in each power group of the        identified in Table 2.3.9-1 non-Class 1E dc and UPS          when the non-Class 1E dc and system.                          UPS system is provided the test signal.
C-254
 
Table 2.3.9-3 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No.                Design Commitment                    Inspections, Tests, Analyses        Acceptance Criteria 423    2.3.09.02b    2.b) The components identified in          Testing will be performed by      A simulated test signal exists Table 2.3.9-2 are powered from their        providing a simulated test signal  at the equipment identified in respective non-Class 1E power group.        in each non-Class 1E power        Table 2.3.9-2 when the group.                            assigned non-Class 1E power group is provided the test signal.
424    2.3.09.03.i  3. The VLS provides the nonsafety-          i) Inspection for the number of    i) At least 64 hydrogen related function to control the            igniters will be performed.        igniters are provided inside containment hydrogen concentration for                                        containment at the locations beyond design basis accidents.                                                specified in Table 2.3.9-2.
425    2.3.09.03.ii  3. The VLS provides the nonsafety-          ii) Operability testing will be    ii) The surface temperature of related function to control the            performed on the igniters.        the igniter exceeds 1700&deg;F.
containment hydrogen concentration for beyond design basis accidents.
426  C.2.3.09.03.iii 3. The VLS provides the nonsafety-          iii) An inspection of the as-built iii) The equipment access related function to control the            containment internal structures    opening and CMT-A opening containment hydrogen concentration for      will be performed.                constitute at least 98% of vent beyond design basis accidents.                                                paths within Room 11206 that vent to Room 11300. The minimum distance between the equipment access opening and containment shell is at least 24.3 feet. The minimum distance between the CMT-A opening and the containment shell is at least 9.4 feet. The CMT-B opening constitutes at least 98% of vent paths within Room 11207 that vent to Room 11300 and is a minimum distance of 24.6 feet away from the containment shell. Other openings through the ceilings of these rooms must be at least 3 feet from the containment shell.
427  2.3.09.03.iv  3. The VLS provides the nonsafety-          iv) An inspection will be          iv) The discharge from each related function to control the            performed of the as-built IRWST    of these IRWST vents is containment hydrogen concentration for      vents that are located in the roof oriented generally away from beyond design basis accidents.              of the IRWST along the side of    the containment shell.
the IRWST next to the containment shell.
428    2.3.09.04a    4.a) Controls exist in the MCR to cause    Testing will be performed on the  Controls in the MCR operate the components identified in Table          igniters using the controls in the to energize the igniters.
2.3.9-2 to perform the listed function. MCR.
C-255
 
Table 2.3.9-3 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No.            Design Commitment                    Inspections, Tests, Analyses          Acceptance Criteria 429  2.3.09.04b 4.b) The components identified in            Testing will be performed on the  The igniters energize after Table 2.3.9-2 perform the listed            igniters using the DAS controls. receiving a signal from DAS.
function after receiving manual a signal from DAS.
430    2.3.09.05 5. Displays of the parameters identified    Inspection will be performed for  Displays identified in in Table 2.3.9-1 can be retrieved in the    retrievability of the displays    Table 2.3.9-1 can be retrieved MCR.                                        identified in Table 2.3.9-1 in the in the MCR.
MCR.
C-256
 
2.3.10          Liquid Radwaste System Design Description The liquid radwaste system (WLS) receives, stores, processes, samples and monitors the discharge of radioactive wastewater.
The WLS has components which receive and store radioactive or potentially radioactive liquid waste. These are the reactor coolant drain tank, the containment sump, the effluent holdup tanks and the waste holdup tanks. The WLS components store and process the waste during normal operation and during anticipated operational occurrences. Monitoring of the liquid waste is performed prior to discharge.
The WLS is as shown in Figure 2.3.10-1 and the component locations of the WLS are as shown in Table 2.3.10-5.
: 1. The functional arrangement of the WLS is as described in the Design Description of this Section 2.3.10.
: 2. a) The components identified in Table 2.3.10-1 as ASME Code Section III are designed and constructed in accordance with ASME Code Section III requirements.
b) The piping identified in Table 2.3.10-2 as ASME Code Section III is designed and constructed in accordance with ASME Code Section III requirements.
: 3. a) Pressure boundary welds in components identified in Table 2.3.10-1 as ASME Code Section III meet ASME Code Section III requirements.
b) Pressure boundary welds in piping identified in Table 2.3.10-2 as ASME Code Section III meet ASME Code Section III requirements.
: 4. a) The components identified in Table 2.3.10-1 as ASME Code Section III retain their pressure boundary integrity at their design pressure.
b) The piping identified in Table 2.3.10-2 as ASME Code Section III retains its pressure boundary integrity at its design pressure.
: 5. a) The seismic Category I equipment identified in Table 2.3.10-1 can withstand seismic design basis loads without loss of safety function.
b) Each of the lines identified in Table 2.3.10-2 for which functional capability is required is designed to withstand combined normal and seismic design basis loads without a loss of its functional capability.
: 6. The WLS provides the following safety-related functions:
a) The WLS preserves containment integrity by isolation of the WLS lines penetrating the containment.
b) Check valves in drain lines to the containment sump limit cross flooding of compartments.
: 7. The WLS provides the nonsafety-related functions of:
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a) Detecting leaks within containment to the containment sump.
b) Controlling releases of radioactive materials in liquid effluents.
: 8. Controls exist in the main control room (MCR) to cause the remotely operated valve identified in Table 2.3.10-3 to perform its active function.
: 9. The check valves identified in Table 2.3.10-1 perform an active safety-related function to change position as indicated in the table.
: 10. Displays of the parameters identified in Table 2.3.10-3 can be retrieved in the MCR.
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Table 2.3.10-1 Class 1E/
Remotely Qual. for Safety-ASME Code      Seismic Operated  Harsh    Related  Active Equipment Name                Tag No. Section III    Cat. I  Valve    Envir. Display Function WLS Containment Sump Level Sensor      WLS-LT-034      No          Yes    No      No/No      No        -
WLS Containment Sump Level Sensor      WLS-LT-035      No          Yes    No      No/No      No        -
WLS Containment Sump Level Sensor      WLS-LT-036      No          Yes    No      No/No      No        -
WLS Drain from Passive Core Cooling    WLS-PL-V071B    Yes          Yes    No        -/-      No    Transfer System (PXS) Compartment A (Room                                                                      Closed 11206) Check Valve WLS Drain from PXS Compartment A      WLS-PL-V072B    Yes          Yes    No        -/-      No    Transfer (Room 11206) Check Valve                                                                              Closed WLS Drain from PXS Compartment B      WLS-PL-V071C    Yes          Yes    No        -/-      No    Transfer (Room 11207) Check Valve                                                                              Closed WLS Drain from PXS Compartment B      WLS-PL-V072C    Yes          Yes    No        -/-      No    Transfer (Room 11207) Check Valve                                                                              Closed WLS Drain from Chemical and Volume    WLS-PL-V071A    Yes          Yes    No        -/-      No    Transfer Control System (CVS) Compartment                                                                      Closed (Room 11209) Check Valve WLS Drain from CVS Compartment        WLS-PL-V072A    Yes          Yes    No        -/-      No    Transfer (Room 11209) Check Valve                                                                              Closed Note: Dash (-) indicates not applicable.
C-259
 
Table 2.3.10-2 Line Name                  Line No.        ASME Section III            Functional Capability Required WLS Drain from PXS            WLS-PL-L062                  Yes                            Yes Compartment A                  WLS-PL-L078 WLS Drain from PXS            WLS-PL-L063                  Yes                            Yes Compartment B                  WLS-PL-L079 WLS Drain from CVS            WLS-PL-L061                  Yes                            Yes Compartment                    WSL-PL-L077 WLS-PL-L020 Table 2.3.10-3 Equipment Name                          Tag No.                      Display          Control Function WLS Effluent Discharge Isolation            WLS-PL-V223                          -                  Close Valve Reactor Coolant Drain Tank Level            WLS-JE-LT002                      Yes                    -
Letdown Flow from CVS to WLS                WLS-JE-FT020                      Yes                    -
Table 2.3.10-4 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No.                Design Commitment                  Inspections, Tests, Analyses          Acceptance Criteria 431    2.3.10.01    1. The functional arrangement of the        Inspection of the as-built system  The as-built WLS conforms WLS is as described in the Design            will be performed.                with the functional Description of this Section 2.3.10.                                            arrangement as described in the Design Description of this Section 2.3.10.
432  2.3.10.02a    2.a) The components identified in            Inspection will be conducted of    The ASME Code Section III Table 2.3.10-1 as ASME Code Section          the as-built components as        design report exists for the as III are designed and constructed in          documented in the ASME design      built components identified in accordance with ASME Code                    reports.                          Table 2.3.10-1 as ASME Code Section III requirements.                                                      Section III.
433  2.3.10.02b    2.b) The piping identified in                Inspection will be conducted of    The ASME Code Section III Table 2.3.10-2 as ASME Code Section          the as-built piping as            design reports exist for the as-III is designed and constructed in          documented in the ASME design      built piping identified in accordance with ASME Code                    reports.                          Table 2.3.10-2 as ASME Code Section III requirements.                                                      Section III.
C-260
 
Table 2.3.10-4 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No.                Design Commitment                      Inspections, Tests, Analyses        Acceptance Criteria 434    2.3.10.03a  3.a) Pressure boundary welds in              Inspection of the as-built        A report exists and concludes components identified in Table 2.3.10-1      pressure boundary welds will be  that the ASME Code Section as ASME Code Section III meet ASME            performed in accordance with      III requirements are met for Code Section III requirements.                the ASME Code Section III.        non-destructive examination of pressure boundary welds.
435  2.3.10.03b    3.b) Pressure boundary welds in piping        Inspection of the as-built        A report exists and concludes identified in Table 2.3.10-2 as ASME          pressure boundary welds will be  that the ASME Code Code Section III meet ASME Code              performed in accordance with      Section III requirements are Section III requirements.                    the ASME Code Section III.        met for non-destructive examination of pressure boundary welds.
436    2.3.10.04a  4.a) The components identified in            A hydrostatic test will be        A report exists and concludes Table 2.3.10-1 as ASME Code                  performed on the components      that the results of the Section III retain their pressure            required by the ASME Code        hydrostatic test of the boundary integrity at their design            Section III to be hydrostatically components identified in pressure.                                    tested.                          Table 2.3.10-1 as ASME Code Section III conform with the requirements of the ASME Code Section III.
437  2.3.10.04b    4.b) The piping identified in                A hydrostatic test will be        A report exists and concludes Table 2.3.10-2 as ASME Code Section          performed on the piping required  that the results of the III retains its pressure boundary            by the ASME Code Section III to  hydrostatic test of the piping integrity at its design pressure.            be hydrostatically tested.        identified in Table 2.3.10-2 as ASME Code Section III conform with the requirements of the ASME Code Section III.
438  2.3.10.05a.i  5.a) The seismic Category I equipment        i) Inspection will be performed  i) The seismic Category I identified in Table 2.3.10-1 can              to verify that the seismic        equipment identified in withstand seismic design basis loads          Category I equipment identified  Table 2.3.10-1 is located on without loss of safety function.              in Table 2.3.10-1 is located on  the Nuclear Island.
the Nuclear Island.
439  2.3.10.05a.ii  5.a) The seismic Category I equipment        ii) Type tests, analyses, or a    ii) A report exists and identified in Table 2.3.10-1 can              combination of type tests and    concludes that the seismic withstand seismic design basis loads          analyses of seismic Category I    Category I equipment can without loss of safety function.              equipment will be performed.      withstand seismic design basis loads without loss of safety function.
440  2.3.10.05a.iii 5.a) The seismic Category I equipment        iii) Inspection will be performed iii) A report exists and identified in Table 2.3.10-1 can              for the existence of a report    concludes that the as-built withstand seismic design basis loads          verifying that the as-built      equipment including without loss of safety function.              equipment including anchorage    anchorage is seismically is seismically bounded by the    bounded by the tested or tested or analyzed conditions. analyzed conditions.
C-261
 
Table 2.3.10-4 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No.              Design Commitment                    Inspections, Tests, Analyses        Acceptance Criteria 441  2.3.10.05b  5.b) Each of the lines identified in        Inspection will be performed for  A report exists and concludes Table 2.3.10-2 for which functional          the existence of a report          that each of the as-built lines capability is required is designed to        verifying that the as-built piping identified in Table 2.3.10-2 for withstand combined normal and seismic        meets the requirements for        which functional capability is design basis loads without a loss of its    functional capability.            required meets the functional capability.                                                          requirements for functional capability.
442  2.3.10.06a  6.a) The WLS preserves containment          See ITAAC Table 2.2.1-3,          See ITAAC Table 2.2.1-3, integrity by isolation of the WLS lines      items 1 and 7.                    items 1 and 7.
penetrating the containment.
443  2.3.10.06b  6.b) Check valves in drain lines to the      Refer to item 9 in this table. Refer to item 9 in this table.
containment sump limit cross flooding of compartments.
444  2.3.10.07a.i  7.a) The WLS provides the nonsafety-        i) Inspection will be performed    i) Nonsafety-related displays related function of detecting leaks          for retrievability of the displays of WLS containment sump within containment to the containment        of containment sump level          level channels WLS-LT-034, sump.                                        channels WLS-LT-034,              WLS-LT-035, and WLS-LT-035, and WLS-LT-036        WLS-LT-036 can be retrieved in the MCR.                        in the MCR.
445  2.3.10.07a.ii 7.a) The WLS provides the nonsafety-        ii) Testing will be performed by  ii) A report exists and related function of detecting leaks          adding water to the sump and      concludes that sump level within containment to the containment        observing display of sump level. channels WLS-LT-034, sump.                                                                          WLS-LT-035, and WLS-LT-036 can detect a change of 1.75 +/- 0.1 inches.
446  2.3.10.07b  7.b) The WLS provides the nonsafety-        Tests will be performed to        A simulated high radiation related function of controlling releases    confirm that a simulated high      signal causes the discharge of radioactive materials in liquid          radiation signal from the          control isolation valve effluents.                                  discharge radiation monitor,      WLS-PL-V223 to close.
WLS-RE-229, causes the discharge isolation valve WLS-PL-V223 to close.
447    2.3.10.08  8. Controls exist in the MCR to cause        Stroke testing will be performed  Controls in the MCR operate the remotely operated valve identified      on the remotely operated valve    to cause the remotely operated in Table 2.3.10-3 to perform its active      listed in Table 2.3.10-3 using    valve to perform its active function.                                    controls in the MCR.              function.
448    2.3.10.09  9. The check valves identified in            Exercise testing of the check      Each check valve changes Table 2.3.10-1 perform an active safety-    valves with active safety          position as indicated on related function to change position as      functions identified in            Table 2.3.10-1.
indicated in the table.                      Table 2.3.10-1 will be performed under pre-operational test pressure, temperature and flow conditions.
C-262
 
Table 2.3.10-4 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No.              Design Commitment                    Inspections, Tests, Analyses            Acceptance Criteria 449  2.3.10.10  10. Displays of the parameters              Inspection will be performed for    Displays identified in identified in Table 2.3.10-3 can be          retrievability of the displays      Table 2.3.10-3 can be retrieved in the MCR.                        identified in Table 2.3.10-3 in      retrieved in the MCR.
the MCR.
Table 2.3.10-5 Component Name                                  Tag No.                  Component Location WLS Reactor Coolant Drain Tank                            WLS-MT-01                      Containment WLS Containment Sump                                      WLS-MT-02                      Containment WLS Degasifier Column                                    WLS-MV-01                    Auxiliary Building WLS Effluent Holdup Tanks                                WLS-MT-05A                    Auxiliary Building WLS-MT-05B WLS Waste Holdup Tanks                                  WLS-MT-06A                    Auxiliary Building WLS-MT-06B WLS Waste Pre-Filter                                      WLS-MV-06                    Auxiliary Building WLS Ion Exchangers                                        WLS-MV-03                    Auxiliary Building WLS-MV-04A WLS-MV-04B WLS-MV-04C WLS Waste After-Filter                                    WLS-MV-07                    Auxiliary Building WLS Monitor Tanks                                        WLS-MT-07A                    Auxiliary Building WLS-MT-07B WLS-MT-07C WLS-MT-07D                    Radwaste Building WLS-MT-07E WLS-MT-07F C-263
 
Figure 2.3.10-1 Liquid Radwaste System C-264
 
2.3.11        Gaseous Radwaste System Design Description The gaseous radwaste system (WGS) receives, processes, and discharges the radioactive waste gases received within acceptable off-site release limits during normal modes of plant operation including power generation, shutdown and refueling.
The WGS is as shown in Figure 2.3.11-1 and the component locations of the WGS are as shown in Table 2.3.11-3.
: 1. The functional arrangement of the WGS is as described in the Design Description of this Section 2.3.11.
: 2. The equipment identified in Table 2.3.11-1 can withstand the appropriate seismic design basis loads without loss of its structural integrity function.
: 3. The WGS provides the nonsafety-related functions of:
: a. Processing radioactive gases prior to discharge.
: b. Controlling the releases of radioactive materials in gaseous effluents.
: c. The WGS is purged with nitrogen on indication of high oxygen levels in the system.
Table 2.3.11-1 Seismic Equipment Name                                  Tag No.                    Category I WGS Activated Carbon Delay Bed A                          WGS-MV-02A                        No(1)
WGS Activated Carbon Delay Bed B                          WGS-MV-02B                        No(1)
WGS Discharge Isolation Valve                              WGS-PL-V051                        No Note:
: 1. The WGS activated carbon delay beds (WGS-MV-02A and B) are designed to one-half SSE.
Table 2.3.11-2 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No.              Design Commitment                  Inspections, Tests, Analyses        Acceptance Criteria 450  2.3.11.01  1. The functional arrangement of the        Inspection of the as-built system The as-built WGS conforms WGS is as described in the Design          will be performed.                with the functional Description of this Section 2.3.11.                                          arrangement as described in the Design Description of this Section 2.3.11.
C-265
 
Table 2.3.11-2 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No.              Design Commitment                    Inspections, Tests, Analyses        Acceptance Criteria 451  2.3.11.02.i  2. The equipment identified as having        i) Inspection will be performed  i) The equipment identified as seismic design requirements in              to verify that the equipment      having seismic design Table 2.3.11-1 can withstand seismic        identified as having seismic      requirements in Table 2.3.11-1 design basis loads without loss of its      design requirements in            is located on the Nuclear structural integrity function.              Table 2.3.11-1 is located on the  Island.
Nuclear Island.
452  2.3.11.02.ii 2. The equipment identified as having        ii) Type tests, analyses, or a    ii) A report exists and seismic design requirements in              combination of type tests and    concludes that the seismically Table 2.3.11-1 can withstand seismic        analyses of seismically designed  designed equipment can design basis loads without loss of its      equipment will be performed.      withstand appropriate seismic structural integrity function.                                                design basis loads without loss of its structural integrity function.
453  2.3.11.02.iii 2. The equipment identified as having        iii) Inspection will be performed iii) A report exists and seismic design requirements in              for the existence of a report    concludes that the as-built Table 2.3.11-1 can withstand seismic        verifying that the as-built      equipment including design basis loads without loss of its      equipment including anchorage    anchorage is seismically structural integrity function.              is seismically bounded by the    bounded by the tested or tested or analyzed conditions. analyzed conditions.
454  2.3.11.03a  3.a) The WGS provides the nonsafety-        Inspection will be performed to  A report exists and concludes related function of processing              verify the contained volume of    that the contained volume in radioactive gases prior to discharge.        each of the activated carbon      each of the activated carbon delay beds, WGS-MV02A and        delay beds, WGS-MV02A and WGS-MV02B.                        WGS-MV02B, is at least 80 ft3.
455  2.3.11.03b  3.b) The WGS provides the nonsafety-        Tests will be performed to        A simulated high radiation related function of controlling the          confirm that the presence of a    signal causes the discharge releases of radioactive materials in        simulated high radiation signal  control isolation valve gaseous effluents.                          from the discharge radiation      WGS-PL-V051 to close.
monitor, WGS-017, causes the discharge control isolation valve WGS-PL-V051 to close.
456  2.3.11.03c  3.c) The WGS is purged with nitrogen        Tests will be performed to        A simulated high oxygen level on indication of high oxygen levels in      confirm that the presence of a    signal causes the nitrogen the system.                                  simulated high oxygen level      purge valve (WGS-PL-V002) signal from the oxygen monitors  to open and the WLS (WGS-025A, -025B) causes          degasifier vacuum pumps the nitrogen purge valve          (WLS-MP-03A, -03B) to stop.
(WGS-PL-V002) to open and the WLS degasifier vacuum pumps (WLS-MP-03A, -03B) to stop.
C-266
 
Table 2.3.11-3 Equipment Name                Tag No. Component Location WGS Gas Cooler                        WGS-ME-01  Auxiliary Building WGS Moisture Separator                WGS-MV-03  Auxiliary Building WGS Activated Carbon Delay Bed A    WGS-MV-02A  Auxiliary Building WGS Activated Carbon Delay Bed B      WGS-MV-02B  Auxiliary Building C-267
 
Figure 2.3.11-1 Gaseous Radwaste System C-268
 
2.3.12          Solid Radwaste System Design Description The solid radwaste system (WSS) receives, collects, and stores the solid radioactive wastes received prior to their processing and packaging by mobile equipment for shipment off-site.
The component locations of the WSS are as shown in Table 2.3.12-2.
: 1. The functional arrangement of the WSS is as described in the Design Description of this Section 2.3.12.
: 2. The WSS provides the nonsafety-related function of storing radioactive spent resins prior to processing or shipment.
Table 2.3.12-1 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No.              Design Commitment                    Inspections, Tests, Analyses            Acceptance Criteria 457  2.3.12.01  1. The functional arrangement of the        Inspection of the as-built system  The as-built WSS conforms WSS is as described in the Design            will be performed.                  with the functional Description of this Section 2.3.12.                                              arrangement as described in the Design Description of this Section 2.3.12.
458  2.3.12.02  2. The WSS provides the nonsafety-          Inspection will be performed to    A report exists and concludes related function of storing radioactive      verify that the volume of each of  that the volume of each of the solids prior to processing or shipment.      the spent resin tanks,              spent resin tanks, WSS-WSS-MV01A and                      MV01A and WSS-MV01B, is WSS-MV01B, is at least 250 ft3. at least 250 ft3.
Table 2.3.12-2 Component Name                                    Tag No.                  Component Location WSS Spent Resin Tank A                                      WSS-MV-01A                    Auxiliary Building WSS Spent Resin Tank B                                      WSS-MV-01B                    Auxiliary Building C-269
 
2.3.13            Primary Sampling System Design Description The primary sampling system collects samples of fluids in the reactor coolant system (RCS) and the containment atmosphere during normal operations.
The PSS is as shown in Figure 2.3.13-1. The PSS Grab Sampling Unit (PSS-MS-01) is located in the Auxiliary Building.
: 1. The functional arrangement of the PSS is as described in the Design Description of this Section 2.3.13.
: 2. The components identified in Table 2.3.13-1 as ASME Code Section III are designed and constructed in accordance with ASME Code Section III requirements.
: 3. Pressure boundary welds in components identified in Table 2.3.13-1 as ASME Code Section III meet ASME Code Section III requirements.
: 4. The components identified in Table 2.3.13-1 as ASME Code Section III retain their pressure boundary integrity at their design pressure.
: 5. The seismic Category I equipment identified in Table 2.3.13-1 can withstand seismic design basis loads without loss of safety function.
: 6. a) The Class 1E equipment identified in Table 2.3.13-1 as being qualified for a harsh environment can withstand the environmental conditions that would exist before, during, and following a design basis accident without loss of their safety function, for the time required to perform the safety function.
b) The Class 1E components identified in Table 2.3.13-1 are powered from their respective Class 1E division.
c) Separation is provided between PSS Class 1E divisions, and between Class 1E divisions and non-Class 1E divisions.
: 7. The PSS provides the safety-related function of preserving containment integrity by isolation of the PSS lines penetrating the containment.
: 8. The PSS provides the nonsafety-related function of providing the capability of obtaining reactor coolant and containment atmosphere samples.
: 9. Safety-related displays identified in Table 2.3.13-1 can be retrieved in the MCR.
: 10. a) Controls exist in the MCR to cause those remotely operated valves identified in Table 2.3.13-1 to perform active functions.
b) The valves identified in Table 2.3.13-1 as having protection and safety monitoring system (PMS) control perform an active function after receiving a signal from the PMS.
: 11. a) The check valve identified in Table 2.3.13-1 perform an active safety-related function to change position as indicated in the table.
C-270
 
b) After loss of motive power, the remotely operated valves identified in Table 2.3.13-1 assume the indicated loss of motive power position.
: 12. Controls exist in the MCR to cause the valves identified in Table 2.3.13-2 to perform the listed function.
C-271
 
Table 2.3.13-1 ASME                          Class 1E/                            Loss of Code          Remotely      Qual. for  Safety-                    Motive Section Seismic Operated        Harsh    Related    Control  Active  Power Equipment Name            Tag No.          III  Cat. I  Valve        Envir. Display  PMS/DAS  Function Position Liquid Sample Line        PSS-PL-V011          Yes    Yes      Yes          Yes/No    Yes      Yes/No  Transfer  Closed Containment Isolation                                                                  (Valve            Closed Valve Outside Reactor                                                                Position)
Containment (ORC)
Liquid Sample Line          PSS-PL-            Yes    Yes      Yes          Yes/Yes    Yes      Yes/No  Transfer  Closed Containment Isolation        V010A                                                    (Valve            Closed Valve Inside Reactor                                                                  Position)
Containment (IRC)
Liquid Sample Line          PSS-PL-            Yes    Yes      Yes          Yes/Yes    Yes      Yes/No  Transfer  Closed Containment Isolation        V010B                                                    (Valve            Closed Valve IRC                                                                            Position)
Containment Air            PSS-PL-V008          Yes    Yes      Yes          Yes/Yes    Yes      Yes/No  Transfer  Closed Sample Containment                                                                    (Valve            Closed Isolation Valve IRC                                                                  Position)
Air Sample Line            PSS-PL-V046          Yes    Yes      Yes          Yes/No    Yes      Yes/No  Transfer  Closed Containment Isolation                                                                  (Valve            Closed Valve ORC                                                                            Position)
Sample Return Line        PSS-PL-V023          Yes    Yes      Yes          Yes/No    Yes      Yes/No  Transfer  Closed Containment Isolation                                                                  (Valve            Closed Valve ORC                                                                            Position)
Sample Return              PSS-PL-V024          Yes    Yes      No            -/-      No        -/-  Transfer  Closed Containment Isolation                                                                                    Closed Check Valve IRC Note: A dash (-) indicates not applicable.
C-272
 
Table 2.3.13-2 Equipment Name                              Tag No.                            Control Function Hot Leg 1 Sample Isolation Valve                  PSS-PL-V001A                  Transfer Open/Transfer Closed Hot Leg 2 Sample Isolation Valve                  PSS-PL-V001B                  Transfer Open/Transfer Closed Table 2.3.13-3 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No.                Design Commitment                    Inspections, Tests, Analyses            Acceptance Criteria 459    2.3.13.01    1. The functional arrangement of the        Inspection of the as-built system    The as-built PSS conforms PSS is as described in the Design            will be performed.                  with the functional Description of this Section 2.3.13.                                              arrangement as described in the Design Description of this Section 2.3.13.
460    2.3.13.02    2. The components identified in Table        Inspection will be conducted of      The ASME Code Section III 2.3.13-1 as ASME Code Section III are        the as-built components as          design reports exist for the as-designed and constructed in accordance      documented in the ASME design        built components identified in with ASME Code Section III                  reports.                            Table 2.3.13-1 as ASME Code requirements.                                                                    Section III.
461    2.3.13.03    3. Pressure boundary welds in                Inspection of the as-built          A report exists and concludes components identified in Table 2.3.13-1      pressure boundary welds will be      that the ASME Code Section as ASME Code Section III meet ASME          performed in accordance with        III requirements are met for Code Section III requirements.              the ASME Code Section III.          non-destructive examination of pressure boundary welds.
462    2.3.13.04    4. The components identified in Table        A hydrostatic test will be          A report exists and concludes 2.3.13-1 as ASME Code Section III            performed on the components          that the results of the retain their pressure boundary integrity    required by the ASME Code            hydrostatic test of the at their design pressure.                    Section III to be hydrostatically    components identified in tested.                              Table 2.3.13-1 as ASME Code Section III conform with the requirements of the ASME Code Section III.
463  2.3.13.05.i    5. The seismic Category I equipment          i) Inspection will be performed      i) The seismic Category I identified in Table 2.3.13-1 can            to verify that the seismic          equipment identified in withstand seismic design basis loads        Category I equipment and valves      Table 2.3.13-1 is located on without loss of its safety function.        identified in Table 2.3.13-1 are    the Nuclear Island.
located on the Nuclear Island.
464  2.3.13.05.ii  5. The seismic Category I equipment          ii) Type tests, analyses, or a      ii) A report exists and identified in Table 2.3.13-1 can            combination of type tests and        concludes that the seismic withstand seismic design basis loads        analyses of seismic Category I      Category I equipment can without loss of its safety function.        equipment will be performed.        withstand seismic design basis loads without loss of safety function.
C-273
 
Table 2.3.13-3 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No.              Design Commitment                    Inspections, Tests, Analyses        Acceptance Criteria 465  2.3.13.05.iii 5. The seismic Category I equipment          iii) Inspection will be performed iii) A report exists and identified in Table 2.3.13-1 can            for the existence of a report    concludes that the as-built withstand seismic design basis loads        verifying that the as-built      equipment including without loss of its safety function.        equipment including anchorage    anchorage is seismically is seismically bounded by the    bounded by the tested or tested or analyzed conditions. analyzed conditions.
466  2.3.13.06a.i  6.a) The Class 1E equipment identified      i) Type tests, analyses, or a    i) A report exists and in Tables 2.3.13-1 as being qualified for    combination of type tests and    concludes that the Class 1E a harsh environment can withstand the        analyses will be performed on    equipment identified in environmental conditions that would          Class 1E equipment located in a  Table 2.3.13-1 as being exist before, during, and following a        harsh environment.                qualified for a harsh design basis accident without loss of                                          environment can withstand the their safety function, for the time                                            environmental conditions that required to perform the safety function.                                      would exist before, during, and following a design basis accident without loss of its safety function for the time required to perform the safety function.
467  2.3.13.06a.ii 6.a) The Class 1E equipment identified      ii) Inspection will be performed  ii) A report exists and in Tables 2.3.13-1 as being qualified for    of the as-built Class 1E          concludes that the as-built a harsh environment can withstand the        equipment and the associated      Class 1E equipment and the environmental conditions that would          wiring, cables, and terminations  associated wiring, cables, and exist before, during, and following a        located in a harsh environment. terminations identified in design basis accident without loss of                                          Table 2.3.13-1 as being their safety function, for the time                                            qualified for a harsh required to perform the safety function.                                      environment are bounded by type tests, analyses, or a combination of type tests and analyses.
468  2.3.13.06b  6.b) The Class 1E components                Testing will be performed on the  A simulated test signal exists identified in Table 2.3.13-1 are powered    PSS by providing a simulated      at the Class 1E equipment from their respective Class 1E division. test signal in each Class 1E      identified in Table 2.3.13-1 division.                        when the assigned Class 1E division is provided the test signal.
469  2.3.13.06c  6.c) Separation is provided between          See ITAAC Table 3.3-6,            See ITAAC Table 3.3-6, PSS Class 1E divisions, and between          item 7.d.                        item 7.d.
Class 1E divisions and non-Class 1E divisions.
470    2.3.13.07  7. The PSS provides the safety- related      See ITAAC Table 2.2.1-3,          See ITAAC Table 2.2.1-3, function of preserving containment          item 7.                          item 7.
integrity by isolation of the PSS lines penetrating the containment.
C-274
 
Table 2.3.13-3 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No.            Design Commitment                    Inspections, Tests, Analyses          Acceptance Criteria 471    2.3.13.08 8. The PSS provides the nonsafety-          Testing will be performed to      A sample is drawn from the related function of providing the            obtain samples of the reactor      reactor coolant and the capability of obtaining reactor coolant      coolant and containment            containment atmosphere.
and containment atmosphere samples.          atmosphere.
472    2.3.13.09 9. Safety-related displays identified in    Inspection will be performed for  The safety-related displays Table 2.3.13-1 can be retrieved in the      retrievability of the safety-      identified in Table 2.3.13-1 MCR.                                        related displays in the MCR.      can be retrieved in the MCR.
473  2.3.13.10a 10.a) Controls exist in the MCR to          Stroke testing will be performed  Controls in the MCR operate cause those remotely operated valves        on the remotely operated valves    to cause those remotely identified in Table 2.3.13-1 to perform      identified in Table 2.3.13-1 using operated valves identified in active functions.                            the controls in the MCR.          Table 2.3.13-1 to perform active functions.
474  2.3.13.10b 10.b) The valves identified in              Testing will be performed on      The remotely operated valves Table 2.3.13-1 as having PMS control        remotely operated valves listed    identified in Table 2.3.13-1 as perform an active function after            in Table 2.3.13-1 using real or    having PMS control perform the receiving a signal from the PMS.            simulated signals into the PMS. active function identified in the table after receiving a signal from the PMS.
475  2.3.13.11a 11.a) The check valve identified in          Exercise testing of the check      The check valve changes Table 2.3.13-1 performs an active            valve with an active safety        position as indicated in safety-related function to change            function identified in            Table 2.3.13-1.
position as indicated in the table.          Table 2.3.13-1 will be performed under preoperational test pressure, temperature, and fluid flow conditions.
476  2.3.13.11b 11.b) After loss of motive power, the        Testing of the remotely operated  After loss of motive power, remotely operated valves identified in      valves will be performed under    each remotely operated valve Table 2.3.13-1 assume the indicated loss    the conditions of loss of motive  identified in Table 2.3.13-1 of motive power position.                    power.                            assumes the indicated loss of motive power position.
477    2.3.13.12 12. Controls exist in the MCR to cause      Testing will be performed on the  Controls in the MCR cause the valves identified in Table 2.3.13-2      components in Table 2.3.13-2      valves identified in to perform the listed function.              using controls in the MCR.        Table 2.3.13-2 to perform the listed functions.
C-275
 
Figure 2.3.13-1 Primary Sampling System C-276
 
2.3.14          Demineralized Water Transfer and Storage System Design Description The demineralized water transfer and storage system (DWS) receives water from the demineralized water treatment system (DTS), and provides a reservoir of demineralized water to supply the condensate storage tank and for distribution throughout the plant. Demineralized water is processed in the DWS to remove dissolved oxygen. In addition to supplying water for makeup of systems which require pure water, the demineralized water is used to sluice spent radioactive resins from the ion exchange vessels in the chemical and volume control system (CVS), the spent fuel pool cooling system (SFS), and the liquid radwaste system (WLS) to the solid radwaste system (WSS).
The component locations of the DWS are as shown in Table 2.3.14-3.
: 1. The functional arrangement of the DWS is as described in the Design Description of this Section 2.3.14.
: 2. The DWS provides the safety-related function of preserving containment integrity by isolation of the DWS lines penetrating the containment.
: 3. The DWS condensate storage tank (CST) provides the nonsafety-related function of water supply to the FWS startup feedwater pumps.
: 4. Displays of the parameters identified in Table 2.3.14-1 can be retrieved in the main control room (MCR).
Table 2.3.14-1 Equipment Name                  Tag No.        Display        Control Function Condensate Storage Tank Water Level            DWS-006            Yes                  -
Note: Dash (-) indicates not applicable.
C-277
 
Table 2.3.14-2 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No.                Design Commitment                    Inspections, Tests, Analyses            Acceptance Criteria 478  2.3.14.01    1. The functional arrangement of the        Inspection of the as-built system    The as-built DWS conforms DWS is as described in the Design            will be performed.                  with the functional Description of this Section 2.3.14.                                              arrangement as described in the Design Description of this Section 2.3.14.
479  2.3.14.02    2. The DWS provides the safety-related      See ITAAC Table 2.2.1-3,            See ITAAC Table 2.2.1-3, function of preserving containment          items 1 and 7.                      items 1 and 7.
integrity by isolation of the DWS lines penetrating the containment.
480  2.3.14.03    3. The DWS CST provides the                  Inspection of the DWS CST will      The volume of the CST nonsafety-related function of water          be performed.                        between the tank overflow and supply to the FWS startup feedwater                                              the startup feedwater pumps tanks.                                                                            supply connection is greater than or equal to 325,000 gallons.
481  2.3.14.04    4. Displays of the parameters identified    Inspection will be performed for    The displays identified in in Table 2.3.14-1 can be retrieved in the    retrievability or parameters in      Table 2.3.14-1 can be MCR.                                        the MCR.                            retrieved in the MCR.
Table 2.3.14-3 Component Name                              Tag No.                        Component Location Demineralizer Water Storage Tank                      DWS-MS-01                            Annex Building Degasification System Package Condensate Storage Tank Degasification                DWS-MS-02                          Turbine Building System Package Demineralized Water Storage Tank                      DWS-MT-01                                Yard Condensate Storage Tank                              DWS-MT-02                                Yard C-278
 
2.3.15          Compressed and Instrument Air System Design Description The compressed and instrument air system (CAS) consists of three subsystems: instrument air, service air, and high-pressure air. The instrument air subsystem supplies compressed air for air-operated valves and dampers. The service air subsystem supplies compressed air at outlets throughout the plant to power air-operated tools and is used as a motive force for air-powered pumps. The service air subsystem is also utilized as a supply source for breathing air. The high-pressure air subsystem supplies air to the main control room emergency habitability system (VES), the generator breaker package, and fire fighting apparatus recharge station.
The CAS is required for normal operation and startup of the plant.
The component locations of the CAS are as shown in Table 2.3.15-3.
: 1. The functional arrangement of the CAS is as described in the Design Description of this Section 2.3.15.
: 2. The CAS provides the safety-related function of preserving containment integrity by isolation of the CAS lines penetrating the containment.
: 3. Displays of the parameters identified in Table 2.3.15-1 can be retrieved in the main control room (MCR).
Table 2.3.15-1 Equipment Name                  Tag No.        Display        Control Function Instrument Air Pressure                        CAS-011          Yes                  -
Note: Dash (-) indicates not applicable.
C-279
 
Table 2.3.15-2 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No.                Design Commitment                    Inspections, Tests, Analyses            Acceptance Criteria 482  2.3.15.01    1. The functional arrangement of the        Inspection of the as-built system    The as-built CAS conforms CAS is as described in the Design            will be performed.                  with the functional Description of this Section 2.3.15.                                              arrangement as described in the Design Description of this Section 2.3.15.
483  2.3.15.02    2. The CAS provides the safety-related      See ITAAC Table 2.2.1-3,            See ITAAC Table 2.2.1-3, function of preserving containment          items 1 and 7.                      items 1 and 7.
integrity by isolation of the CAS lines penetrating the containment.
484  2.3.15.03    3. Displays of the parameters identified    Inspection will be performed for    The displays identified in in Table 2.3.15-1 can be retrieved in the    retrievability of parameters in      Table 2.3.15-1 can be MCR.                                        the MCR.                            retrieved in the MCR.
Table 2.3.15-3 Component Name                                Tag No.                    Component Location Instrument Air Compressor Package A                    CAS-MS-01A                        Turbine Building Instrument Air Compressor Package B                    CAS-MS-01B                        Turbine Building Instrument Air Dryer Package A                          CAS-MS-02A                        Turbine Building Instrument Air Dryer Package B                          CAS-MS-02B                        Turbine Building Service Air Compressor Package A                        CAS-MS-03A                        Turbine Building Service Air Compressor Package B                        CAS-MS-03B                        Turbine Building Service Air Dryer Package A                            CAS-MS-04A                        Turbine Building Service Air Dryer Package B                            CAS-MS-04B                        Turbine Building High Pressure Air Compressor and Filter                  CAS-MS-05                        Turbine Building Package Instrument Air Receiver A                              CAS-MT-01A                        Turbine Building Instrument Air Receiver B                              CAS-MT-01B                        Turbine Building Service Air Receiver                                    CAS-MT-02                        Turbine Building C-280
 
2.3.16          Potable Water System No entry for this system.
2.3.17          Waste Water System No entry for this system.
2.3.18          Plant Gas System No entry. Covered in Section 3.3, Buildings.
2.3.19          Communication System Design Description The communication system (EFS) provides intraplant communications during normal, maintenance, transient, fire, and accident conditions, including loss of offsite power.
: 1. a) The EFS has handsets, amplifiers, loudspeakers, and siren tone generators connected as a telephone/page system.
b) The EFS has sound-powered equipment connected as a system.
: 2. The EFS provides the following nonsafety-related functions:
a) The EFS telephone/page system provides intraplant, station-to-station communications and area broadcasting between the main control room (MCR) and the locations listed in Table 2.3.19-1.
b) The EFS provides sound-powered communications between the MCR, the remote shutdown workstation (RSW), the Division A, B, C, D dc equipment rooms (Rooms 12201/12203/12205/12207), the Division A, B, C, D I&C rooms (Rooms 12301/12302/12304/12305), and the diesel generator building (Rooms 60310/60320) without external power.
C-281
 
Table 2.3.19-1 Telephone/Page System Equipment                                            Location Fuel Handling Area                                                                          12562 Division A, B, C, D dc Equipment Rooms                                          12201/12203/12205/12207 Division A, B, C, D I&C Rooms                                                    12301/12302/12304/12305 Maintenance Floor Staging Area                                                              12351 Containment Maintenance Floor                                                              11300 Containment Operating Deck                                                                  11500 Table 2.3.19-2 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No.                Design Commitment                    Inspections, Tests, Analyses            Acceptance Criteria 485  2.3.19.01a    1.a) The EFS has handsets, amplifiers,        Inspection of the as-built system    The as-built EFS has handsets, loudspeakers, and siren tone generators      will be performed.                  amplifiers, loudspeakers, and connected as a telephone/page system.                                              siren tone generators connected as a telephone/page system.
486  2.3.19.01b    1.b) The EFS has sound-powered                Inspection of the as-built system    The as-built EFS has sound-equipment connected as a system.              will be performed.                  powered equipment connected as a system.
487  2.3.19.02a    2.a) The EFS telephone/page system            An inspection and test will be      Telephone/page equipment is provides intraplant, station-to-station      performed on the telephone/page      installed and voice communications and area broadcasting          communication equipment.            transmission and reception between the MCR and the locations                                                  from the MCR are listed in Table 2.3.19-1.                                                          accomplished.
488  2.3.19.02b    2.b) EFS provides sound-powered              An inspection and test will be      Sound-powered equipment is communications between the MCR, the          performed of the sound-powered      installed and voice RSW, the Division A, B, C, D dc              communication equipment.            transmission and reception are equipment rooms                                                                    accomplished.
(Rooms 12201/12203/12205/ 12207),
the Division A, B, C, D I&C rooms (Rooms 12301/12302/ 12304/12305),
and the diesel generator building (Rooms 60310/60320) without external power.
C-282
 
2.3.20          Turbine Building Closed Cooling Water System No entry for this system.
2.3.21          Secondary Sampling System No entry for this system.
2.3.22          Containment Leak Rate Test System No entry. Covered in Section 2.2.1, Containment System.
2.3.23          This section intentionally blank 2.3.24          Demineralized Water Treatment System No entry for this system.
2.3.25          Gravity and Roof Drain Collection System No entry for this system.
2.3.26          This section intentionally blank 2.3.27          Sanitary Drainage System No entry for this system.
2.3.28          Turbine Island Vents, Drains, and Relief System No entry for this system.
C-283
 
2.3.29          Radioactive Waste Drain System Design Description The radioactive waste drain system (WRS) collects radioactive and potentially radioactive liquid wastes from equipment and floor drains during normal operation, startup, shutdown, and refueling. The liquid wastes are then transferred to appropriate processing and disposal systems.
Nonradioactive wastes are collected by the waste water system (WWS). The WRS is as shown in Figure 2.3.29-1.
: 1. The functional arrangement of the WRS is as described in the Design Description of this Section 2.3.29.
: 2. The WRS collects liquid wastes from the equipment and floor drainage of the radioactive portions of the auxiliary building, annex building, and radwaste building and directs these wastes to a WRS sump or WLS waste holdup tanks located in the auxiliary building.
: 3. The WRS collects chemical wastes from the auxiliary building chemical laboratory drains and the decontamination solution drains in the annex building and directs these wastes to the chemical waste tank of the liquid radwaste system.
: 4. The WWS stops the discharge from the turbine building sump upon detection of high radiation in the discharge stream to the oil separator.
C-284
 
Table 2.3.29-1 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No.            Design Commitment                  Inspections, Tests, Analyses        Acceptance Criteria 489  2.3.29.01 1. The functional arrangement of the        Inspection of the as-built system The as-built WRS conforms WRS is as described in the Design          will be performed.                with the functional Description of this Section 2.3.29.                                          arrangement as described in the Design Description of this Section 2.3.29.
490  2.3.29.02 2. The WRS collects liquid wastes from      A test is performed by pouring    The water poured into these the equipment and floor drainage of the    water into the equipment and      drains is collected either in the radioactive portions of the auxiliary      floor drains in the radioactive  auxiliary building radioactive building, annex building, and radwaste      portions of the auxiliary        drains sump or the WLS waste building and directs these wastes to a      building, annex building, and    holdup tanks.
WRS sump or WLS waste holdup tanks          radwaste building.
located in the auxiliary building.
491  2.3.29.03 3. The WRS collects chemical wastes        A test is performed by pouring    The water poured into these from the auxiliary building chemical        water into the auxiliary building drains is collected in the laboratory drains and the                  chemical laboratory and the      chemical waste tank of the decontamination solution drains in the      decontamination solution drains  liquid radwaste system.
annex building and directs these wastes    in the annex building.
to the chemical waste tank of the liquid radwaste system.
492  2.3.29.04 4. The WWS stops the discharge from        Tests will be performed to        A simulated high radiation the turbine building sump upon              confirm that a simulated high    signal causes the turbine detection of high radiation in the          radiation signal from the turbine building sump pumps discharge stream to the oil separator.      building sump discharge          (WWS-MP-01A and B) to radiation monitor, WWS-021        stop operating, stopping the causes the sump pumps            spread of radiation outside of (WWS-MP-01A and B) to stop        the turbine building.
operating, stopping the spread of radiation outside of the turbine building.
C-285
 
Figure 2.3.29-1 Radioactive Waste Drain System C-286
 
2.3.30          Storm Drain System No entry for this system.
2.3.31          Raw Water System No entry for this system.
2.3.32          Yard Fire Water System No entry for this system.
C-287
 
2.4              Steam and Power Conversion Systems 2.4.1            Main and Startup Feedwater System See Section 2.2.4 for information on the main feedwater system.
Design Description The startup feedwater system supplies feedwater to the steam generators during plant startup, hot standby and shutdown conditions, and during transients in the event of main feedwater system unavailability.
: 1. The functional arrangement of the startup feedwater system is as described in the Design Description of this Section 2.4.1.
: 2. The FWS provides the following nonsafety-related functions:
The FWS provides startup feedwater flow from the condensate storage tank (CST) to the steam generator system (SGS) for heat removal from the RCS.
: 3. Controls exist in the main control room (MCR) to cause the components identified in Table 2.4.1-1 to perform the listed function.
: 4. Displays of the parameters identified in Table 2.4.1-1 can be retrieved in the MCR.
Table 2.4.1-1 Equipment Name                    Tag No.        Display        Control Function Startup Feedwater Pump A (Motor)      FWS-MP-03A          Yes                Start (Run Status)
Startup Feedwater Pump B (Motor)      FWS-MP-03B          Yes                Start (Run Status)
Startup Feedwater Pump A Isolation Valve  FWS-PL-V013A          Yes                Open (Valve Position)
Startup Feedwater Pump B Isolation Valve  FWS-PL-V013B          Yes                Open (Valve Position)
C-288
 
Table 2.4.1-2 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No.              Design Commitment                  Inspections, Tests, Analyses            Acceptance Criteria 493  2.4.01.01    1. The functional arrangement of the        Inspection of the as-built system    The as-built startup feedwater startup feedwater system is as described    will be performed.                  system conforms with the in the Design Description of this                                                functional arrangement as Section 2.4.1.                                                                  described in the Design Description of this Section 2.4.1.
494  2.4.01.02    2. The FWS provides startup feedwater      Testing will be performed to        Each FWS startup feedwater flow from the CST to the SGS for heat      confirm that each of the startup    pump provides a flow rate removal from the RCS.                      feedwater pumps can provide          greater than or equal to water from the CST to both          260 gpm to each steam steam generators.                    generator system at a steam generator secondary side pressure of at least 1106 psia.
495  2.4.01.03    3. Controls exist in the MCR to cause      Testing will be performed on the    Controls in the MCR operate the components identified in                components in Table 2.4.1-1          to cause the components listed Table 2.4.1-1 to perform the listed        using controls in the MCR.          in Table 2.4.1-1 to perform the function.                                                                        listed functions.
496  2.4.01.04    4. Displays of the parameters identified    Inspection will be performed for    The displays identified in in Table 2.4.1-1 can be retrieved in the    retrievability of parameters in      Table 2.4.1-1 can be retrieved MCR.                                        the MCR.                            in the MCR.
Table 2.4.1-3 Component Name                              Tag No.                      Component Location Startup Feedwater Pump A                            FWS-MP-03A                          Turbine Building Startup Feedwater Pump B                            FWS-MP-03B                          Turbine Building C-289
 
Figure 2.4.1-1 Main and Startup Feedwater System C-290
 
2.4.2              Main Turbine System Design Description The main turbine system (MTS) is designed for electric power production consistent with the capability of the reactor and the reactor coolant system.
The component locations of the MTS are as shown in Table 2.4.2-2.
: 1. The functional arrangement of the MTS is as described in the Design Description of this Section 2.4.2.
: 2. a) Controls exist in the MCR to trip the main turbine-generator.
b) The main turbine-generator trips after receiving a signal from the PMS.
c) The main turbine-generator trips after receiving a signal from the DAS.
: 3. The overspeed trips for the AP1000 turbine are set for 110% and 111% (+/-1% each). Each trip is initiated electrically in separate systems. The trip signals from the two turbine electrical overspeed protection trip systems are isolated from, and independent of, each other.
Table 2.4.2-1 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No.                  Design Commitment                  Inspections, Tests, Analyses          Acceptance Criteria 497    2.4.02.01      1. The functional arrangement of the        Inspection of the as-built system  The as-built MTS conforms MTS is as described in the Design          will be performed.                with the functional Description of this Section 2.4.2.                                            arrangement as described in the Design Description of this Section 2.4.2.
498  2.4.02.02a      2.a) Controls exist in the MCR to trip      Testing will be performed on the  Controls in the MCR operate the main turbine-generator.                main turbine-generator using      to trip the main turbine-controls in the MCR.              generator.
499  2.4.02.02b      2.b) The main turbine-generator trips      Testing will be performed using    The main turbine-generator after receiving a signal from the PMS.      real or simulated signals into the trips after receiving a signal PMS.                              from the PMS.
500  2.4.02.02c      2.c) The main turbine-generator trips      Testing will be performed using    The main turbine-generator after receiving a signal from the DAS.      real or simulated signals into the trips after receiving a signal DAS.                              from the DAS.
501  2.4.02.03.i      3) The trip signals from the two turbine    i) The system design will be      i) The system design review electrical overspeed protection trip        reviewed.                          shows that the trip signals of systems are isolated from, and                                                the two electrical overspeed independent of, each other.                                                    protection trip systems are isolated from, and independent of, each other.
C-291
 
Table 2.4.2-1 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No.                Design Commitment                    Inspections, Tests, Analyses          Acceptance Criteria 502  2.4.02.03.ii  3) The trip signals from the two turbine    ii) Testing of the as-built system  ii) The main turbine-electrical overspeed protection trip        will be performed using              generator trips after overspeed systems are isolated from, and              simulated signals from the          signals are received from the independent of, each other.                turbine speed sensors.              speed sensors of the 110%
emergency electrical overspeed trip system, and the main turbine-generator trips after overspeed signals are received from the speed sensors of the 111% backup electrical overspeed trip system.
503  2.4.02.03.iii  3) The trip signals from the two turbine    iii) Inspection will be performed    iii) A report exists and electrical overspeed protection trip        for the existence of a report        concludes that the two systems are isolated from, and              verifying that the two turbine      electrical overspeed protection independent of, each other.                electrical overspeed protection      systems have diverse systems have diverse hardware        hardware and and software/firmware.              software/firmware.
Table 2.4.2-2 Component Name                                    Tag No.                      Component Location HP Turbine                                                MTS-MG-01                          Turbine Building LP Turbine A                                            MTS-MG-02A                          Turbine Building LP Turbine B                                            MTS-MG-02B                          Turbine Building LP Turbine C                                            MTS-MG-02C                          Turbine Building Gland Steam Condenser                                      GSS-ME-01                          Turbine Building Gland Condenser Vapor Exhauster 1A                      GSS-MA-01A                          Turbine Building Gland Condenser Vapor Exhauster 1B                      GSS-MA-01B                          Turbine Building Electrical Overspeed Trip Device                                --                          Turbine Building Emergency Electrical Overspeed                                  --                          Turbine Building Trip Device C-292
 
2.4.3        Main Steam System No entry. Covered in Section 2.2.4, Steam Generator System.
2.4.4        Steam Generator Blowdown System No entry. Containment isolation function covered in Section 2.2.1, Containment System and 2.2.4, Steam Generator System.
No entry. Steam generator isolation function covered in Section 2.2.4, Steam Generator System.
2.4.5        Condenser Air Removal System No entry. Covered in Section 3.5, Radiation Monitoring.
(Note: Monitor is TDS-RE001.)
C-293
 
2.4.6            Condensate System Design Description The condensate system (CDS) provides feedwater at the required temperature, pressure, and flow rate to the deaerator. Condensate is pumped from the main condenser hotwell by the condensate pumps and passes through the low-pressure feedwater heaters to the deaerator.
The circulating water system (CWS) removes heat from the condenser and is site specific starting from the interface at the locations where the CWS piping enters and exits the turbine building.
The CDS operates during plant startup and power operations (full and part loads).
The component locations of the CDS are as shown in Table 2.4.6-3.
: 1. The functional arrangement of the CDS is as described in the Design Description of this Section 2.4.6.
: 2. Displays of the parameters identified in Table 2.4.6-1 can be retrieved in the main control room (MCR).
Table 2.4.6-1 Equipment Name                                      Tag No.                    Display Condenser Backpressure                                              CDS-056A                      Yes Condenser Backpressure                                              CDS-056B                      Yes Condenser Backpressure                                              CDS-056C                      Yes Table 2.4.6-2 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No.              Design Commitment                    Inspections, Tests, Analyses        Acceptance Criteria 504    2.4.06.01    1. The functional arrangement of the        Inspection of the as-built system The as-built CDS conforms CDS is as described in the Design          will be performed.                with the functional Description of this Section 2.4.6.                                            arrangement as described in the Design Description of Section 2.4.6.
505    2.4.06.02    2. Displays of the parameters identified    Inspection will be performed for  The displays identified in in Table 2.4.6-1 can be retrieved in the    retrievability of the parameters  Table 2.4.6-1 can be retrieved MCR.                                        in the MCR.                      in the MCR.
C-294
 
Table 2.4.6-3 Component Name                    Component Location Low Pressure Feedwater Heaters                              Turbine Building Deaerator Feedwater Heater and Storage Tank                Turbine Building Main Condenser Shell A                                      Turbine Building Main Condenser Shell B                                      Turbine Building Main Condenser Shell C                                      Turbine Building Condensate Pump A                                          Turbine Building Condensate Pump B                                          Turbine Building Condensate Pump C                                          Turbine Building C-295
 
2.4.7          Circulating Water System No entry for this system.
2.4.8          Auxiliary Steam Supply System No entry for this system.
2.4.9          Condenser Tube Cleaning System No entry for this system.
2.4.10          Turbine Island Chemical Feed System No entry for this system.
2.4.11          Condensate Polishing System No entry for this system.
2.4.12          Gland Seal System No entry. Covered in Section 2.4.2, Main Turbine System.
2.4.13          Generator Hydrogen and CO2 System No entry for this system.
2.4.14          Heater Drain System No entry for this system.
2.4.15          Hydrogen Seal Oil System No entry for this system.
2.4.16          Main Turbine and Generator Lube Oil System No entry for this system.
C-296
 
2.5            Instrumentation and Control Systems 2.5.1          Diverse Actuation System Design Description The diverse actuation system (DAS) initiates reactor trip, actuates selected functions, and provides plant information to the operator.
The component locations of the DAS are as shown in Table 2.5.1-5.
: 1. The functional arrangement of the DAS is as described in the Design Description of this Section 2.5.1.
: 2. The DAS provides the following nonsafety-related functions:
a) The DAS provides an automatic reactor trip on low wide-range steam generator water level, or on low pressurizer water level, or on high hot leg temperature, separate from the PMS.
b) The DAS provides automatic actuation of selected functions, as identified in Table 2.5.1-1, separate from the PMS.
c) The DAS provides manual initiation of reactor trip and selected functions, as identified in Table 2.5.1-2, separate from the PMS. These manual initiation functions are implemented in a manner that bypasses the control room multiplexers, if any; the PMS cabinets; and the signal processing equipment of the DAS.
d) The DAS provides main control room (MCR) displays of selected plant parameters, as identified in Table 2.5.1-3, separate from the PMS.
: 3. The DAS has the following features:
a) The signal processing hardware of the DAS uses input modules, output modules, and microprocessor or special purpose logic processor boards that are different than those used in the PMS.
b) The display hardware of the DAS uses a different display device than that used in the PMS.
c) Software diversity between DAS and PMS will be achieved through the use of different algorithms, logic, program architecture, executable operating system, and executable software/logic.
d) The DAS has electrical surge withstand capability (SWC), and can withstand the electromagnetic interference (EMI), radio frequency (RFI), and electrostatic discharge (ESD) conditions that exist where the DAS equipment is located in the plant.
e) The sensors identified on Table 2.5.1-3 are used for DAS input and are separate from those being used by the PMS and plant control system.
f) The DAS is powered by non-Class 1E uninterruptible power supplies that are independent and separate from the power supplies which power the PMS.
C-297
 
g) The DAS signal processing cabinets are provided with the capability for channel testing without actuating the controlled components.
h) The DAS equipment can withstand the room ambient temperature and humidity conditions that will exist at the plant locations in which the DAS equipment is installed at the times for which the DAS is designed to be operational.
: 4. The DAS hardware and any software are developed using a planned design process which provides for specific design documentation and reviews during the following life cycle stages:
a) Development phase for hardware and any software b) System test phase c) Installation phase The planned design process also provides for the use of commercial off-the-shelf hardware and software.
: 5. The DAS manual actuation of ADS, IRWST injection, and containment recirculation can be executed correctly and reliably.
Table 2.5.1-1 Functions Automatically Actuated by the DAS
: 1. Reactor and Turbine Trip on Low Wide-range Steam Generator Water Level or Low Pressurizer Water Level or High Hot Leg Temperature
: 2. Passive Residual Heat Removal (PRHR) Actuation and In-containment Refueling Water Storage Tank (IRWST) Gutter Isolation on Low Wide-range Steam Generator Water Level or on High Hot Leg Temperature
: 3. Core Makeup Tank (CMT) Actuation and Trip All Reactor Coolant Pumps on Low Wide-Range Steam Generator Water Level or Low Pressurizer Water Level
: 4. Isolation of Selected Containment Penetrations and Initiation of Passive Containment Cooling System (PCS) on High Containment Temperature C-298
 
Table 2.5.1-2 Functions Manually Actuated by the DAS
: 1.      Reactor and Turbine Trip
: 2.      PRHR Actuation and IRWST Gutter Isolation
: 3.      CMT Actuation and Trip All Reactor Coolant Pumps
: 4.      First-stage Automatic Depressurization System (ADS) Valve Actuation
: 5.      Second-stage ADS Valve Actuation
: 6.      Third-stage ADS Valve Actuation
: 7.      Fourth-stage ADS Valve Actuation
: 8.      PCS Actuation
: 9.      Isolation of Selected Containment Penetrations
: 10.      Containment Hydrogen Ignitor Actuation
: 11.      IRWST Injection Actuation
: 12.      Containment Recirculation Actuation
: 13.      Actuate IRWST Drain to Containment Table 2.5.1-3 DAS Sensors and Displays Equipment Name                                    Tag Number Reactor Coolant System (RCS) Hot Leg Temperature                              RCS-300A RCS Hot Leg Temperature                                                      RCS-300B Steam Generator 1 Wide-range Level                                            SGS-044 Steam Generator 1 Wide-range Level                                            SGS-045 Steam Generator 2 Wide-range Level                                            SGS-046 Steam Generator 2 Wide-range Level                                            SGS-047 Pressurizer Water Level                                                      RCS-305A Pressurizer Water Level                                                      RCS-305B Containment Temperature                                                      VCS-053A Containment Temperature                                                      VCS-053B Core Exit Temperature                                                          IIS-009 Core Exit Temperature                                                          IIS-013 Core Exit Temperature                                                          IIS-030 Core Exit Temperature                                                          IIS-034 Rod Control Motor Generator Voltage                                          PLS-ET001 Rod Control Motor Generator Voltage                                          PLS-ET002 C-299
 
Table 2.5.1-4 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No.              Design Commitment                    Inspections, Tests, Analyses          Acceptance Criteria 506  2.5.01.01    1. The functional arrangement of the          Inspection of the as-built system  The as-built DAS conforms DAS is as described in the Design            will be performed.                with the functional Description of this Section 2.5.1.                                              arrangement as described in the Design Description of this Section 2.5.1.
507  2.5.01.02a  2.a) The DAS provides an automatic            Electrical power to the PMS        The field breakers of the reactor trip on low wide-range steam          equipment will be disconnected    control rod motor-generator generator water level, or on low              and an operational test of the as- sets open after the test signal pressurizer water level, or on high hot      built DAS will be performed        reaches the specified limit.
leg temperature, separate from the            using real or simulated test PMS.                                          signals.
508  2.5.01.02b  2.b) The DAS provides automatic              Electrical power to the PMS        Appropriate DAS output actuation of selected functions, as          equipment will be disconnected    signals are generated after the identified in Table 2.5.1-1, separate        and an operational test of the as- test signal reaches the from the PMS.                                built DAS will be performed        specified limit.
using real or simulated test signals.
509  2.5.01.02c.i  2.c) The DAS provides manual                  Electrical power to the control    i) The field breakers of the initiation of reactor trip, and selected      room multiplexers, if any, and    control rod motor-generator functions, as identified in Table 2.5.1-2,    PMS equipment will be              sets open after reactor and separate from the PMS. These manual          disconnected and the outputs      turbine trip manual initiation initiation functions are implemented in      from the DAS signal processing    controls are actuated.
a manner that bypasses the control            equipment will be disabled.
room multiplexers, if any; the PMS            While in this configuration, an cabinets; and the signal processing          operational test of the as-built equipment of the DAS.                        system will be performed using the DAS manual actuation controls.
510  2.5.01.02c.ii 2.c) The DAS provides manual                  Electrical power to the control    ii) DAS output signals are initiation of reactor trip, and selected      room multiplexers, if any, and    generated for the selected functions, as identified in Table 2.5.1-2,    PMS equipment will be              functions, as identified in separate from the PMS. These manual          disconnected and the outputs      Table 2.5.1-2, after manual initiation functions are implemented in      from the DAS signal processing    initiation controls are a manner that bypasses the control            equipment will be disabled.        actuated.
room multiplexers, if any; the PMS            While in this configuration, an cabinets; and the signal processing          operational test of the as-built equipment of the DAS.                        system will be performed using the DAS manual actuation controls.
511  2.5.01.02d  2.d) The DAS provides MCR displays            Electrical power to the PMS        The selected plant parameters of selected plant parameters, as              equipment will be disconnected    can be retrieved in the MCR.
identified in Table 2.5.1-3, separate        and inspection will be performed from the PMS.                                for retrievability of the selected plant parameters in the MCR.
C-300
 
Table 2.5.1-4 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No.            Design Commitment                  Inspections, Tests, Analyses          Acceptance Criteria 512  2.5.01.03a 3.a) The signal processing hardware of      Inspection of the as-built DAS    The DAS signal processing the DAS uses input modules, output          and PMS signal processing        equipment uses input modules, and microprocessor or special      hardware will be performed.      modules, output modules, and purpose logic processor boards that are                                      micro-processor or special different than those used in the PMS.                                        purpose logic processor boards that are different than those used in the PMS. The difference may be a different design, use of different component types, or different manufacturers.
513  2.5.01.03b 3.b) The display hardware of the DAS        Inspection of the as-built DAS    The DAS display hardware is uses a different display device than that  and PMS display hardware will    different than the display used in the PMS.                            be performed.                    hardware used in the PMS.
The difference may be a different design, use of different component types, or different manufacturers.
514  2.5.01.03c 3.c) Software diversity between the        Inspection of the DAS and PMS    Any DAS algorithms, logic, DAS and PMS will be achieved through        design documentation will be      program architecture, the use of different algorithms, logic,    performed.                        executable operating systems, program architecture, executable                                              and executable software/logic operating system, and executable                                              are different than those used software/logic.                                                              in the PMS.
515  2.5.01.03d 3.d) The DAS has electrical surge          Type tests, analyses, or a        A report exists and concludes withstand capability (SWC), and can        combination of type tests and    that the DAS equipment can withstand the electromagnetic              analyses will be performed on    withstand the SWC, EMI, RFI interference (EMI), radio frequency        the equipment.                    and ESD conditions that exist (RFI), and electrostatic discharge (ESD)                                      where the DAS equipment is conditions that exist where the DAS                                          located in the plant.
equipment is located in the plant.
516  2.5.01.03e 3.e) The sensors identified on Table        Inspection of the as-built system The sensors identified on 2.5.1-3 are used for DAS input and are      will be performed.                Table 2.5.1-3 are used by separate from those being used by the                                        DAS and are separate from PMS and plant control system.                                                those being used by the PMS and plant control system.
517  2.5.01.03f 3.f) The DAS is powered by non-Class        Electrical power to the PMS      A simulated test signal exists 1E uninterruptible power supplies that      equipment will be disconnected. at the DAS equipment when are independent and separate from the      While in this configuration, a    the assigned non-Class 1E power supplies which power the PMS.        test will be performed by        uninterruptible power supply providing simulated test signals  is provided the test signal.
in the non-Class 1E uninterruptible power supplies.
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Table 2.5.1-4 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No.            Design Commitment                  Inspections, Tests, Analyses        Acceptance Criteria 518  2.5.01.03g 3.g) The DAS signal processing              Channel tests will be performed The capability exists for cabinets are provided with the              on the as built system.        testing individual DAS capability for channel testing without                                      channels without propagating actuating the controlled components.                                        an actuation signal to a DAS controlled component.
519  2.5.01.03h 3.h) The DAS equipment can withstand        Type tests, analyses, or a      A report exists and concludes the room ambient temperature and            combination of type tests and  that the DAS equipment can humidity conditions that will exist at      analyses will be performed on  withstand the room ambient the plant locations in which the DAS        the equipment.                  temperature and humidity equipment is installed at the times for                                    conditions that will exist at the which the DAS is designed to be                                            plant locations in which the operational.                                                                DAS equipment is installed at the times for which the DAS is designed to be operational.
520  2.5.01.04  4. The DAS hardware and any software        Inspection will be performed of A report exists and concludes are developed using a planned design        the process used to design the  that the process defines the process which provides for specific        hardware and any software.      organizational responsibilities, design documentation and reviews                                            activities, and configuration during the following life cycle stages:                                    management controls for the a) Development phase for hardware and                                      following:
any software                                                                a) Documentation and review b) System test phase                                                        of hardware and any software.
c) Installation phase                                                      b) Performance of tests and the documentation of test The planned design process also results during the system test provides for the use of commercial off-phase.
the-shelf hardware and software.
c) Performance of tests and inspections during the installation phase.
The process also defines requirements for the use of commercial off-the-shelf hardware and software.
521  2.5.01.05  5. The DAS manual actuation of ADS,        See ITAAC Table 3.2-1, item 1. See ITAAC 3.2-1, item 1.
IRWST injection, and containment recirculation can be executed correctly and reliably.
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Table 2.5.1-5 Component Name              Tag No. Component Location DAS Processor Cabinet 1      DAS-JD-001      Annex Building DAS Processor Cabinet 2      DAS-JD-002      Annex Building DAS Squib Valve Control Cabinet DAS-JD-003    Auxiliary Building DAS Instrument Cabinet      DAS-JD-004    Auxiliary Building C-303
 
2.5.2          Protection and Safety Monitoring System Design Description The protection and safety monitoring system (PMS) initiates reactor trip and actuation of engineered safety features in response to plant conditions monitored by process instrumentation and provides safety-related displays. The PMS has the equipment identified in Table 2.5.2-1. The PMS has four divisions of Reactor Trip and Engineered Safety Features Actuation, and two divisions of safety-related post-accident parameter displays. The functional arrangement of the PMS is depicted in Figure 2.5.2-1 and the component locations of the PMS are as shown in Table 2.5.2-9.
: 1. The functional arrangement of the PMS is as described in the Design Description of this Section 2.5.2.
: 2. The seismic Category I equipment, identified in Table 2.5.2-1, can withstand seismic design basis loads without loss of safety function.
: 3. The Class 1E equipment, identified in Table 2.5.2-1, has electrical surge withstand capability (SWC), and can withstand the electromagnetic interference (EMI), radio frequency interference (RFI), and electrostatic discharge (ESD) conditions that would exist before, during, and following a design basis accident without loss of safety function for the time required to perform the safety function.
: 4. The Class 1E equipment, identified in Table 2.5.2-1, can withstand the room ambient temperature, humidity, pressure, and mechanical vibration conditions that would exist before, during, and following a design basis accident without loss of safety function for the time required to perform the safety function.
: 5. a) The Class 1E equipment, identified in Table 2.5.2-1, is powered from its respective Class 1E division.
b) Separation is provided between PMS Class 1E divisions, and between Class 1E divisions and non-Class 1E cable.
: 6. The PMS provides the following safety-related functions:
a) The PMS initiates an automatic reactor trip, as identified in Table 2.5.2-2, when plant process signals reach specified limits.
b) The PMS initiates automatic actuation of engineered safety features, as identified in Table 2.5.2-3, when plant process signals reach specified limits.
c) The PMS provides manual initiation of reactor trip and selected engineered safety features as identified in Table 2.5.2-4.
: 7. The PMS provides the following nonsafety-related functions:
a) The PMS provides process signals to the plant control system (PLS) through isolation devices.
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b) The PMS provides process signals to the data display and processing system (DDS) through isolation devices.
c) Data communication between safety and nonsafety systems does not inhibit the performance of the safety function.
d) The PMS ensures that the automatic safety function and the Class 1E manual controls both have priority over the non-Class 1E soft controls.
e) The PMS receives signals from non-safety equipment that provides interlocks for PMS test functions through isolation devices.
: 8. The PMS, in conjunction with the operator workstations, provides the following functions:
a) The PMS provides for the minimum inventory of displays, visual alerts, and fixed position controls, as identified in Table 2.5.2-5. The plant parameters listed with a "Yes" in the "Display" column and visual alerts listed with a "Yes" in the "Alert" column can be retrieved in the main control room (MCR). The fixed position controls listed with a "Yes" in the "Control" column are provided in the MCR.
b) The PMS provides for the transfer of control capability from the MCR to the remote shutdown workstation (RSW) using multiple transfer switches. Each individual transfer switch is associated with only a single safety-related group or with nonsafety-related control capability.
c) Displays of the open/closed status of the reactor trip breakers can be retrieved in the MCR.
: 9. a) The PMS automatically removes blocks of reactor trip and engineered safety features actuation when the plant approaches conditions for which the associated function is designed to provide protection. These blocks are identified in Table 2.5.2-6.
b) The PMS two-out-of-four initiation logic reverts to a two-out-of-three coincidence logic if one of the four channels is bypassed. All bypassed channels are alarmed in the MCR.
c) The PMS does not allow simultaneous bypass of two redundant channels.
d) The PMS provides the interlock functions identified in Table 2.5.2-7.
: 10. Setpoints are determined using a methodology which accounts for loop inaccuracies, response testing, and maintenance or replacement of instrumentation.
: 11. The PMS hardware and software is developed using a planned design process which provides for specific design documentation and reviews during the following life cycle stages:
a) Design requirements phase, may be referred to as conceptual or project definition phase (Complete) b) System definition phase c) Hardware and software development phase, consisting of hardware and software design and implementation C-305
 
d) System integration and test phase e) Installation phase
: 12. The PMS software is designed, tested, installed, and maintained using a process which incorporates a graded approach according to the relative importance of the software to safety and specifies requirements for:
a) Software management including documentation requirements, standards, review requirements, and procedures for problem reporting and corrective action.
b) Software configuration management including historical records of software and control of software changes.
c) Verification and validation including requirements for reviewer independence.
: 13. The use of commercial grade hardware and software items in the PMS is accomplished through a process that specifies requirements for:
a) Review of supplier design control, configuration management, problem reporting, and change control.
b) Review of product performance.
c) Receipt acceptance of the commercial grade item.
d) Final acceptance based on equipment qualification and software validation in the integrated system.
: 14. The Component Interface Module (CIM) is developed using a planned design process which provides for specific design documentation and reviews.
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Table 2.5.2-1 PMS Equipment Name and Classification Qual. for Equipment Name                        Seismic Cat. I Class 1E Harsh Envir.
PMS Cabinets, Division A                                          Yes        Yes        No PMS Cabinets, Division B                                          Yes        Yes        No PMS Cabinets, Division C                                          Yes        Yes        No PMS Cabinets, Division D                                          Yes        Yes        No Reactor Trip Switchgear, Division A                              Yes        Yes        No Reactor Trip Switchgear, Division B                              Yes        Yes        No Reactor Trip Switchgear, Division C                              Yes        Yes        No Reactor Trip Switchgear, Division D                              Yes        Yes        No MCR/RSW Transfer Panels                                          Yes        Yes        No MCR Safety-related Display, Division B                            Yes        Yes        No MCR Safety-related Display, Division C                            Yes        Yes        No MCR Safety-related Controls                                      Yes        Yes        No Table 2.5.2-2 PMS Automatic Reactor Trips Source Range High Neutron Flux Reactor Trip Intermediate Range High Neutron Flux Reactor Trip Power Range High Neutron Flux (Low Setpoint) Trip Power Range High Neutron Flux (High Setpoint) Trip Power Range High Positive Flux Rate Trip Reactor Coolant Pump High Bearing Water Temperature Trip Overtemperature Delta-T Trip Overpower Delta-T Trip Pressurizer Low Pressure Trip Pressurizer High Pressure Trip Pressurizer High Water Level Trip Low Reactor Coolant Flow Trip Low Reactor Coolant Pump Speed Trip Low Steam Generator Water Level Trip High-2 Steam Generator Water Level Trip Automatic or Manual Safeguards Actuation Trip Automatic or Manual Depressurization System Actuation Trip Automatic or Manual Core Makeup Tank (CMT) Injection Trip Passive Residual Heat Removal (PRHR) Actuation Reactor Trip C-307
 
Table 2.5.2-3 PMS Automatically Actuated Engineered Safety Features Safeguards Actuation Containment Isolation Automatic Depressurization System (ADS) Actuation Main Feedwater Isolation Reactor Coolant Pump Trip CMT Injection Turbine Trip (Isolated signal to nonsafety equipment)
Steam Line Isolation Steam Generator Relief Isolation Steam Generator Blowdown Isolation Passive Containment Cooling Actuation Startup Feedwater Isolation Passive Residual Heat Removal (PRHR) Heat Exchanger Alignment Block of Boron Dilution Chemical and Volume Control System (CVS) Makeup Line Isolation Steam Dump Block (Isolated signal to nonsafety equipment)
MCR Isolation, Air Supply Initiation, and Electrical Load De-energization Auxiliary Spray and Letdown Purification Line Isolation Containment Air Filtration System Isolation Normal Residual Heat Removal Isolation Refueling Cavity Isolation In-Containment Refueling Water Storage Tank (IRWST) Injection IRWST Containment Recirculation CVS Letdown Isolation Pressurizer Heater Block (Isolated signal to nonsafety equipment)
Containment Vacuum Relief Table 2.5.2-4 PMS Manually Actuated Functions Reactor Trip Safeguards Actuation Containment Isolation Depressurization System Stages 1, 2, and 3 Actuation Depressurization System Stage 4 Actuation Feedwater Isolation Core Makeup Tank Injection Actuation Steam Line Isolation Passive Containment Cooling Actuation Passive Residual Heat Removal Heat Exchanger Alignment IRWST Injection Containment Recirculation Actuation MCR Isolation, Air Supply Initiation and Electrical Load De-energization Steam Generator Relief Isolation Chemical and Volume Control System Isolation Normal Residual Heat Removal System Isolation Containment Vacuum Relief C-308
 
Table 2.5.2-5 Minimum Inventory of Displays, Alerts, and Fixed Position Controls in the MCR Description                                  Control            Display            Alert(1)
Neutron Flux                                                            -                  Yes                Yes Neutron Flux Doubling(2)                                                -                  No                Yes Startup Rate                                                            -                  Yes                Yes Reactor Coolant System (RCS) Pressure                                  -                  Yes                Yes Wide-range Hot Leg Temperature                                          -                  Yes                No Wide-range Cold Leg Temperature                                        -                  Yes                Yes RCS Cooldown Rate Compared to the Limit Based on RCS                    -                  Yes                Yes Pressure Wide-range Cold Leg Temperature Compared to the Limit                  -                  Yes                Yes Based on RCS Pressure Change of RCS Temperature by more than 5&deg;F in the last                  -                  No                Yes 10 minutes Containment Water Level                                                -                  Yes                Yes Containment Pressure                                                    -                  Yes                Yes Pressurizer Water Level                                                -                  Yes                Yes Pressurizer Water Level Trend                                          -                  Yes                No Pressurizer Reference Leg Temperature                                  -                  Yes                No Reactor Vessel-Hot Leg Water Level                                      -                  Yes                Yes Pressurizer Pressure                                                    -                  Yes                No Core Exit Temperature                                                  -                  Yes                Yes RCS Subcooling                                                          -                  Yes                Yes RCS Cold Overpressure Limit                                            -                  Yes                Yes IRWST Water Level                                                      -                  Yes                Yes PRHR Flow                                                              -                  Yes                Yes PRHR Outlet Temperature                                                -                  Yes                Yes Note: Dash (-) indicates not applicable.
: 1. These parameters are used to generate visual alerts that identify challenges to the critical safety functions. For the main control room, the visual alerts are embedded in the safety-related displays as visual signals.
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Table 2.5.2-5 (cont.)
Minimum Inventory of Displays, Alerts, and Fixed Position Controls in the MCR Description                                Control    Display      Alert(1)
Passive Containment Cooling System (PCS) Storage Tank                  -          Yes        No Water Level PCS Cooling Flow                                                      -          Yes        No IRWST to Normal Residual Heat Removal System (RNS)                    -          Yes        Yes Suction Valve Status(2)
Remotely Operated Containment Isolation Valve Status(2)                -          Yes        No Containment Area High-range Radiation Level                            -          Yes        Yes Containment Pressure (Extended Range)                                  -          Yes        No CMT Level                                                              -          Yes        No Manual Reactor Trip (also initiates turbine trip)                    Yes          -          -
Manual Safeguards Actuation                                          Yes          -          -
Manual CMT Actuation                                                  Yes          -          -
Manual MCR Emergency Habitability System Actuation                    Yes          -          -
Manual ADS Stages 1, 2, and 3 Actuation                              Yes          -          -
Manual ADS Stage 4 Actuation                                          Yes          -          -
Manual PRHR Actuation                                                Yes          -          -
Manual Containment Cooling Actuation                                  Yes          -          -
Manual IRWST Injection Actuation                                      Yes          -          -
Manual Containment Recirculation Actuation                            Yes          -          -
Manual Containment Isolation                                          Yes          -          -
Manual Main Steam Line Isolation                                      Yes          -          -
Manual Feedwater Isolation                                            Yes          -          -
Manual Containment Hydrogen Igniter (Nonsafety-related)              Yes          -          -
Manual Containment Vacuum Relief                                      Yes Note: Dash (-) indicates not applicable.
: 2. These instruments are not required after 24 hours.
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Table 2.5.2-6 PMS Blocks Reactor Trip Functions:
Source Range High Neutron Flux Reactor Trip Intermediate Range High Neutron Flux Reactor Trip Power Range High Neutron Flux (Low Setpoint) Trip Pressurizer Low Pressure Trip Pressurizer High Water Level Trip Low Reactor Coolant Flow Trip Low Reactor Coolant Pump Speed Trip High Steam Generator Water Level Trip Engineered Safety Features:
Automatic Safeguards Containment Isolation Main Feedwater Isolation Reactor Coolant Pump Trip Core Makeup Tank Injection Steam Line Isolation Startup Feedwater Isolation Block of Boron Dilution Chemical and Volume Control System Isolation Chemical and Volume Control System Letdown Isolation Steam Dump Block Auxiliary Spray and Letdown Purification Line Isolation Passive Residual Heat Removal Heat Exchanger Alignment Normal Residual Heat Removal System Isolation Table 2.5.2-7 PMS Interlocks RNS Suction Valves PRHR Heat Exchanger Inlet Isolation Valve CMT Cold Leg Balance Line Isolation Valves Containment Vacuum Relief Isolation Valves Table 2.5.2-8 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No.                Design Commitment                  Inspections, Tests, Analyses        Acceptance Criteria 522  2.5.02.01    1. The functional arrangement of the        Inspection of the as-built system The as-built PMS conforms PMS is as described in the Design          will be performed.                with the functional Description of this Section 2.5.2.                                            arrangement as described in the Design Description of this Section 2.5.2.
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Table 2.5.2-8 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No.              Design Commitment                    Inspections, Tests, Analyses          Acceptance Criteria 523  2.5.02.02.i  2. The seismic Category I equipment,        i) Inspection will be performed    i) The seismic Category I identified in Table 2.5.2-1, can            to verify that the seismic        equipment identified in withstand seismic design basis loads        Category I equipment identified    Table 2.5.2-1 is located on the without loss of safety function.            in Table 2.5.2-1 is located on the Nuclear Island.
Nuclear Island.
524  2.5.02.02.ii 2. The seismic Category I equipment,        ii) Type tests, analyses, or a    ii) A report exists and identified in Table 2.5.2-1, can            combination of type tests and      concludes that the seismic withstand seismic design basis loads        analyses of seismic Category I    Category I equipment can without loss of safety function.            equipment will be performed.      withstand seismic design basis loads without loss of safety function.
525  2.5.02.02.iii 2. The seismic Category I equipment,        iii) Inspection will be performed  iii) A report exists and identified in Table 2.5.2-1, can            for the existence of a report      concludes that the as-built withstand seismic design basis loads        verifying that the as-built        equipment including without loss of safety function.            equipment including anchorage      anchorage is seismically is seismically bounded by the      bounded by the tested or tested or analyzed conditions. analyzed conditions.
526    2.5.02.03  3. The Class 1E equipment, identified        Type tests, analyses, or a        A report exists and concludes in Table 2.5.2-1, has electrical surge      combination of type tests and      that the Class 1E equipment withstand capability (SWC), and can          analyses will be performed on      identified in Table 2.5.2-1 can withstand the electromagnetic                the equipment.                    withstand the SWC, EMI, interference (EMI), radio frequency                                            RFI, and ESD conditions that interference (RFI), and electrostatic                                          would exist before, during, discharge (ESD) conditions that would                                          and following a design basis exist before, during, and following a                                          accident without loss of safety design basis accident without loss of                                          function for the time required safety function for the time required to                                        to perform the safety function.
perform the safety function.
527    2.5.02.04  4. The Class 1E equipment, identified        Type tests, analyses, or a        A report exists and concludes in Table 2.5.2-1, can withstand the room    combination of type tests and      that the Class 1E equipment ambient temperature, humidity,              analyses will be performed on      identified in Table 2.5.2-1 can pressure, and mechanical vibration          the Class 1E equipment            withstand the room ambient conditions that would exist before,          identified in Table 2.5.2-1.      temperature, humidity, during, and following a design basis                                            pressure, and mechanical accident without loss of safety function                                        vibration conditions that for the time required to perform the                                            would exist before, during, safety function.                                                                and following a design basis accident without loss of safety function for the time required to perform the safety function.
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Table 2.5.2-8 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No.              Design Commitment                    Inspections, Tests, Analyses          Acceptance Criteria 528  2.5.02.05a  5.a) The Class 1E equipment, identified      Tests will be performed by        A simulated test signal exists in Table 2.5.2-1, is powered from its        providing a simulated test signal at the Class 1E equipment respective Class 1E division.                in each Class 1E division.        identified in Table 2.5.2-1 when the assigned Class 1E division is provided the test signal.
529  2.5.02.05b  5.b) Separation is provided between          See ITAAC Table 3.3-6,            See ITAAC Table 3.3-6, PMS Class 1E divisions, and between          items 7.d and 7.e.                items 7.d and 7.e.
Class 1E divisions and non-Class 1E cable.
530  2.5.02.06a.i  6.a) The PMS initiates an automatic          An operational test of the as-    i) The reactor trip switchgear reactor trip, as identified in                built PMS will be performed      opens after the test signal Table 2.5.2-2, when plant process            using real or simulated test      reaches the specified limit.
signals reach specified limits.              signals.                          This only needs to be verified for one automatic reactor trip function.
531  2.5.02.06a.ii 6.a) The PMS initiates an automatic          An operational test of the as-    ii) PMS output signals to the reactor trip, as identified in                built PMS will be performed      reactor trip switchgear are Table 2.5.2-2, when plant process            using real or simulated test      generated after the test signal signals reach specified limits.              signals.                          reaches the specified limit.
This needs to be verified for each automatic reactor trip function.
532  2.5.02.06b  6.b) The PMS initiates automatic              An operational test of the as-    Appropriate PMS output actuation of engineered safety features,      built PMS will be performed      signals are generated after the as identified in Table 2.5.2-3, when          using real or simulated test      test signal reaches the plant process signals reach specified        signals.                          specified limit. These output limits.                                                                        signals remain following removal of the test signal.
Tests from the actuation signal to the actuated device(s) are performed as part of the system-related inspection, test, analysis, and acceptance criteria.
533  2.5.02.06c.i  6.c) The PMS provides manual                  An operational test of the as-    i) The reactor trip switchgear initiation of reactor trip and selected      built PMS will be performed      opens after manual reactor trip engineered safety features as identified      using the PMS manual actuation    controls are actuated.
in Table 2.5.2-4.                            controls.
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Table 2.5.2-8 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No.              Design Commitment                    Inspections, Tests, Analyses          Acceptance Criteria 534  2.5.02.06c.ii 6.c) The PMS provides manual                  An operational test of the as-    ii) PMS output signals are initiation of reactor trip and selected      built PMS will be performed      generated for reactor trip and engineered safety features as identified      using the PMS manual actuation    selected engineered safety in Table 2.5.2-4.                            controls.                        features as identified in Table 2.5.2-4 after the manual initiation controls are actuated.
535  2.5.02.07a  7.a) The PMS provides process signals        Type tests, analyses, or a        A report exists and concludes to the PLS through isolation devices.        combination of type tests and    that the isolation devices analyses of the isolation devices prevent credible faults from will be performed.                propagating into the PMS.
536  2.5.02.07b  7.b) The PMS provides process signals        Type tests, analyses, or a        A report exists and concludes to the DDS through isolation devices.        combination of type tests and    that the isolation devices analyses of the isolation devices prevent credible faults from will be performed.                propagating into the PMS.
537  2.5.02.07c  7.c) Data communication between              Type tests, analyses, or a        A report exists and concludes safety and nonsafety systems does not        combination of type tests and    that data communication inhibit the performance of the safety        analyses of the PMS gateways      between safety and nonsafety function.                                    will be performed.                systems does not inhibit the performance of the safety function.
538  2.5.02.07d  7.d) The PMS ensures that the                Type tests, analyses, or a        A report exists and concludes automatic safety function and the            combination of type tests and    that the automatic safety Class 1E manual controls both have            analyses of the PMS manual        function and the Class 1E priority over the non-Class 1E soft          control circuits and algorithms  manual controls both have controls.                                    will be performed.                priority over the non-Class 1E soft controls.
539  2.5.02.07e  7.e) The PMS receives signals from            Type tests, analyses, or a        A report exists and concludes non-safety equipment that provides            combination of type tests and    that the isolation devices interlocks for PMS test functions            analyses of the isolation devices prevent credible faults from through isolation devices.                    will be performed.                propagating into the PMS.
540  2.5.02.08a.i  8.a) The PMS provides for the                i) An inspection will be          i) The plant parameters listed minimum inventory of displays, visual        performed for retrievability of  in Table 2.5.2-5 with a "Yes" alerts, and fixed position controls, as      plant parameters in the MCR.      in the "Display" column, can identified in Table 2.5.2-5. The plant                                          be retrieved in the MCR.
parameters listed with a "Yes" in the "Display" column and visual alerts listed with a "Yes" in the "Alert" column can be retrieved in the MCR.
The fixed position controls listed with a "Yes" in the "Control" column are provided in the MCR.
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Table 2.5.2-8 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No.                Design Commitment                    Inspections, Tests, Analyses        Acceptance Criteria 541  2.5.02.08a.ii  8.a) The PMS provides for the                ii) An inspection and test will be ii) The plant parameters listed minimum inventory of displays, visual        performed to verify that the plant in Table 2.5.2-5 with a "Yes" alerts, and fixed position controls, as      parameters are used to generate    in the "Alert" column are used identified in Table 2.5.2-5. The plant      visual alerts that identify        to generate visual alerts that parameters listed with a "Yes" in the        challenges to critical safety      identify challenges to critical "Display" column and visual alerts          functions.                        safety functions. The visual listed with a "Yes" in the "Alert"                                              alerts actuate in accordance column can be retrieved in the MCR.                                            with their correct logic and The fixed position controls listed with a                                      values.
                    "Yes" in the "Control" column are provided in the MCR.
542  2.5.02.08a.iii 8.a) The PMS provides for the                iii) An operational test of the    iii) For each test of an as-built minimum inventory of displays, visual        as-built system will be            fixed position control listed in alerts, and fixed position controls, as      performed using each MCR          Table 2.5.2-5 with a "Yes" in identified in Table 2.5.2-5. The plant      fixed position control.            the "Control" column, an parameters listed with a "Yes" in the                                          actuation signal is generated.
                    "Display" column and visual alerts                                              Tests from the actuation signal listed with a "Yes" in the "Alert"                                              to the actuated device(s) are column can be retrieved in the MCR.                                            performed as part of the The fixed position controls listed with a                                      system-related inspection, test, "Yes" in the "Control" column are                                              analysis and acceptance provided in the MCR.                                                            criteria.
543  2.5.02.08b.i  8.b) The PMS provides for the transfer      i) An inspection will be          i) A transfer switch exists for of control capability from the MCR to        performed to verify that a        each safety-related division the RSW using multiple transfer              transfer switch exists for each    and the nonsafety-related switches. Each individual transfer          safety-related division and the    control capability.
switch is associated with only a single      nonsafety-related control safety-related group or with nonsafety-      capability.
related control capability.
544  2.5.02.08b.ii  8.b) The PMS provides for the transfer      ii) An operational test of the as- ii) Actuation of each transfer of control capability from the MCR to        built system will be performed to  switch results in an alarm in the RSW using multiple transfer              demonstrate the transfer of        the MCR and RSW, the switches. Each individual transfer          control capability from the MCR    activation of operator control switch is associated with only a single      to the RSW.                        capability from the RSW, and safety-related group or with nonsafety-                                        the deactivation of operator related control capability.                                                    control capability from the MCR for the associated safety-related division and nonsafety-related control capability.
545    2.5.02.08c  8.c) Displays of the open/closed status      Inspection will be performed for  Displays of the open/closed of the reactor trip breakers can be          retrievability of displays of the  status of the reactor trip retrieved in the MCR.                        open/closed status of the reactor  breakers can be retrieved in trip breakers in the MCR.          the MCR.
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Table 2.5.2-8 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No.            Design Commitment                    Inspections, Tests, Analyses        Acceptance Criteria 546  2.5.02.09a 9.a) The PMS automatically removes          An operational test of the as-  The PMS blocks are blocks of reactor trip and engineered        built PMS will be performed      automatically removed when safety features actuation when the plant    using real or simulated test    the test signal reaches the approaches conditions for which the          signals.                        specified limit.
associated function is designed to provide protection. These blocks are identified in Table 2.5.2-6.
547  2.5.02.09b 9.b) The PMS two-out-of-four                An operational test of the as-  The PMS two-out-of-four initiation logic reverts to a two-out-of-    built PMS will be performed. initiation logic reverts to a three coincidence logic if one of the                                        two-out-of-three coincidence four channels is bypassed. All bypassed                                      logic if one of the four channels are alarmed in the MCR.                                              channels is bypassed. All bypassed channels are alarmed in the MCR.
548  2.5.02.09c 9.c) The PMS does not allow                  An operational test of the as-  The redundant channel cannot simultaneous bypass of two redundant        built PMS will be performed. be placed in bypass.
channels.                                    With one channel in bypass, an attempt will be made to place a redundant channel in bypass.
549  2.5.02.09d 9.d) The PMS provides the interlock          An operational test of the as-  Appropriate PMS output functions identified in Table 2.5.2-7.      built PMS will be performed      signals are generated as the using real or simulated test    interlock conditions are signals.                        changed.
550  2.5.02.10  10. Setpoints are determined using a        Inspection will be performed for A report exists and concludes methodology which accounts for loop          a document that describes the    that the PMS setpoints are inaccuracies, response testing, and          methodology and input            determined using a maintenance or replacement of                parameters used to determine the methodology which accounts instrumentation.                            PMS setpoints.                  for loop inaccuracies, response testing, and maintenance or replacement of instrumentation.
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Table 2.5.2-8 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No.            Design Commitment                  Inspections, Tests, Analyses        Acceptance Criteria 551  2.5.02.11 11. The PMS hardware and software is        Inspection will be performed of A report exists and concludes developed using a planned design            the process used to design the  that the process defines the process which provides for specific        hardware and software.          organizational responsibilities, design documentation and reviews                                            activities, and configuration during the following life cycle stages:                                    management controls for the a) Not used                                                                following:
b) System definition phase                                                  a) Not used.
c) Hardware and software development                                        b) Specification of functional phase, consisting of hardware and                                          requirements.
software design and implementation                                          c) Documentation and review d) System integration and test phase                                        of hardware and software.
e) Installation phase                                                      d) Performance of system tests and the documentation of system test results, including a response time test performed under maximum CPU loading to demonstrate that the PMS can fulfill its response time criteria.
e) Performance of installation tests and inspections.
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Table 2.5.2-8 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No.            Design Commitment                    Inspections, Tests, Analyses          Acceptance Criteria 552  2.5.02.12 12. The PMS software is designed,            Inspection will be performed of  A report exists and concludes tested, installed, and maintained using a    the process used to design, test, that the process establishes a process which incorporates a graded          install, and maintain the PMS    method for classifying the approach according to the relative          software.                        PMS software elements importance of the software to safety and                                      according to their relative specifies requirements for:                                                    importance to safety and a) Software management including                                              specifies requirements for documentation requirements, standards,                                        software assigned to each review requirements, and procedures                                            safety classification. The for problem reporting and corrective                                          report also concludes that action.                                                                        requirements are provided for the following software b) Software configuration management development functions:
including historical records of software and control of software changes.                                              a) Software management including documentation c) Verification and validation including requirements, standards, requirements for reviewer review requirements, and independence.
procedures for problem reporting and corrective action. Software management requirements may be documented in the software quality assurance plan, software management plan, software development plan, software safety plan, and software operation and maintenance plan; or these requirements may be combined into a single software management plan.
b) Software configuration management including historical records of software and control of software changes. Software configuration management requirements are provided in the software configuration management plan.
c) Verification and validation including requirements for reviewer independence.
Verification and validation requirements are provided in the verification and validation plan.
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Table 2.5.2-8 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No.            Design Commitment                  Inspections, Tests, Analyses        Acceptance Criteria 553  2.5.02.13 13. The use of commercial grade            Inspection will be performed of A report exists and concludes computer hardware and software items        the process defined to use      that the process has in the PMS is accomplished through a        commercial grade components in  requirements for:
process that specifies requirements for:    the application.                a) Review of supplier design a) Review of supplier design control,                                      control, configuration configuration management, problem                                          management, problem reporting, and change control.                                              reporting, and change control.
b) Review of product performance.                                          b) Review of product c) Receipt acceptance of the                                                performance.
commercial grade item.                                                      c) Receipt acceptance of the d) Acceptance based on equipment                                            commercial grade item.
qualification and software validation in                                    d) Acceptance based on the integrated system.                                                      equipment qualification and software validation in the integrated system.
554  2.5.02.14 14. The Component Interface Module          An inspection and or an audit  A report exists and concludes (CIM) is developed using a planned          will be performed of the        that CIM meets the below design process which provides for          processes used to design the    listed life cycle stages.
specific design documentation and          hardware, development          Life cycle stages:
reviews.                                    software, qualification and testing.                        a. Design requirements phase, may be referred to as conceptual or project definition phase
: b. System definition phase
: c. Hardware and software development phase, consisting of hardware and software design and implementation
: d. System integration and test phase
: e. Installation phase
{Design Acceptance Criteria}
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Table 2.5.2-9 Component Name                                    Component Location PMS Cabinets, Division A                          Auxiliary Building PMS Cabinets, Division B                          Auxiliary Building PMS Cabinets, Division C                          Auxiliary Building PMS Cabinets, Division D                          Auxiliary Building Reactor Trip Switchgear, Division A                Auxiliary Building Reactor Trip Switchgear, Division B                Auxiliary Building Reactor Trip Switchgear, Division C                Auxiliary Building Reactor Trip Switchgear, Division D                Auxiliary Building MCR/RSW Transfer Panels                            Auxiliary Building MCR Safety-related Displays                        Auxiliary Building MCR Safety-related Controls                        Auxiliary Building C-320
 
Figure 2.5.2-1 Protection and Safety Monitoring System C-321
 
2.5.3          Plant Control System Design Description The plant control system (PLS) provides for automatic and manual control of nonsafety-related plant components during normal and emergency plant operations. The PLS has distributed controllers and operator controls interconnected by computer data links or data highways.
: 1. The functional arrangement of the PLS is as described in the Design Description of this Section 2.5.3.
: 2. The PLS provides control interfaces for the control functions listed in Table 2.5.3-1.
Table 2.5.3-1 Control Functions Supported by the PLS
: 1. Reactor Power                                  5. Steam Generator Feedwater
: 2. Reactor Rod Position                          6. Steam Dump
: 3. Pressurizer Pressure                          7. Rapid Power Reduction
: 4. Pressurizer Water Level Table 2.5.3-2 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No.            Design Commitment                  Inspections, Tests, Analyses            Acceptance Criteria 555  2.5.03.01    1. The functional arrangement        Inspection of the as-built system  The as-built PLS conforms with of the PLS is as described in the    will be performed.                the functional arrangement as Design Description of this                                              described in the Design Section 2.5.3.                                                          Description of this Section 2.5.3.
556  2.5.03.02    2. The PLS provides control          An operational test of the system  The PLS provides control interfaces for the control            will be performed using simulated  interfaces for the control functions functions listed in Table 2.5.3-1. input signals. System outputs or  listed in Table 2.5.3-1.
component operations will be monitored to determine the operability of the control functions.
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2.5.4          Data Display and Processing System Design Description The data display and processing system (DDS) provides nonsafety-related alarms and displays, analysis of plant data, plant data logging and historical storage and retrieval, and operational support for plant personnel. The DDS has distributed computer processors and video display units to support the data processing and display functions.
: 1. The functional arrangement of the DDS is as described in the Design Description of this Section 2.5.4.
: 2. The DDS, in conjunction with the operator workstations, provides the following function:
The DDS provides for the minimum inventory of displays, visual alerts, and fixed position controls, as identified in Table 2.5.4-1. The plant parameters listed with a "Yes" in the "Display" column and visual alerts listed with a "Yes" in the "Alert" column can be retrieved at the remote shutdown workstation (RSW). The controls listed with a "Yes" in the "Control" column are provided at the RSW.
: 3. The DDS provides information pertinent to the status of the protection and safety monitoring system.
: 4. The plant operating instrumentation installed for feedwater flow measurement is one that has been specifically approved by the NRC; the power calorimetric uncertainty calculation includes uncertainties for the associated instrumentation based on an NRC approved methodology; and the calculated calorimetric values are bounded by the uncertainty value assumed for the initial reactor power in the safety analysis.
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Table 2.5.4-1 Minimum Inventory of Controls, Displays, and Alerts at the RSW Description                                  Control              Display          Alert(1)
Neutron Flux                                                              -                  Yes              Yes Neutron Flux Doubling                                                    -                  No              Yes Startup Rate                                                              -                  Yes              Yes Reactor Coolant System (RCS) Pressure                                    -                  Yes              Yes Wide-range Hot Leg Temperature                                            -                  Yes              No Wide-range Cold Leg Temperature                                          -                  Yes              Yes RCS Cooldown Rate Compared to the Limit Based on                          -                  Yes              Yes RCS Pressure Wide-range Cold Leg Temperature Compared to the Limit                    -                  Yes              Yes Based on RCS Pressure Change of RCS Temperature by more than 5&deg;F in the last                    -                  No              Yes 10 minutes Containment Water Level                                                  -                  Yes              Yes Containment Pressure                                                      -                  Yes              Yes Pressurizer Water Level                                                  -                  Yes              Yes Pressurizer Water Level Trend                                            -                  Yes              No Pressurizer Reference Leg Temperature                                    -                  Yes              No Reactor Vessel-Hot Leg Water Level                                        -                  Yes              Yes Pressurizer Pressure                                                      -                  Yes              No Core Exit Temperature                                                    -                  Yes              Yes RCS Subcooling                                                            -                  Yes              Yes RCS Cold Overpressure Limit                                              -                  Yes              Yes In-containment Refueling Water Storage Tank (IRWST)                      -                  Yes              Yes Water Level Passive Residual Heat Removal (PRHR) Flow                                -                  Yes              Yes Note: Dash (-) indicates not applicable.
: 1. These parameters are used to generate visual alerts that identify challenges to the critical safety functions. For the RSW, the visual alerts are embedded in the nonsafety-related displays as visual signals.
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Table 2.5.4-1 (cont.)
Minimum Inventory of Controls, Displays, and Alerts at the RSW Description                                  Control              Display          Alert(1)
PRHR Outlet Temperature                                                    -                  Yes              Yes Passive Containment Cooling System (PCS) Storage Tank                      -                  Yes              No Water Level PCS Cooling Flow                                                          -                  Yes              No IRWST to Normal Residual Heat Removal System (RNS)                        -                  Yes              Yes Suction Valve Status Remotely Operated Containment Isolation Valve Status                      -                  Yes              No Containment Area High-range Radiation Level                                -                  Yes              Yes Containment Pressure (Extended Range)                                      -                  Yes              No Core Makeup Tank (CMT) Level                                              -                  Yes              No Manual Reactor Trip (also initiates turbine trip)                        Yes                    -                -
Manual Safeguards Actuation                                              Yes                    -                -
Manual CMT Actuation                                                    Yes                    -                -
Manual Automatic Depressurization System (ADS) Stages 1,                Yes                    -                -
2, and 3 Actuation Manual ADS Stage 4 Actuation                                            Yes                    -                -
Manual PRHR Actuation                                                    Yes                    -                -
Manual Containment Cooling Actuation                                    Yes                    -                -
Manual IRWST Injection Actuation                                        Yes                    -                -
Manual Containment Recirculation Actuation                              Yes                    -                -
Manual Containment Isolation                                            Yes                    -                -
Manual Main Steam Line Isolation                                        Yes                    -                -
Manual Feedwater Isolation                                              Yes                    -                -
Manual Containment Hydrogen Igniter (Nonsafety-related)                  Yes                    -                -
Note: Dash (-) indicates not applicable.
: 1. These parameters are used to generate visual alerts that identify challenges to the critical safety functions. For the RSW, the visual alerts are embedded in the nonsafety-related displays as visual signals.
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Table 2.5.4-2 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No.          Design Commitment                  Inspections, Tests, Analyses            Acceptance Criteria 557  2.5.04.01  1. The functional arrangement of      Inspection of the as-built system    The as-built DDS conforms with the DDS is as described in the        will be performed.                  the functional arrangement as Design Description of this                                                described in the Design Section 2.5.4.                                                            Description of this Section 2.5.4.
558  2.5.04.02.i  2. The DDS provides for the          i) An inspection will be performed  i) The plant parameters listed in minimum inventory of displays,        for retrievability of plant          Table 2.5.4-1 with a "Yes" in the visual alerts, and fixed position    parameters at the RSW.              "Display" column can be retrieved controls, as identified in Table                                          at the RSW.
2.5.4-1. The plant parameters listed with a "Yes" in the "Display" column and visual alerts listed with a "Yes" in the "Alert" column can be retrieved at the RSW. The controls listed with a "Yes" in the "Control" column are provided at the RSW.
559  2.5.04.02.ii 2. The DDS provides for the          ii) An inspection and test will be  ii) The plant parameters listed in minimum inventory of displays,        performed to verify that the plant  Table 2.5.4-1 with a "Yes" in the visual alerts, and fixed position    parameters are used to generate      "Alert" column are used to controls, as identified in            visual alerts that identify          generate visual alerts that identify Table 2.5.4-1. The plant              challenges to critical safety        challenges to critical safety parameters listed with a "Yes" in    functions.                          functions. The visual alerts the "Display" column and visual                                            actuate in accordance with their alerts listed with a "Yes" in the                                          logic and values.
                  "Alert" column can be retrieved at the RSW. The controls listed with a "Yes" in the "Control" column are provided at the RSW.
560 2.5.04.02.iii 2. The DDS provides for the          iii) An operational test of the as-  iii) For each test of a control listed minimum inventory of displays,        built system will be performed      in Table 2.5.4-1 with a "Yes" in visual alerts, and fixed position    using each RSW control.              the "Control" column, an actuation controls, as identified in                                                signal is generated. Tests from the Table 2.5.4-1. The plant                                                  actuation signal to the actuated parameters listed with a "Yes" in                                          device(s) are performed as part of the "Display" column and visual                                            the system-related inspection, test, alerts listed with a "Yes" in the                                          analysis and acceptance criteria.
                  "Alert" column can be retrieved at the RSW. The controls listed with a "Yes" in the "Control" column are provided at the RSW.
561  2.5.04.03  3. The DDS provides                  Tests of the as-built system will be The as-built system provides information pertinent to the          performed.                          displays of the bypassed and status of the protection and                                              operable status of the protection safety monitoring system.                                                  and safety monitoring system.
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Table 2.5.4-2 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No.          Design Commitment                  Inspections, Tests, Analyses            Acceptance Criteria 562 C.2.5.04.04a 4. The plant calorimetric            Inspection will be performed of    a) The as-built system takes input uncertainty and plant                the plant operating instrumentation for feedwater flow measurement instrumentation performance is        installed for feedwater flow        from a Caldon [Cameron] LEFM bounded by the 1% calorimetric        measurement, its associated power  CheckPlus' System; uncertainty value assumed for        calorimetric uncertainty the initial reactor power in the      calculation, and the calculated safety analysis.                      calorimetric values.
563 C.2.5.04.04b 4. The plant calorimetric            Inspection will be performed of    b) The power calorimetric uncertainty and plant                the plant operating instrumentation uncertainty calculation instrumentation performance is        installed for feedwater flow        documented for that bounded by the 1% calorimetric        measurement, its associated power  instrumentation is based on an uncertainty value assumed for        calorimetric uncertainty            accepted Westinghouse the initial reactor power in the      calculation, and the calculated    methodology and the uncertainty safety analysis.                      calorimetric values.                values for that instrumentation are not lower than those for the actual installed instrumentation; and 564 C.2.5.04.04c 4. The plant calorimetric            Inspection will be performed of    c) The calculated calorimetric uncertainty and plant                the plant operating instrumentation power uncertainty measurement instrumentation performance is        installed for feedwater flow        values are bounded by the bounded by the 1% calorimetric        measurement, its associated power  1% uncertainty value assumed for uncertainty value assumed for        calorimetric uncertainty            the initial reactor power in the the initial reactor power in the      calculation, and the calculated    safety analysis.
safety analysis.                      calorimetric values.
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2.5.5            In-Core Instrumentation System Design Description The in-core instrumentation system (IIS) provides safety-related core exit thermocouple signals to the protection and safety monitoring system (PMS). The IIS also provides nonsafety-related core exit thermocouple signals to the diverse actuation system (DAS). The core exit thermocouples are housed in the core instrument assemblies. Multiple core instrument assemblies are used to provide radial coverage of the core. At least three core instrument assemblies are provided in each core quadrant.
: 1. The functional arrangement of the IIS is as described in the Design Description of this Section 2.5.5.
: 2. The seismic Category I equipment identified in Table 2.5.5-1 can withstand seismic design basis loads without loss of safety function.
: 3. a) The Class 1E equipment identified in Table 2.5.5-1 as being qualified for a harsh environment can withstand environmental conditions that would exist before, during, and following a design basis accident without loss of safety function, for the time required to perform the safety function.
b) The Class 1E cables between the Incore Thermocouple elements and the connector boxes located on the integrated head package have sheaths.
c) For cables other than those covered by 3.b, separation is provided between IIS Class 1E divisions, and between Class 1E divisions and non-Class 1E cable.
: 4. Safety-related displays of the parameters identified in Table 2.5.5-1 can be retrieved in the main control room (MCR).
Table 2.5.5-1 Seismic      ASME Code                          Qual. for        Safety-Related Equipment Name              Cat. I    Classification      Class 1E      Harsh Envir.            Display Incore Thimble                  Yes              -              Yes(1)          Yes(1)            Core Exit Assemblies (at least                                                                              Temperature(1) three assemblies in each core quadrant)
Note: Dash (-) indicates not applicable.
: 1. Only applies to the safety-related assemblies. There are at least two safety-related assemblies in each core quadrant.
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Table 2.5.5-2 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No.              Design Commitment                    Inspections, Tests, Analyses        Acceptance Criteria 565    2.5.05.01  1. The functional arrangement of the        Inspection of the as-built system  The as-built IIS conforms with IIS is as described in the Design            will be performed.                the functional arrangement as Description of this Section 2.5.5.                                              described in the Design Description of this Section 2.5.5.
566  2.5.05.02.i  2. The seismic Category I equipment          i) Inspection will be performed    i) The seismic Category I identified in Table 2.5.5-1 can withstand    to verify that the seismic        equipment identified in seismic design basis dynamic loads          Category I equipment identified    Table 2.5.5-1 is located on the without loss of safety function.            in Table 2.5.5-1 is located on the Nuclear Island.
Nuclear Island.
567  2.5.05.02.ii 2. The seismic Category I equipment          ii) Type tests, analyses, or a    ii) A report exists and identified in Table 2.5.5-1 can withstand    combination of type tests and      concludes that the seismic seismic design basis dynamic loads          analyses of seismic Category I    Category I equipment can without loss of safety function.            equipment will be performed.      withstand seismic design basis dynamic loads without loss of safety function.
568  2.5.05.02.iii 2. The seismic Category I equipment          iii) Inspection will be performed  iii) A report exists and identified in Table 2.5.5-1 can withstand    for the existence of a report      concludes that the as-built seismic design basis dynamic loads          verifying that the as-built        equipment including without loss of safety function.            equipment including anchorage      anchorage is seismically is seismically bounded by the      bounded by the tested or tested or analyzed conditions. analyzed conditions.
569  2.5.05.03a.i  3.a) The Class 1E equipment identified      i) Type tests, analysis, or a      i) A report exists and in Table 2.5.5-1 as being qualified for a    combination of type tests and      concludes that the Class 1E harsh environment can withstand the          analysis will be performed on      equipment identified in environmental conditions that would          Class 1E equipment located in a    Table 2.5.5-1 as being exist before, during, and following a        harsh environment.                qualified for a harsh design basis accident without loss of                                          environment. This equipment safety function, for the time required to                                      can withstand the perform the safety function.                                                    environmental conditions that would exist before, during, and following a design basis accident without loss of safety function for the time required to perform the safety function.
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Table 2.5.5-2 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No.              Design Commitment                    Inspections, Tests, Analyses        Acceptance Criteria 570  2.5.05.03a.ii 3.a) The Class 1E equipment identified      ii) Inspection will be performed  ii) A report exists and in Table 2.5.5-1 as being qualified for a  of the as-built Class 1E          concludes that the as-built harsh environment can withstand the        equipment and the associated      Class 1E equipment and the environmental conditions that would        wiring, cables, and terminations  associated wiring, cables, and exist before, during, and following a      located in a harsh environment. terminations identified in design basis accident without loss of                                        Table 2.5.5-1 as being safety function, for the time required to                                    qualified for a harsh perform the safety function.                                                  environment are bounded by type tests, analyses, or a combination of type tests and analyses.
571  2.5.05.03b  3.b) The Class 1E cables between the        Inspection of the as-built system The as-built Class 1E cables Incore Thermocouple elements and the        will be performed.                between the Incore connector boxes located on the                                                Thermocouple elements and integrated head package have sheaths.                                        the connector boxes located on the integrated head package have sheaths.
572  2.5.05.03c  3.c) For cables other than those            See ITAAC Table 3.3-6,            See ITAAC Table 3.3-6, covered by 3.b, separation is provided      item 7.d.                        item 7.d.
between IIS Class 1E divisions, and between Class 1E divisions and non-Class 1E cable.
573  2.5.05.04    4. Safety-related displays of the          Inspection will be performed for  Safety-related displays parameters identified in Table 2.5.5-1      retrievability of the safety-    identified in Table 2.5.5-1 can can be retrieved in the MCR.                related displays in the MCR.      be retrieved in the MCR.
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2.5.6          Special Monitoring System Design Description The special monitoring system (SMS) monitors the reactor coolant system (RCS) for the occurrence of impacts characteristic of metallic loose parts. Metal impact monitoring sensors are provided to monitor the RCS at the upper and lower head region of the reactor pressure vessel, and at the reactor coolant inlet region of each steam generator.
: 1. The functional arrangement of the SMS is as described in the Design Description of this Section 2.5.6.
: 2. Data obtained from the metal impact monitoring sensors can be retrieved in the main control room (MCR).
Table 2.5.6-1 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No.            Design Commitment                    Inspections, Tests, Analyses        Acceptance Criteria 574  2.5.06.01  1. The functional arrangement of the        Inspection of the as-built system The as-built SMS conforms SMS is as described in the Design          will be performed.                with the functional Description of this Section 2.5.6.                                            arrangement as described in the Design Description of this Section 2.5.6.
575  2.5.06.02  2. Data obtained from the metal impact      Inspection will be performed for  Data obtained from the metal monitoring sensors can be retrieved in      retrievability of data from the  impact monitoring sensors can the MCR.                                    metal impact monitoring sensors  be retrieved in the MCR.
in the MCR.
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2.5.7          Operation and Control Centers System Design Description The operation and control centers system (OCS) is developed and implemented based upon a human factors engineering (HFE) program. The human system interface (HSI) scope includes the design of the OCS and each of the HSI resources. For the purposes of the HFE program, the OCS includes the main control room, remote shutdown workstation, the local control stations, and the associated workstations for each of these centers. Implementation of the HFE program involves the completion of the human factors engineering analyses and plans described in Tier 1 Material Section 3.2, Human Factors Engineering.
2.5.8          Radiation Monitoring System No entry. Radiation monitoring function covered in Section 3.5, Radiation Monitoring.
2.5.9          Seismic Monitoring System Design Description The seismic monitoring system (SJS) provides for the collection of seismic data in digital format, analysis of seismic data, notification of the operator if the ground motion exceeds a threshold value, and notification of the operator (after analysis of data) that a predetermined cumulative absolute velocity (CAV) has been exceeded. The SJS has at least four triaxial acceleration sensor units and a time-history analyzer and recording system. The time-history analyzer and recording system are located in the auxiliary building.
: 1. The functional arrangement of the SJS is as described in the Design Description of this Section 2.5.9.
: 2. The SJS can compute CAV and the 5 percent of critical damping response spectrum for frequencies between 1 and 10 Hertz.
: 3. The SJS has a dynamic range of 0.001g to 1.0g and a frequency range of 0.2 to 50 Hertz.
Table 2.5.9-1 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No.              Design Commitment                  Inspections, Tests, Analyses        Acceptance Criteria 576  2.5.09.01    1. The functional arrangement of the        Inspection of the as-built system The as-built SJS conforms SJS is as described in the Design          will be performed.                with the functional Description of this Section 2.5.9.                                            arrangement as described in the Design Description of this Section 2.5.9.
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Table 2.5.9-1 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No.            Design Commitment                    Inspections, Tests, Analyses          Acceptance Criteria 577  2.5.09.02 2. The SJS can compute CAV and the 5        Type tests using simulated input  A report exists and concludes percent of critical damping response        signals, analyses, or a          that the SJS time-history spectrum for frequencies between 1 and      combination of type tests and    analyzer and recording system 10 Hz.                                      analyses, of the SJS time-history can record data at a sampling analyzer and recording system    rate of at least 200 samples will be performed.                per second, that the pre-event recording time is adjustable from less than or equal to 1.2 seconds to greater than or equal to 15.0 seconds, and that the initiation value is adjustable from less than or equal to 0.002g to greater than or equal to 0.02g.
578  2.5.09.03 3. The SJS has a dynamic range of            Type tests, analyses, or a        A report exists and concludes 0.001g to 1.0g and a frequency range of      combination of type tests and    that the SJS triaxial 0.2 to 50 Hertz.                            analyses, of the SJS triaxial    acceleration sensors have a acceleration sensors will be      dynamic range of at least performed.                        0.001g to 1.0g and a frequency range of at least 0.2 to 50 Hertz.
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2.5.10          Main Turbine Control and Diagnostic System No entry. Covered in Section 2.4.2, Main Turbine System.
2.5.11          Meteorological and Environmental Monitoring System No entry for this system.
2.5.12          Closed Circuit TV System No entry for this system.
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2.6              Electrical Power Systems 2.6.1            Main ac Power System Design Description The main ac power system (ECS) provides electrical ac power to nonsafety-related loads and non-Class 1E power to the Class 1E battery chargers and regulating transformers during normal and off-normal conditions.
The ECS is as shown in Figures 2.6.1-1 and the component locations of the ECS are as shown in Table 2.6.1-5.
: 1. The functional arrangement of the ECS is as described in the Design Description of this Section 2.6.1.
: 2. The seismic Category I equipment identified in Table 2.6.1-1 can withstand seismic design basis loads without loss of safety function.
: 3. a) The Class 1E breaker control power for the equipment identified in Table 2.6.1-1 are powered from their respective Class 1E division.
b) Separation is provided between ECS Class 1E divisions, and between Class 1E divisions and non-Class 1E cable.
: 4. The ECS provides the following nonsafety-related functions:
a) The ECS provides the capability for distributing non-Class 1E ac power from onsite sources (ZOS) to nonsafety-related loads listed in Table 2.6.1-2.
b) The 6900 Vac circuit breakers in switchgear ECS-ES-1 and ECS-ES-2 open after receiving a signal from the onsite standby power system.
c) Each standby diesel generator 6900 Vac circuit breaker closes after receiving a signal from the onsite standby power system.
d) Each ancillary diesel generator unit is sized to supply power to long-term safety-related post-accident monitoring loads and control room lighting and ventilation through a regulating transformer; and for one passive containment cooling system (PCS) recirculation pump.
e) The ECS provides two loss-of-voltage signals to the onsite standby power system (ZOS), one for each diesel-backed 6900 Vac switchgear bus.
f)  The ECS provides a reverse-power trip of the generator circuit breaker which is blocked for at least 15 seconds following a turbine trip.
: 5. Controls exist in the main control room (MCR) to cause the circuit breakers identified in Table 2.6.1-3 to perform the listed functions.
: 6. Displays of the parameters identified in Table 2.6.1-3 can be retrieved in the MCR.
C-335
 
Table 2.6.1-1 Class 1E/
Seismic    Qual. for    Safety-Related Equipment Name            Tag No.        Category I  Harsh Envir.      Display Reactor Coolant Pump (RCP) Circuit ECS-ES-31          Yes        Yes/No            No Breaker                                                      (Trip open only)
RCP Circuit Breaker                ECS-ES-32          Yes        Yes/No            No (Trip open only)
RCP Circuit Breaker                ECS-ES-41          Yes        Yes/No            No (Trip open only)
RCP Circuit Breaker                ECS-ES-42          Yes        Yes/No            No (Trip open only)
RCP Circuit Breaker                ECS-ES-51          Yes        Yes/No            No (Trip open only)
RCP Circuit Breaker                ECS-ES-52          Yes        Yes/No            No (Trip open only)
RCP Circuit Breaker                ECS-ES-61          Yes        Yes/No            No (Trip open only)
RCP Circuit Breaker                ECS-ES-62          Yes        Yes/No            No (Trip open only)
C-336
 
Table 2.6.1-2 Load Description                      Power Source Load Center Transformers EK-11, EK-12, EK-13, EK-14            ZOS-MG-02A Diesel Oil Transfer Module Enclosure A Electric Unit Heater    ZOS-MG-02A Diesel Oil Transfer Module Enclosure A Fan                      ZOS-MG-02A Class 1E Division A Regulating Transformer                      ZOS-MG-02A Class 1E Division C Regulating Transformer                      ZOS-MG-02A Diesel Generator Fuel Oil Transfer Pump 1A                      ZOS-MG-02A Diesel Generator Room A Building Standby Exhaust Fans 1A and 2A ZOS-MG-02A Diesel Generator Service Module A Air Handling Unit (AHU)      ZOS-MG-02A 01A Fan Startup Feedwater Pump A                                        ZOS-MG-02A Service Water Pump A                                            ZOS-MG-02A Service Water Cooling Tower Fan A                              ZOS-MG-02A MCR/Control Support Area (CSA) AHU A Supply and                ZOS-MG-02A Return Fans Divisions A/C Class 1E Electrical Room AHU A Supply and        ZOS-MG-02A Return Fans Divisions B/D Class 1E Electrical Room AHU D Supply and        ZOS-MG-02A Return Fans Air-cooled Chiller Pump 2                                      ZOS-MG-02A Component Cooling Water Pump 1A                                ZOS-MG-02A Air-cooled Chiller 2                                            ZOS-MG-02A Chemical and Volume Control System (CVS) Makeup Pump 1A        ZOS-MG-02A CVS Pump Room Unit Cooler Fan A                                ZOS-MG-02A Normal Residual Heat Removal System (RNS) Pump 1A              ZOS-MG-02A RNS Pump Room Unit Cooler Fan A                                ZOS-MG-02A Equipment Room AHU Supply and Return Fans VXS-MA-01A/02A        ZOS-MG-02A Switchgear Room A AHU Supply and Return Fans VXS-MA-05A/06A    ZOS-MG-02A Non-1E Battery Charger EDS1-DC-1                                ZOS-MG-02A Non-1E Battery Room A Exhaust Fan                              ZOS-MG-02A Non-1E Battery Charger EDS3-DC-1                                ZOS-MG-02A C-337
 
Table 2.6.1-2 (cont.)
Load Description                        Power Source Class 1E Division A Battery Charger 1 (24-hour)                  ZOS-MG-02A Class 1E Division C Battery Charger 1 (24-hour)                  ZOS-MG-02A Class 1E Division C Battery Charger 2 (72-hour)                  ZOS-MG-02A Divisions A/C Class 1E Battery Room Exhaust Fan A                ZOS-MG-02A Supplemental Air Filtration Unit Fan A                            ZOS-MG-02A Backup Group 4A Pressurizer Heaters                              ZOS-MG-02A Spent Fuel Cooling Pump 1A                                        ZOS-MG-02A Load Center Transformers EK-21, EK-22, EK-23, EK-24              ZOS-MG-02B Diesel Oil Transfer Module Enclosure B Electric Unit Heater      ZOS-MG-02B Diesel Oil Transfer Module Enclosure B Fan                        ZOS-MG-02B Class 1E Division B Regulating Transformer                        ZOS-MG-02B Class 1E Division D Regulating Transformer                        ZOS-MG-02B Diesel Generator Fuel Oil Transfer Pump 1B                        ZOS-MG-02B Diesel Generator Room B Building Standby Exhaust Fans 1B and 2B  ZOS-MG-02B Diesel Generator Service Module B AHU 01B Fan                    ZOS-MG-02B Startup Feedwater Pump B                                          ZOS-MG-02B Service Water Pump B                                              ZOS-MG-02B Service Water Cooling Tower Fan B                                ZOS-MG-02B MCR/CSA AHU B Supply and Return Fans                              ZOS-MG-02B Divisions B/D Class 1E Electrical Room AHU B Supply and          ZOS-MG-02B Return Fans Divisions A/C Class 1E Electrical Room AHU C Supply and          ZOS-MG-02B Return Fans Air-cooled Chiller Pump 3                                        ZOS-MG-02B Component Cooling Water Pump 1B                                  ZOS-MG-02B Air-cooled Chiller 3                                              ZOS-MG-02B CVS Makeup Pump 1B                                                ZOS-MG-02B CVS Pump Room Unit Cooler Fan B                                  ZOS-MG-02B RNS Pump 1B                                                      ZOS-MG-02B RNS Pump Room Unit Cooler Fan B                                  ZOS-MG-02B Equipment Room B AHU Supply and Return Fans VXS-MA-01B/02B        ZOS-MG-02B C-338
 
Table 2.6.1-2 (cont.)
Load Description                                      Power Source Switchgear Room B AHU Supply and Return Fans VXS-MA-05B/06B                    ZOS-MG-02B Non-1E Battery Charger EDS2-DC-1                                                ZOS-MG-02B Non-1E Battery Charger EDS4-DC-1                                                ZOS-MG-02B Non-1E Battery Room B Exhaust Fan                                              ZOS-MG-02B Class 1E Division B Battery Charger 1 (24-hour)                                ZOS-MG-02B Class 1E Division B Battery Charger 2 (72-hour)                                ZOS-MG-02B Class 1E Division D Battery Charger 1 (24-hour)                                ZOS-MG-02B Divisions B/D Class 1E Battery Room Exhaust Fan B                              ZOS-MG-02B Supplemental Air Filtration Unit Fan B                                          ZOS-MG-02B Backup Group 4B Pressurizer Heaters                                            ZOS-MG-02B Spent Fuel Cooling Pump 1B                                                      ZOS-MG-02B Table 2.6.1-3 Equipment                Tag No.                  Display                Control Function 6900 V Switchgear Bus 1        ECS-ES-1                      Yes                        Yes (Bus voltage, breaker position for  (Breaker open/close) all breakers on bus) 6900 V Switchgear Bus 2        ECS-ES-2                      Yes                        Yes (Bus voltage, breaker position for  (Breaker open/close) all breakers on bus)
Unit Auxiliary                ZAS-ET-2A                      Yes                        No Transformer A                                      (Secondary Voltage)
Unit Auxiliary                ZAS-ET-2B                      Yes                        No Transformer B                                      (Secondary Voltage)
Reserve Auxiliary              ZAS-ET-4A                      Yes                        No Transformer A                                      (Secondary Voltage)
Reserve Auxiliary              ZAS-ET-4B                      Yes                        No Transformer B                                      (Secondary Voltage)
C-339
 
Table 2.6.1-4 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No.              Design Commitment                    Inspections, Tests, Analyses        Acceptance Criteria 579    2.6.01.01  1. The functional arrangement of the        Inspection of the as-built system  The as-built ECS conforms ECS is as described in the Design            will be performed.                with the functional Description of this Section 2.6.1.                                              arrangement as described in the Design Description of this Section 2.6.1.
580  2.6.01.02.i  2. The seismic Category I equipment          i) Inspection will be performed    i) The seismic Category I identified in Table 2.6.1-1 can withstand    to verify that the seismic        equipment identified in seismic design basis loads without loss      Category I equipment identified    Table 2.6.1-1 is located on the of safety function.                          in Table 2.6.1-1 is located on the Nuclear Island.
Nuclear Island.
581  2.6.01.02.ii 2. The seismic Category I equipment          ii) Type tests, analyses, or a    ii) A report exists and identified in Table 2.6.1-1 can withstand    combination of type tests and      concludes that the seismic seismic design basis loads without loss      analyses of seismic Category I    Category I equipment can of safety function.                          equipment will be performed.      withstand seismic design basis loads without loss of safety function.
582  2.6.01.02.iii 2. The seismic Category I equipment          iii) Inspection will be performed  iii) A report exists and identified in Table 2.6.1-1 can withstand    for the existence of a report      concludes that the as-built seismic design basis loads without loss      verifying that the as-built        equipment including of safety function.                          equipment including anchorage      anchorage is seismically is seismically bounded by the      bounded by the tested or tested or analyzed conditions. analyzed conditions.
583  2.6.01.03a  3.a) The Class 1E breaker control            Testing will be performed on the  A simulated test signal exists power for the equipment identified in        ECS by providing a simulated      at the Class 1E equipment Table 2.6.1-1 are powered from their        test signal in each Class 1E      identified in Table 2.6.1-1 respective Class 1E division.                division.                          when the assigned Class 1E division is provided the test signal.
584  2.6.01.03b  3.b) Separation is provided between          See ITAAC Table 3.3-6,            See ITAAC Table 3.3-6, ECS Class 1E divisions, and between          item 7.d.                          item 7.d.
Class 1E divisions and non-Class 1E cable.
585  2.6.01.04a  4.a) The ECS provides the capability        Tests will be performed using a    A test signal exists at the for distributing non-Class 1E ac power      test signal to confirm that an    terminals of each selected from onsite sources (ZOS) to nonsafety-      electrical path exists for each    load.
related loads listed in Table 2.6.1-2.      selected load listed in Table 2.6.1-2 from an ECS-ES-1 or ECS-ES-2 bus. Each test may be a single test or a series of over-lapping tests.
586  2.6.01.04b  4.b) The 6900 Vac circuit breakers in        See ITAAC Table 2.6.4-1,          See ITAAC Table 2.6.4-1, switchgear ECS-ES-1 and ECS-ES-2            item 2.a.                          item 2.a.
open after receiving a signal from the onsite standby power load system.
C-340
 
Table 2.6.1-4 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No.              Design Commitment                  Inspections, Tests, Analyses          Acceptance Criteria 587  2.6.01.04c 4.c) Each standby diesel generator          Testing will be performed using    Each standby diesel generator 6900 Vac circuit breaker closes after        real or simulated signals from    6900 Vac circuit breaker receiving a signal from the onsite          the standby diesel load system. closes after receiving a signal standby power system.                                                          from the standby diesel system.
588  2.6.01.04d 4.d) Each ancillary diesel generator        Each ancillary diesel generator    Each diesel generator provides unit is sized to supply power to long-      will be operated with fuel        power to the load with a term safety-related post-accident            supplied from the ancillary        generator terminal voltage of monitoring loads and control room            diesel generator fuel tank and    480 +/- 10% volts and a lighting and ventilation through a          with a load of 35 kW or greater    frequency of 60 +/- 5% Hz.
regulating transformer; and for one PCS      and a power factor between recirculation pump.                          0.9 and 1.0 for a time period required to reach engine temperature equilibrium plus 2.5 hours.
589  2.6.01.04e 4.e) The ECS provides two loss-of-          Tests on the as-built ECS system  A loss-of-voltage signal is voltage signals to the onsite standby        will be conducted by simulating    generated when the loss-of-power system (ZOS), one for each            a loss-of-voltage condition on    voltage condition is simulated.
diesel-backed 6900 Vac switchgear bus.      each diesel-backed 6900 Vac switchgear bus.
590  2.6.01.04f 4.f) The ECS provides a reverse-power        Tests on the as-built ECS system  The generator circuit breaker trip of the generator circuit breaker        will be conducted by simulating    trip signal does not occur until which is blocked for at least 15 seconds    a turbine trip signal followed by  at least 15 seconds after the following a turbine trip.                    a simulated reverse-power          simulated turbine trip.
condition. The generator circuit breaker trip signal will be monitored.
591  2.6.01.05  5. Controls exist in the MCR to cause        Tests will be performed to verify  Controls in the MCR cause the circuit breakers identified in          that controls in the MCR can      the circuit breakers identified Table 2.6.1-3 to perform the listed          operate the circuit breakers      in Table 2.6.1-3 to operate.
functions.                                  identified in Table 2.6.1-3.
592  2.6.01.06  6. Displays of the parameters identified    Inspection will be performed for  Displays identified in in Table 2.6.1-3 can be retrieved in the    retrievability of the displays    Table 2.6.1-3 can be retrieved MCR.                                        identified in Table 2.6.1-3 in the in the MCR.
MCR.
C-341
 
Table 2.6.1-5 Component Name                                Tag No. Component Location RCP Circuit Breaker                                          ECS-ES-31  Auxiliary Building RCP Circuit Breaker                                          ECS-ES-32  Auxiliary Building RCP Circuit Breaker                                          ECS-ES-41  Auxiliary Building RCP Circuit Breaker                                          ECS-ES-42  Auxiliary Building RCP Circuit Breaker                                          ECS-ES-51  Auxiliary Building RCP Circuit Breaker                                          ECS-ES-52  Auxiliary Building RCP Circuit Breaker                                          ECS-ES-61  Auxiliary Building RCP Circuit Breaker                                          ECS-ES-62  Auxiliary Building 6900 V Switchgear Bus 1                                        ECS-ES-1  Annex Building 6900 V Switchgear Bus 2                                        ECS-ES-2  Annex Building 6900 V Switchgear Bus 3                                        ECS-ES-3  Turbine Building 6900 V Switchgear Bus 4                                        ECS-ES-4  Turbine Building 6900 V Switchgear Bus 5                                        ECS-ES-5  Turbine Building 6900 V Switchgear Bus 6                                        ECS-ES-6  Turbine Building Main Generator                                                ZAS-MG-01  Turbine Building Generator Circuit Breaker                                    ZAS-ES-01  Turbine Building Main Step-up Transformer                                      ZAS-ET-1A        Yard Main Step-up Transformer                                      ZAS-ET-1B        Yard Main Step-up Transformer                                      ZAS-ET-1C        Yard Unit Auxiliary Transformer A                                  ZAS-ET-2A        Yard Unit Auxiliary Transformer B                                  ZAS-ET-2B        Yard Reserve Auxiliary Transformer A                              ZAS-ET-4A        Yard Reserve Auxiliary Transformer B                              ZAS-ET-4B        Yard Ancillary Diesel Generator #1                                ECS-MG-01  Annex Building Ancillary Diesel Generator #2                                ECS-MG-02  Annex Building Ancillary Diesel Generator Distribution Panel 1              ECS-ED-01  Annex Building Ancillary Diesel Generator Distribution Panel 1              ECS-ED-02  Annex Building C-342
 
Figure 2.6.1-1 (Sheet 1 of 4)
Main ac Power System C-343
 
Figure 2.6.1-1 (Sheet 2 of 4)
Main ac Power System C-344
 
Figure 2.6.1-1 (Sheet 3 of 4)
Main ac Power System C-345
 
Figure 2.6.1-1 (Sheet 4 of 4)
Main ac Power System C-346
 
2.6.2            Non-Class 1E dc and Uninterruptible Power Supply System Design Description The non-Class 1E dc and uninterruptible power supply system (EDS) provides dc and uninterruptible ac electrical power to nonsafety-related loads during normal and off-normal conditions.
The EDS is as shown in Figure 2.6.2-1 and the component locations of the EDS are as shown in Table 2.6.2-2.
: 1. The functional arrangement of the EDS is as described in the Design Description of this Section 2.6.2.
: 2. The EDS provides the following nonsafety-related functions:
a) Each EDS load group 1, 2, 3, and 4 battery charger supplies the corresponding dc switchboard bus load while maintaining the corresponding battery charged.
b) Each EDS load group 1, 2, 3, and 4 battery supplies the corresponding dc switchboard bus load for a period of 2 hours without recharging.
c) Each EDS load group 1, 2, 3, and 4 inverter supplies the corresponding ac load.
Table 2.6.2-1 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No.                Design Commitment                  Inspections, Tests, Analyses        Acceptance Criteria 593    2.6.02.01    1. The functional arrangement of the        Inspection of the as-built system The as-built EDS conforms EDS is as described in the Design          will be performed.                with the functional Description of this Section 2.6.2.                                            arrangement as described in the Design Description of this Section 2.6.2.
594  2.6.02.02a    2.a) Each EDS load group 1, 2, 3, and      Testing of each as-built battery  Each battery charger provides 4 battery charger supplies the              charger will be performed by      an output current of at least corresponding dc switchboard bus load      applying a simulated or real      550 amps with an output while maintaining the corresponding        load, or a combination of        voltage in the range 105 to battery charged.                            simulated or real loads.          140 V.
595  2.6.02.02b    2.b) Each EDS load group 1, 2, 3, and      Testing of each as-built battery  The battery terminal voltage is 4 battery supplies the corresponding dc    will be performed by applying a  greater than or equal to 105 V switchboard bus load for a period of        simulated or real load, or a      after a period of no less than 2 hours without recharging.                combination of simulated or real  2 hours, with an equivalent loads. The test will be          load greater than 500 amps.
conducted on a battery that has been fully charged and has been connected to a battery charger maintained at 135 +/- 1 V for a period of no less than 24 hours prior to the test.
C-347
 
Table 2.6.2-1 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No.              Design Commitment                    Inspections, Tests, Analyses          Acceptance Criteria 596  2.6.02.02c  2.c) Each EDS load group 1, 2, 3, and      Testing of each as-built inverter  Each inverter provides a line-4 inverter supplies the corresponding ac    will be performed by applying a    to-line output voltage of load.                                      simulated or real load, or a        208 +/- 2% V at a frequency of combination of simulated or real    60 +/- 0.5% Hz.
loads, equivalent to a resistive load greater than 35 kW.
Table 2.6.2-2 Component Name                                    Tag No.                Component Location Load Group 1 Battery                                            EDS1-DB-1                  Annex Building Load Group 2 Battery                                            EDS2-DB-1                  Annex Building Load Group 3 Battery                                            EDS3-DB-1                  Annex Building Load Group 4 Battery                                            EDS4-DB-1                  Annex Building Load Group 1 Battery Charger                                    EDS1-DC-1                  Annex Building Load Group 2 Battery Charger                                    EDS2-DC-1                  Annex Building Load Group 3 Battery Charger                                    EDS3-DC-1                  Annex Building Load Group 4 Battery Charger                                    EDS4-DC-1                  Annex Building Load Group 1 125 Vdc Switchboard                                EDS1-DS-1                  Annex Building Load Group 1 125 Vdc Switchboard                                EDS1-DS-11                Annex Building Load Group 2 125 Vdc Switchboard                                EDS2-DS-1                  Annex Building Load Group 2 125 Vdc Switchboard                                EDS2-DS-11                Annex Building Load Group 3 125 Vdc Switchboard                                EDS3-DS-1                  Annex Building Load Group 3 125 Vdc Switchboard                                EDS3-DS-11                Annex Building Load Group 4 125 Vdc Switchboard                                EDS4-DS-1                  Annex Building Load Group 4 125 Vdc Switchboard                                EDS4-DS-11                Annex Building Load Group 1 Inverter                                            EDS1-DU-1                  Annex Building Load Group 2 Inverter                                            EDS2-DU-1                  Annex Building Load Group 3 Inverter                                            EDS3-DU-1                  Annex Building Load Group 4 Inverter                                            EDS4-DU-1                  Annex Building C-348
 
Figure 2.6.2-1 (Sheet 1 of 2)
Non-Class 1E dc and Uninterruptible Power Supply System C-349
 
Figure 2.6.2-1 (Sheet 2 of 2)
Non-Class 1E dc and Uninterruptible Power Supply System C-350
 
2.6.3          Class 1E dc and Uninterruptible Power Supply System Design Description The Class 1E dc and uninterruptible power supply system (IDS) provides dc and uninterruptible ac electrical power for safety-related equipment during normal and off-normal conditions.
The IDS is as shown in Figure 2.6.3-1 and the component locations of the IDS are as shown in Table 2.6.3-4.
: 1. The functional arrangement of the IDS is as described in the Design Description of this Section 2.6.3.
: 2. The seismic Category I equipment identified in Table 2.6.3-1 can withstand seismic design basis loads without loss of safety function.
: 3. Separation is provided between Class 1E divisions, and between Class 1E divisions and non-Class 1E cables.
: 4. The IDS provides the following safety-related functions:
a) The IDS provides electrical independence between the Class 1E divisions.
b) The IDS provides electrical isolation between the non-Class 1E ac power system and the non-Class 1E lighting in the MCR.
c) Each IDS 24-hour battery bank supplies a dc switchboard bus load for a period of 24 hours without recharging.
d) Each IDS 72-hour battery bank supplies a dc switchboard bus load for a period of 72 hours without recharging.
e) The IDS spare battery bank supplies a dc load equal to or greater than the most severe switchboard bus load for the required period without recharging.
f) Each IDS 24-hour inverter supplies its ac load.
g) Each IDS 72-hour inverter supplies its ac load.
h) Each IDS 24-hour battery charger provides the protection and safety monitoring system (PMS) with two loss-of-ac input voltage signals.
i) The IDS supplies an operating voltage at the terminals of the Class 1E motor-operated valves identified in subsections 2.1.2, 2.2.1, 2.2.2, 2.2.3, 2.2.4, 2.3.2, and 2.3.6 that is greater than or equal to the minimum specified voltage.
: 5. The IDS provides the following nonsafety-related functions:
a) Each IDS 24-hour battery charger supplies a dc switchboard bus load while maintaining the corresponding battery charged.
b) Each IDS 72-hour battery charger supplies a dc switchboard bus load while maintaining the corresponding battery charged.
c) Each IDS regulating transformer supplies an ac load when powered from the 480 V motor control center (MCC).
C-351
 
d) The IDS Divisions B and C regulating transformers supply their post-72 hour ac loads when powered from an ancillary diesel generator.
: 6. Safety-related displays identified in Table 2.6.3-1 can be retrieved in the MCR.
: 7. The IDS dc battery fuses and battery charger circuit breakers, and dc distribution panels, MCCs, and their circuit breakers and fuses, are sized to supply their load requirements.
: 8. Circuit breakers and fuses in IDS battery, battery charger, dc distribution panel, and MCC circuits are rated to interrupt fault currents.
: 9. The IDS batteries, battery chargers, dc distribution panels, and MCCs are rated to withstand fault currents for the time required to clear the fault from its power source.
: 10. The IDS electrical distribution system cables are rated to withstand fault currents for the time required to clear the fault from its power source.
: 11. Displays of the parameters identified in Table 2.6.3-2 can be retrieved in the MCR.
Table 2.6.3-1 Class 1E/    Safety-Seismic    Qual. for    Related Equipment Name                      Tag No.        Cat. I    Harsh Envir. Display Division A 250 Vdc 24-Hour Battery Bank        IDSA-DB-1          Yes      Yes/No          No Division B 250 Vdc 24-Hour Battery Bank 1      IDSB-DB-1          Yes      Yes/No          No Division B 250 Vdc 72-Hour Battery Bank 2      IDSB-DB-2          Yes      Yes/No          No Division C 250 Vdc 24-Hour Battery Bank 1      IDSC-DB-1          Yes      Yes/No          No Division C 250 Vdc 72-Hour Battery Bank 2      IDSC-DB-2          Yes      Yes/No          No Division D 250 Vdc 24-Hour Battery Bank        IDSD-DB-1          Yes      Yes/No          No Spare 250 Vdc Battery Bank                    IDSS-DB-1          Yes      Yes/No          No Division A 24-Hour Battery Charger 1          IDSA-DC-1          Yes      Yes/No          No Division B 24-Hour Battery Charger 1          IDSB-DC-1          Yes      Yes/No          No Division B 72-Hour Battery Charger 2          IDSB-DC-2          Yes      Yes/No          No Division C 24-Hour Battery Charger 1          IDSC-DC-1          Yes      Yes/No          No Division C 72-Hour Battery Charger 2          IDSC-DC-2          Yes      Yes/No          No Division D 24-Hour Battery Charger 1          IDSD-DC-1          Yes      Yes/No          No Spare Battery Charger 1                        IDSS-DC-1          Yes      Yes/No          No Division A 250 Vdc Distribution Panel          IDSA-DD-1          Yes      Yes/No          No Division B 250 Vdc Distribution Panel          IDSB-DD-1          Yes      Yes/No          No Division C 250 Vdc Distribution Panel          IDSC-DD-1          Yes      Yes/No          No C-352
 
Table 2.6.3-1 Class 1E/  Safety-Seismic  Qual. for  Related Equipment Name                Tag No. Cat. I Harsh Envir. Display Division D 250 Vdc Distribution Panel    IDSD-DD-1      Yes    Yes/No      No Division A 120 Vac Distribution Panel 1  IDSA-EA-1      Yes    Yes/No      No Division A 120 Vac Distribution Panel 2  IDSA-EA-2      Yes    Yes/No      No Division B 120 Vac Distribution Panel 1  IDSB-EA-1      Yes    Yes/No      No Division B 120 Vac Distribution Panel 2  IDSB-EA-2      Yes    Yes/No      No Division B 120 Vac Distribution Panel 3  IDSB-EA-3      Yes    Yes/No      No Division C 120 Vac Distribution Panel 1  IDSC-EA-1      Yes    Yes/No      No Division C 120 Vac Distribution Panel 2  IDSC-EA-2      Yes    Yes/No      No Division C 120 Vac Distribution Panel 3  IDSC-EA-3      Yes    Yes/No      No Division D 120 Vac Distribution Panel 1  IDSD-EA-1      Yes    Yes/No      No Division D 120 Vac Distribution Panel 2  IDSD-EA-2      Yes    Yes/No      No Division A Fuse Panel 4                  IDSA-EA-4      Yes    Yes/No      No Division B Fuse Panel 4                  IDSB-EA-4      Yes    Yes/No      No Division B Fuse Panel 5                  IDSB-EA-5      Yes    Yes/No      No Division B Fuse Panel 6                  IDSB-EA-6      Yes    Yes/No      No Division C Fuse Panel 4                  IDSC-EA-4      Yes    Yes/No      No Division C Fuse Panel 5                  IDSC-EA-5      Yes    Yes/No      No Division C Fuse Panel 6                  IDSC-EA-6      Yes    Yes/No      No Division D Fuse Panel 4                  IDSD-EA-4      Yes    Yes/No      No Division A Fused Transfer Switch Box 1  IDSA-DF-1      Yes    Yes/No      No Division B Fused Transfer Switch Box 1  IDSB-DF-1      Yes    Yes/No      No Division B Fused Transfer Switch Box 2  IDSB-DF-2      Yes    Yes/No      No Division C Fused Transfer Switch Box 1  IDSC-DF-1      Yes    Yes/No      No Division C Fused Transfer Switch Box 2  IDSC-DF-2      Yes    Yes/No      No Division D Fused Transfer Switch Box 1  IDSD-DF-1      Yes    Yes/No      No Spare Fused Transfer Switch Box 1        IDSS-DF-1    Yes    Yes/No      No Spare Battery 125/250 Vdc Disconnect    IDSS-SW-1      Yes    Yes/No      No Switch Division A 250 Vdc MCC                  IDSA-DK-1      Yes    Yes/No      No C-353
 
Table 2.6.3-1 Class 1E/  Safety-Seismic  Qual. for  Related Equipment Name          Tag No. Cat. I Harsh Envir. Display Division B 250 Vdc MCC            IDSB-DK-1      Yes    Yes/No      No Division C 250 Vdc MCC            IDSC-DK-1      Yes    Yes/No      No Division D 250 Vdc MCC            IDSD-DK-1      Yes    Yes/No      No Division A 250 Vdc Switchboard 1  IDSA-DS-1      Yes    Yes/No    Yes (Bus Voltage)
Division B 250 Vdc Switchboard 1  IDSB-DS-1      Yes    Yes/No    Yes (Bus Voltage)
Division B 250 Vdc Switchboard 2  IDSB-DS-2      Yes    Yes/No    Yes (Bus Voltage)
Division C 250 Vdc Switchboard 1  IDSC-DS-1      Yes    Yes/No    Yes (Bus Voltage)
Division C 250 Vdc Switchboard 2  IDSC-DS-2      Yes    Yes/No    Yes (Bus Voltage)
Division D 250 Vdc Switchboard 1  IDSD-DS-1      Yes    Yes/No    Yes (Bus Voltage)
Division A Regulating Transformer  IDSA-DT-1      Yes    Yes/No      No Division B Regulating Transformer  IDSB-DT-1      Yes    Yes/No      No Division C Regulating Transformer  IDSC-DT-1      Yes    Yes/No      No Division D Regulating Transformer  IDSD-DT-1      Yes    Yes/No      No Division A 24-Hour Inverter 1      IDSA-DU-1      Yes    Yes/No      No Division B 24-Hour Inverter 1      IDSB-DU-1      Yes    Yes/No      No Division B 72-Hour Inverter 2      IDSB-DU-2      Yes    Yes/No      No Division C 24-Hour Inverter 1      IDSC-DU-1      Yes    Yes/No      No Division C 72-Hour Inverter 2      IDSC-DU-2      Yes    Yes/No      No Division D 24-Hour Inverter 1      IDSD-DU-1      Yes    Yes/No      No Spare Termination Box 2            IDSS-DF-2    Yes    Yes/No      No Spare Termination Box 3            IDSS-DF-3    Yes    Yes/No      No Spare Termination Box 4            IDSS-DF-4    Yes    Yes/No      No Spare Termination Box 5            IDSS-DF-5    Yes    Yes/No      No Spare Termination Box 6            IDSS-DF-6    Yes    Yes/No      No C-354
 
Table 2.6.3-2 Equipment                        Tag No.      Display/Status Indication Division A Battery Monitor        IDSA-DV-1                          Yes (Battery Ground Detection, Battery High Discharge Rate)
Division B 24-Hour Battery        IDSB-DV-1                          Yes Monitor                                                  (Battery Ground Detection, Battery High Discharge Rate)
Division B 72-Hour Battery        IDSB-DV-2                          Yes Monitor                                                  (Battery Ground Detection, Battery High Discharge Rate)
Division C 24-Hour Battery        IDSC-DV-1                          Yes Monitor                                                  (Battery Ground Detection, Battery High Discharge Rate)
Division C 72-Hour Battery        IDSC-DV-2                          Yes Monitor                                                  (Battery Ground Detection, Battery High Discharge Rate)
Division D Battery Monitor        IDSD-DV-1                          Yes (Battery Ground Detection, Battery High Discharge Rate)
Division A Fused Transfer Switch  IDSA-DF-1                          Yes Box                                                        (Battery Current, Battery Disconnect Switch Position)
Division B 24-Hour Fused Transfer IDSB-DF-1                          Yes Switch Box                                                (Battery Current, Battery Disconnect Switch Position)
Division B 72-Hour Fused Transfer IDSB-DF-2                          Yes Switch Box                                                (Battery Current, Battery Disconnect Switch Position)
Division C 24-Hour Fused Transfer IDSC-DF-1                          Yes Switch Box                                                (Battery Current, Battery Disconnect Switch Position)
Division C 72-Hour Fused Transfer IDSC-DF-2                          Yes Switch Box                                                (Battery Current, Battery Disconnect Switch Position)
Division D Fused Transfer        IDSD-DF-1                          Yes Switch Box                                                (Battery Current, Battery Disconnect Switch Position)
Division A Battery Charger        IDSA-DC-1                          Yes (Charger Output Current, Charger Trouble(1))
C-355
 
Table 2.6.3-2 Equipment                                Tag No.                      Display/Status Indication Division B 24-Hour Battery              IDSB-DC-1                                              Yes Charger                                                                            (Charger Output Current, Charger Trouble(1))
Division B 72-Hour Battery              IDSB-DC-2                                              Yes Charger                                                                            (Charger Output Current, Charger Trouble(1))
Division C 24-Hour Battery              IDSC-DC-1                                              Yes Charger                                                                            (Charger Output Current, Charger Trouble(1))
Division C 72-Hour Battery              IDSC-DC-2                                              Yes Charger                                                                            (Charger Output Current, Charger Trouble(1))
Division D Battery Charger              IDSD-DC-1                                              Yes (Charger Output Current, Charger Trouble(1))
Note: (1) Battery charger trouble includes charger dc output under/over voltage Table 2.6.3-3 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No.                  Design Commitment                    Inspections, Tests, Analyses          Acceptance Criteria 597    2.6.03.01      1. The functional arrangement of the        Inspection of the as-built system    The as-built IDS conforms IDS is as described in the Design          will be performed.                  with the functional Description of this Section 2.6.3.                                              arrangement as described in the Design Description of this Section 2.6.3.
598  2.6.03.02.i    2. The seismic Category I equipment        i) Inspection will be performed      i) The seismic Category I identified in Table 2.6.3-1 can withstand  to verify that the seismic          equipment identified in seismic design basis loads without loss    Category I equipment identified      Table 2.6.3-1 is located on the of safety function.                        in Table 2.6.3-1 is located on the  Nuclear Island.
Nuclear Island.
599  2.6.03.02.ii    2. The seismic Category I equipment        ii) Type tests, analyses, or a      ii) A report exists and identified in Table 2.6.3-1 can withstand  combination of type tests and        concludes that the seismic seismic design basis loads without loss    analyses of seismic Category I      Category I equipment can of safety function.                        equipment will be performed.        withstand seismic design basis loads without loss of safety function.
C-356
 
Table 2.6.3-3 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No.              Design Commitment                    Inspections, Tests, Analyses        Acceptance Criteria 600  2.6.03.02.iii 2. The seismic Category I equipment        iii) Inspection will be performed iii) A report exists and identified in Table 2.6.3-1 can withstand  for the existence of a report    concludes that the as-built seismic design basis loads without loss    verifying that the as-built      equipment including of safety function.                        equipment including anchorage    anchorage is seismically is seismically bounded by the    bounded by the tested or tested or analyzed conditions. analyzed conditions.
601  2.6.03.03    3. Separation is provided between          See ITAAC Table 3.3-6,            See ITAAC Table 3.3-6, Class 1E divisions, and between            item 7.d.                        item 7.d.
Class 1E divisions and non-Class 1E cables.
602  2.6.03.04a  4.a) The IDS provides electrical            Testing will be performed on the  A simulated test signal exists independence between the Class 1E          IDS by providing a simulated      at the Class 1E equipment divisions.                                  test signal in each Class 1E      identified in Table 2.6.3-1 division.                        when the assigned Class 1E division is provided the test signal.
603  2.6.03.04b  4.b) The IDS provides electrical            Type tests, analyses, or a        A report exists and concludes isolation between the non-Class 1E ac      combination of type tests and    that the battery chargers, power system and the non-Class 1E          analyses of the isolation devices regulating transformers, and lighting in the MCR.                        will be performed.                isolation fuses prevent credible faults from propagating into the IDS.
604  2.6.03.04c  4.c) Each IDS 24-hour battery bank          Testing of each 24-hour as-built  The battery terminal voltage is supplies a dc switchboard bus load for a    battery bank will be performed    greater than or equal to 210 V period of 24 hours without recharging.      by applying a simulated or real  after a period of no less than load, or a combination of        24 hours with an equivalent simulated or real loads which    load that equals or exceeds the envelope the battery bank design  battery bank design duty cycle duty cycle. The test will be      capacity.
conducted on a battery bank that has been fully charged and has been connected to a battery charger maintained at 270+/-2 V for a period of no less than 24 hours prior to the test.
C-357
 
Table 2.6.3-3 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No.            Design Commitment                    Inspections, Tests, Analyses        Acceptance Criteria 605  2.6.03.04d 4.d) Each IDS 72-hour battery bank          Testing of each 72-hour as-built The battery terminal voltage is supplies a dc switchboard bus load for a    battery bank will be performed  greater than or equal to 210 V period of 72 hours without recharging.      by applying a simulated or real  after a period of no less than load, or a combination of        72 hours with an equivalent simulated or real loads which    load that equals or exceeds the envelope the battery bank design battery bank design duty cycle duty cycle. The test will be    capacity.
conducted on a battery bank that has been fully charged and has been connected to a battery charger maintained at 270+/-2 V for a period of no less than 24 hours prior to the test.
606  2.6.03.04e 4.e) The IDS spare battery bank              Testing of the as-built spare    The battery terminal voltage is supplies a dc load equal to or greater      battery bank will be performed  greater than or equal to 210 V than the most severe switchboard bus        by applying a simulated or real  after a period with a load and load for the required period without        load, or a combination of        duration that equals or recharging.                                  simulated or real loads which    exceeds the most severe envelope the most severe of the  battery bank design duty cycle division batteries design duty  capacity.
cycle. The test will be conducted on a battery bank that has been fully charged and has been connected to a battery charger maintained at 270+/-2 V for a period of no less than 24 hours prior to the test.
607  2.6.03.04f 4.f) Each IDS 24-hour inverter supplies      Testing of each 24-hour as-built Each 24-hour inverter supplies its ac load.                                inverter will be performed by    a line-to-line output voltage of applying a simulated or real    208 +/- 2% V at a frequency of load, or a combination of        60 +/- 0.5% Hz.
simulated or real loads, equivalent to a resistive load greater than 12 kW. The inverter input voltage will be no more than 210 Vdc during the test.
608  2.6.03.04g 4.g) Each IDS 72-hour inverter              Testing of each 72-hour as-built Each 72-hour inverter supplies supplies its ac load.                        inverter will be performed by    a line-to-line output voltage of applying a simulated or real    208 +/- 2% V at a frequency of load, or a combination of        60 +/- 0.5% Hz.
simulated or real loads, equivalent to a resistive load greater than 7 kW. The inverter input voltage will be no more than 210 Vdc during the test.
C-358
 
Table 2.6.3-3 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No.              Design Commitment                    Inspections, Tests, Analyses          Acceptance Criteria 609  2.6.03.04h  4.h) Each IDS 24-hour battery charger        Testing will be performed by      Two PMS input signals exist provides the PMS with two loss-of-ac          simulating a loss of input voltage from each 24-hour battery input voltage signals.                        to each 24-hour battery charger. charger indicating loss of ac input voltage when the loss-of-input voltage condition is simulated.
610  2.6.03.04i  4.i) The IDS supplies an operating            Testing will be performed by      The motor starter input voltage at the terminals of the Class 1E      stroking each specified motor-    terminal voltage is greater motor operated valves identified in          operated valve and measuring      than or equal 200 Vdc with subsections 2.1.2, 2.2.1, 2.2.2, 2.2.3,      the terminal voltage at the motor  the motor operating.
2.2.4, 2.3.2, and 2.3.6 that is greater      starter input terminals with the than or equal to the minimum specified        motor operating. The battery voltage.                                      terminal voltage will be no more than 210 Vdc during the test.
611  2.6.03.05a  5.a) Each IDS 24-hour battery charger        Testing of each as-built 24-hour  Each 24-hour battery charger supplies a dc switchboard bus load            battery charger will be            provides an output current of while maintaining the corresponding          performed by applying a            at least 150 A with an output battery charged.                              simulated or real load, or a      voltage in the range 210 to combination of simulated or real  280 V.
loads.
612  2.6.03.05b  5.b) Each IDS 72-hour battery charger        Testing of each 72-hour as-built  Each 72-hour battery charger supplies a dc switchboard bus load            battery charger will be            provides an output current of while maintaining the corresponding          performed by applying a            at least 125 A with an output battery charged.                              simulated or real load, or a      voltage in the range 210 to combination of simulated or real  280 V.
loads.
613  2.6.03.05c  5.c) Each IDS regulating transformer          Testing of each as-built          Each regulating transformer supplies an ac load when powered from        regulating transformer will be    supplies a line-to-line output the 480 V MCC.                                performed by applying a            voltage of 208 +/- 2% V.
simulated or real load, or a combination of simulated or real loads, equivalent to a resistive load greater than 30 kW when powered from the 480 V MCC.
614  2.6.03.05d.i  5.d) The IDS Divisions B and C                Inspection of the as-built system  i) Ancillary diesel generator 1 regulating transformers supply their          will be performed.                is electrically connected to post-72-hour ac loads when powered                                              regulating transformer from an ancillary diesel generator.                                              IDSC-DT-1 615  2.6.03.05d.ii 5.d) The IDS Divisions B and C                Inspection of the as-built system  ii) Ancillary diesel generator regulating transformers supply their          will be performed.                2 is electrically connected to post-72-hour ac loads when powered                                              regulating transformer from an ancillary diesel generator.                                              IDSB-DT-1.
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Table 2.6.3-3 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No.            Design Commitment                    Inspections, Tests, Analyses        Acceptance Criteria 616  2.6.03.06 6. Safety-related displays identified in    Inspection will be performed for  Safety-related displays Table 2.6.3-1 can be retrieved in the        retrievability of the safety-    identified in Table 2.6.3-1 can MCR.                                        related displays in the MCR.      be retrieved in the MCR.
617  2.6.03.07 7. The IDS dc battery fuses and battery      Analyses for the as-built IDS dc  Analyses for the as-built IDS charger circuit breakers, and dc            electrical distribution system to dc electrical distribution distribution panels, MCCs, and their        determine the capacities of the  system exist and conclude that circuit breakers and fuses, are sized to    battery fuses and battery charger the capacities of as-built IDS supply their load requirements.              circuit breakers, and dc          battery fuses and battery distribution panels, MCCs, and    charger circuit breakers, and their circuit breakers and fuses, dc distribution panels, MCCs, will be performed.                and their circuit breakers and fuses, as determined by their nameplate ratings, exceed their analyzed load requirements.
618  2.6.03.08 8. Circuit breakers and fuses in IDS        Analyses for the as-built IDS dc  Analyses for the as-built IDS battery, battery charger, dc distribution    electrical distribution system to dc electrical distribution panel, and MCC circuits are rated to        determine fault currents will be  system exist and conclude that interrupt fault currents.                    performed.                        the analyzed fault currents do not exceed the interrupt capacity of circuit breakers and fuses in the battery, battery charger, dc distribution panel, and MCC circuits, as determined by their nameplate ratings.
619  2.6.03.09 9. The IDS batteries, battery chargers,      Analyses for the as-built IDS dc  Analyses for the as-built IDS dc distribution panels, and MCCs are        electrical distribution system to dc electrical distribution rated to withstand fault currents for the    determine fault currents will be  system exist and conclude that time required to clear the fault from its    performed.                        the fault current capacities of power source.                                                                  as-built IDS batteries, battery chargers, dc distribution panels, and MCCs, as determined by manufacturers ratings, exceed their analyzed fault currents for the time required to clear the fault from its power source as determined by the circuit interrupting device coordination analyses.
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Table 2.6.3-3 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No.                Design Commitment                    Inspections, Tests, Analyses            Acceptance Criteria 620  2.6.03.10    10. The IDS electrical distribution          Analyses for the as-built IDS dc    Analyses for the as-built IDS system cables are rated to withstand        electrical distribution system to    dc electrical distribution fault currents for the time required to      determine fault currents will be    system exist and conclude that clear the fault from its power source.      performed.                          the IDS dc electrical distribution system cables will withstand the analyzed fault currents, as determined by manufacturers ratings, for the time required to clear the fault from its power source as determined by the circuit interrupting device coordination analyses.
621  2.6.03.11    11. Displays of the parameters              Inspection will be performed for    Displays identified in identified in Table 2.6.3-2 can be          retrievability of the displays      Table 2.6.3-2 can be retrieved retrieved in the MCR.                        identified in Table 2.6.3-2 in the  in the MCR.
MCR.
Table 2.6.3-4 Component Name                                  Tag No.                    Component Location Division A 250 Vdc 24-Hour Battery Bank                      IDSA-DB-1                      Auxiliary Building Division B 250 Vdc 24-Hour Battery Bank 1                    IDSB-DB-1                      Auxiliary Building Division B 250 Vdc 72-Hour Battery Bank 2                    IDSB-DB-2                      Auxiliary Building Division C 250 Vdc 24-Hour Battery Bank 1                    IDSC-DB-1                      Auxiliary Building Division C 250 Vdc 72-Hour Battery Bank 2                    IDSC-DB-2                      Auxiliary Building Division D 250 Vdc 24-Hour Battery Bank                      IDSD-DB-1                      Auxiliary Building Spare 125 Vdc Battery Bank                                  IDSS-DB-1                      Auxiliary Building Division A 24-Hour Battery Charger 1                        IDSA-DC-1                      Auxiliary Building Division B 24-Hour Battery Charger 1                        IDSB-DC-1                      Auxiliary Building Division B 72-Hour Battery Charger 2                        IDSB-DC-2                      Auxiliary Building Division C 24-Hour Battery Charger 1                        IDSC-DC-1                      Auxiliary Building Division C 72-Hour Battery Charger 2                        IDSC-DC-2                      Auxiliary Building Division D 24-Hour Battery Charger 1                        IDSD-DC-1                      Auxiliary Building Spare Battery Charger 1                                      IDSS-DC-1                      Auxiliary Building Division A 250 Vdc Distribution Panel                        IDSA-DD-1                      Auxiliary Building C-361
 
Table 2.6.3-4 Component Name                          Tag No. Component Location Division B 250 Vdc Distribution Panel                IDSB-DD-1  Auxiliary Building Division C 250 Vdc Distribution Panel                IDSC-DD-2  Auxiliary Building Division D 250 Vdc Distribution Panel                IDSD-DD-1  Auxiliary Building Division A 120 Vac Distribution Panel 1              IDSA-EA-1  Auxiliary Building Division A 120 Vac Distribution Panel 2              IDSA-EA-2  Auxiliary Building Division B 120 Vac Distribution Panel 1              IDSB-EA-1  Auxiliary Building Division B 120 Vac Distribution Panel 2              IDSB-EA-2  Auxiliary Building Division B 120 Vac Distribution Panel 3              IDSB-EA-3  Auxiliary Building Division C 120 Vac Distribution Panel 1              IDSC-EA-1  Auxiliary Building Division C 120 Vac Distribution Panel 2              IDSC-EA-2  Auxiliary Building Division C 120 Vac Distribution Panel 3              IDSC-EA-3  Auxiliary Building Division D 120 Vac Distribution Panel 1              IDSD-EA-1  Auxiliary Building Division D 120 Vac Distribution Panel 2              IDSD-EA-2  Auxiliary Building Division A Fuse Panel 4                              IDSA-EA-4  Auxiliary Building Division B Fuse Panel 4                              IDSB-EA-4  Auxiliary Building Division B Fuse Panel 5                              IDSB-EA-5  Auxiliary Building Division B Fuse Panel 6                              IDSB-EA-6  Auxiliary Building Division C Fuse Panel 4                              IDSC-EA-4  Auxiliary Building Division C Fuse Panel 5                              IDSC-EA-5  Auxiliary Building Division C Fuse Panel 6                              IDSC-EA-6  Auxiliary Building Division D Fuse Panel 4                              IDSD-EA-4  Auxiliary Building Division A Fused Transfer Switch Box 1              IDSA-DF-1  Auxiliary Building Division B Fused Transfer Switch Box 1              IDSB-DF-1  Auxiliary Building Division B Fused Transfer Switch Box 2              IDSB-DF-2  Auxiliary Building Division C Fused Transfer Switch Box 1              IDSC-DF-1  Auxiliary Building Division C Fused Transfer Switch Box 2              IDSC-DF-2  Auxiliary Building Division D Fused Transfer Switch Box 1              IDSD-DF-1  Auxiliary Building Spare Fused Transfer Switch Box 1                    IDSS-DF-1  Auxiliary Building Spare Battery 125/240 Vdc Disconnect Switch          IDSS-SW-1  Auxiliary Building Division A 250 Vdc MCC                              IDSA-DK-1  Auxiliary Building C-362
 
Table 2.6.3-4 Component Name                Tag No. Component Location Division B 250 Vdc MCC                    IDSB-DK-1  Auxiliary Building Division C 250 Vdc MCC                    IDSC-DK-1  Auxiliary Building Division D 250 Vdc MCC                    IDSD-DK-1  Auxiliary Building Division A 250 Vdc Switchboard 1          IDSA-DS-1  Auxiliary Building Division B 250 Vdc Switchboard 1          IDSB-DS-1  Auxiliary Building Division B 250 Vdc Switchboard 2          IDSB-DS-2  Auxiliary Building Division C 250 Vdc Switchboard 1          IDSC-DS-1  Auxiliary Building Division C 250 Vdc Switchboard 2          IDSC-DS-2  Auxiliary Building Division D 250 Vdc Switchboard 1          IDSD-DS-1  Auxiliary Building Division A Regulating Transformer          IDSA-DT-1  Auxiliary Building Division B Regulating Transformer          IDSB-DT-1  Auxiliary Building Division C Regulating Transformer          IDSC-DT-1  Auxiliary Building Division D Regulating Transformer          IDSD-DT-1  Auxiliary Building Division A 24-Hour Inverter 1              IDSA-DU-1  Auxiliary Building Division B 24-Hour Inverter 1              IDSB-DU-1  Auxiliary Building Division B 72-Hour Inverter 2              IDSB-DU-2  Auxiliary Building Division C 24-Hour Inverter 1              IDSC-DU-1  Auxiliary Building Division C 72-Hour Inverter 2              IDSC-DU-2  Auxiliary Building Division D 24-Hour Inverter 1              IDSD-DU-1  Auxiliary Building Spare Termination Box 2                    IDSS-DF-2  Auxiliary Building Spare Termination Box 3                    IDSS-DF-3  Auxiliary Building Spare Termination Box 4                    IDSS-DF-4  Auxiliary Building Spare Termination Box 5                    IDSS-DF-5  Auxiliary Building Spare Termination Box 6                    IDSS-DF-6  Auxiliary Building C-363
 
Figure 2.6.3-1 (Sheet 1 of 4)
Class 1E dc and Uninterruptible Power Supply System (Division A)
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Figure 2.6.3-1 (Sheet 2 of 4)
Class 1E dc and Uninterruptible Power Supply System (Division B)
C-365
 
Figure 2.6.3-1 (Sheet 3 of 4)
Class 1E dc and Uninterruptible Power Supply System (Division C)
C-366
 
Figure 2.6.3-1 (Sheet 4 of 4)
Class 1E dc and Uninterruptible Power Supply System (Division D)
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2.6.4            Onsite Standby Power System Design Description The onsite standby power system (ZOS) provides backup ac electrical power for nonsafety-related loads during normal and off-normal conditions.
The ZOS has two standby diesel generator units and the component locations of the ZOS are as shown in Table 2.6.4-2. The centerline of the diesel engine exhaust gas discharge is located more than twenty (20) feet higher than that of the combustion air intake.
: 1. The functional arrangement of the ZOS is as described in the Design Description of this Section 2.6.4.
: 2. The ZOS provides the following nonsafety-related functions:
a) On loss of power to a 6900 volt diesel-backed bus, the associated diesel generator automatically starts and produces ac power at rated voltage and frequency. The source circuit breakers and bus load circuit breakers are opened, and the generator is connected to the bus.
b) Each diesel generator unit is sized to supply power to the selected nonsafety-related electrical components.
c) Automatic-sequence loads are sequentially loaded on the associated buses.
: 3. Displays of diesel generator status (running/not running) and electrical output power (watts) can be retrieved in the main control room (MCR).
: 4. Controls exist in the MCR to start and stop each diesel generator.
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Table 2.6.4-1 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No.            Design Commitment                    Inspections, Tests, Analyses        Acceptance Criteria 622  2.6.04.01  1. The functional arrangement of the        Inspection of the as-built system The as-built ZOS conforms ZOS is as described in the Design          will be performed.                with the functional Description of this Section 2.6.4.                                            arrangement as described in the Design Description of this Section 2.6.4.
623  2.6.04.02a 2.a) On loss of power to a 6900 volt        Tests on the as-built ZOS system  Each as-built diesel generator diesel-backed bus, the associated diesel    will be conducted by providing a  automatically starts on generator automatically starts and          simulated loss-of-voltage signal. receiving a simulated loss-of-produces ac power at rated voltage and      The starting air supply receiver  voltage signal and attains a frequency. The source circuit breakers      will not be replenished during    voltage of 6900 + 10% V and and bus load circuit breakers are          the test.                        frequency 60 + 5% Hz after opened, and the generator is connected                                        the start signal is initiated and to the bus.                                                                  opens ac power system breakers on the associated 6900 V bus.
624  2.6.04.02b 2.b) Each diesel generator unit is sized    Each diesel generator will be    Each diesel generator provides to supply power to the selected            operated with a load of 4000 kW  power to the load with a nonsafety-related electrical                or greater and a power factor    generator terminal voltage of components.                                between 0.9 and 1.0 for a time    6900 +/- 10% V and a period required to reach engine  frequency of 60 + 5% Hz.
temperature equilibrium plus 2.5 hours.
625  2.6.04.02c 2.c) Automatic-sequence loads are          An actual or simulated signal is  The load sequencer initiates a sequentially loaded on the associated      initiated to start the load      closure signal within buses.                                      sequencer operation. Output      +/-5 seconds of the set intervals signals will be monitored to      to connect the loads.
determine the operability of the load sequencer. Time measurements are taken to determine the load stepping intervals.
626  2.6.04.03  3. Displays of diesel generator status      Inspection will be performed for  Displays of diesel generator (running/not running) and electrical        retrievability of the displays in status and electrical output output power (watts) can be retrieved in    the MCR.                          power can be retrieved in the the MCR.                                                                      MCR.
627  2.6.04.04  4. Controls exist in the MCR to start      A test will be performed to      Controls in the MCR operate and stop each diesel generator.            verify that controls in the MCR  to start and stop each diesel can start and stop each diesel    generator.
generator.
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Table 2.6.4-2 Component Name                Tag No. Component Location Onsite Diesel Generator A Package      ZOS-MS-05A  Diesel Generator Building Onsite Diesel Generator B Package        ZOS-MS-05B Diesel Generator Building C-370
 
2.6.5            Lighting System Design Description The lighting system (ELS) provides the normal and emergency lighting in the main control room (MCR) and at the remote shutdown workstation (RSW).
: 1. The functional arrangement of the ELS is as described in the Design Description of this Section 2.6.5.
: 2. The ELS has six groups of emergency lighting fixtures located in the MCR and at the RSW.
Each group is powered by one of the Class 1E inverters. The ELS has four groups of panel lighting fixtures located on or near safety panels in the MCR. Each group is powered by one of the Class 1E inverters in Divisions B and C (one 24-hour and one 72-hour inverter in each Division).
: 3. The lighting fixtures located in the MCR utilize seismic supports.
: 4. The panel lighting circuits are classified as associated and treated as Class 1E. These lighting circuits are routed with the Divisions B and C Class 1E circuits. Separation is provided between ELS associated divisions and between associated divisions and non-Class 1E cable.
: 5. The normal lighting can provide 50 foot candles at the safety panel and at the workstations in the MCR and at the RSW.
: 6. The emergency lighting can provide 10 foot candles at the safety panel and at the workstations in the MCR and at the RSW.
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Table 2.6.5-1 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No.              Design Commitment                    Inspections, Tests, Analyses          Acceptance Criteria 628    2.6.05.01  1. The functional arrangement of the        Inspection of the as-built system    The as-built ELS conforms ELS is as described in the Design            will be performed.                  with the functional Description of this Section 2.6.5.                                                arrangement as described in the Design Description of this Section 2.6.5.
629  2.6.05.02.i  2. The ELS has six groups of                i) Inspection of the as-built        i) The as-built ELS has six emergency lighting fixtures located in      system will be performed.            groups of emergency lighting the MCR and at the RSW. Each group                                                fixtures located in the MCR is powered by one of the Class 1E                                                and at the RSW. The ELS has inverters. The ELS has four groups of                                            four groups of panel lighting panel lighting fixtures located on or                                            fixtures located on or near near safety panels in the MCR. Each                                              safety panels in the MCR.
group is powered by one of the Class 1E inverters in Divisions B and C (one 24-hour and one 72-hour inverter in each Division).
630  2.6.05.02.ii 2. The ELS has six groups of                ii) Testing of the as-built system  ii) Each of the six as-built emergency lighting fixtures located in      will be performed using one          emergency lighting groups is the MCR and at the RSW. Each group          Class 1E inverter at a time.        supplied power from its is powered by one of the Class 1E                                                respective Class 1E inverter inverters. The ELS has four groups of                                            and each of the four as-built panel lighting fixtures located on or                                            panel lighting groups is near safety panels in the MCR. Each                                              supplied power from its group is powered by one of the                                                    respective Class 1E inverter.
Class 1E inverters in Divisions B and C (one 24-hour and one 72-hour inverter in each Division).
631  2.6.05.03.i  3. The lighting fixtures located in the      i) Inspection will be performed      i) The lighting fixtures MCR utilize seismic supports.                to verify that the lighting fixtures located in the MCR are located in the MCR are located      located on the Nuclear Island.
on the Nuclear Island.
632  2.6.05.03.ii 3. The lighting fixtures located in the      ii) Analysis of seismic supports    ii) A report exists and MCR utilize seismic supports.                will be performed.                  concludes that the seismic supports can withstand seismic design basis loads.
633    2.6.05.04  4. The panel lighting circuits are          See ITAAC Table 3.3-6,              See ITAAC Table 3.3-6, classified as associated and treated as      item 7.d.                            item 7.d.
Class 1E. These lighting circuits are routed with the Divisions B and C Class 1E circuits. Separation is provided between ELS associated divisions and between associated divisions and non-Class 1E cable.
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Table 2.6.5-1 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No.              Design Commitment                    Inspections, Tests, Analyses        Acceptance Criteria 634  2.6.05.05.i  5. The normal lighting can provide          i) Testing of the as-built normal  i) When adjusted for 50 foot candles at the safety panel and    lighting in the MCR will be        maximum illumination and at the workstations in the MCR and at      performed.                        powered by the main ac power the RSW.                                                                      system, the normal lighting in the MCR provides at least 50 foot candles at the safety panel and at the workstations.
635  2.6.05.05.ii 5. The normal lighting can provide          ii) Testing of the as-built normal ii) When adjusted for 50 foot candles at the safety panel and    lighting at the RSW will be        maximum illumination and at the workstations in the MCR and at      performed.                        powered by the main ac power the RSW.                                                                      system, the normal lighting in the RSW provides at least 50 foot candles at the safety panel and at the workstations.
636  2.6.05.06.i  6. The emergency lighting can provide      i) Testing of the as-built        i) When adjusted for 10 foot candles at the safety panel and    emergency lighting in the MCR      maximum illumination and at the workstations in the MCR and at      will be performed.                powered by the six Class 1E the RSW.                                                                      inverters, the emergency lighting in the MCR provides at least 10 foot candles at the safety panel and at the workstations.
637  2.6.05.06.ii 6. The emergency lighting can provide      ii) Testing of the as-built        ii) When adjusted for 10 foot candles at the safety panel and    emergency lighting at the RSW      maximum illumination and at the workstations in the MCR and at      will be performed.                powered by the six Class 1E the RSW.                                                                      inverters, the emergency lighting provides at least 10 foot candles at the RSW.
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2.6.6          Grounding and Lightning Protection System Design Description The grounding and lightning protection system (EGS) provides electrical grounding for instrumentation grounding, equipment grounding, and lightning protection during normal and off-normal conditions.
: 1. The EGS provides an electrical grounding system for: (1) instrument/computer grounding; (2) electrical system grounding of the neutral points of the main generator, main step-up transformers, auxiliary transformers, load center transformers, and onsite standby diesel generators; and (3) equipment grounding of equipment enclosures, metal structures, metallic tanks, ground bus of switchgear assemblies, load centers, motor control centers, and control cabinets. Lightning protection is provided for exposed structures and buildings housing safety-related and fire protection equipment. Each grounding system and lightning protection system is grounded to the station grounding grid.
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Table 2.6.6-1 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No.              Design Commitment                    Inspections, Tests, Analyses      Acceptance Criteria 638  2.6.06.01.i  1. The EGS provides an electrical            i) An inspection for the        i) A connection exists grounding system for:                        instrument/computer grounding    between the (1) instrument/computer grounding;          system connection to the station instrument/computer (2) electrical system grounding of the      grounding grid will be          grounding system and the neutral points of the main generator,        performed.                      station grounding grid.
main step-up transformers, auxiliary transformers, load center transformers, auxiliary and onsite standby diesel generators; and (3) equipment grounding of equipment enclosures, metal structures, metallic tanks, ground bus of switchgear assemblies, load centers, motor control centers, and control cabinets. Lightning protection is provided for exposed structures and buildings housing safety-related and fire protection equipment. Each grounding system and lighting protection system is grounded to the station grounding grid.
639  2.6.06.01.ii 1. The EGS provides an electrical            ii) An inspection for the        ii) A connection exists grounding system for:                        electrical system grounding      between the electrical system (1) instrument/computer grounding;          connection to the station        grounding and the station (2) electrical system grounding of the      grounding grid will be          grounding grid.
neutral points of the main generator,        performed.
main step-up transformers, auxiliary transformers, load center transformers, auxiliary and onsite standby diesel generators; and (3) equipment grounding of equipment enclosures, metal structures, metallic tanks, ground bus of switchgear assemblies, load centers, motor control centers, and control cabinets. Lightning protection is provided for exposed structures and buildings housing safety-related and fire protection equipment. Each grounding system and lighting protection system is grounded to the station grounding grid.
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Table 2.6.6-1 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No.              Design Commitment                    Inspections, Tests, Analyses      Acceptance Criteria 640  2.6.06.01.iii 1. The EGS provides an electrical            iii) An inspection for the      iii) A connection exists grounding system for:                        equipment grounding system      between the equipment (1) instrument/computer grounding;          connection to the station      grounding system and the (2) electrical system grounding of the      grounding grid will be          station grounding grid.
neutral points of the main generator,        performed.
main step-up transformers, auxiliary transformers, load center transformers, auxiliary and onsite standby diesel generators; and (3) equipment grounding of equipment enclosures, metal structures, metallic tanks, ground bus of switchgear assemblies, load centers, motor control centers, and control cabinets. Lightning protection is provided for exposed structures and buildings housing safety-related and fire protection equipment. Each grounding system and lighting protection system is grounded to the station grounding grid.
641  2.6.06.01.iv  1. The EGS provides an electrical            iv) An inspection for the      iv) A connection exists grounding system for:                        lightning protection system    between the lighting (1) instrument/computer grounding;          connection to the station      protection system and the (2) electrical system grounding of the      grounding grid will be          station grounding grid.
neutral points of the main generator,        performed.
main step-up transformers, auxiliary transformers, load center transformers, auxiliary and onsite standby diesel generators; and (3) equipment grounding of equipment enclosures, metal structures, metallic tanks, ground bus of switchgear assemblies, load centers, motor control centers, and control cabinets. Lightning protection is provided for exposed structures and buildings housing safety-related and fire protection equipment. Each grounding system and lighting protection system is grounded to the station grounding grid.
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2.6.7            Special Process Heat Tracing System No entry for this system.
2.6.8            Cathodic Protection System No entry.
2.6.9            Plant Security System Design Description The physical security system provides physical features to detect, delay, assist response to, and defend against the design basis threat (DBT) for radiological sabotage. The physical security system consists of physical barriers and an intrusion detection system. The details of the physical security system are categorized as Safeguards Information. The physical security system provides protection for vital equipment and plant personnel.
: 1. The external walls, doors, ceiling, and floors in the main control room, the central alarm station, and the secondary alarm station are bullet-resistant to at least Underwriters Laboratory Ballistic Standard 752, level 4.
: 2. Not used.
: 3. Secondary security power supply system for alarm annunciator equipment and non-portable communications equipment is located within a vital area.
: 4. Vital areas are locked and alarmed with active intrusion detection systems that annunciate in the central and secondary alarm stations upon intrusion into a vital area.
: 5. a) Security alarm annunciation and video assessment information is displayed concurrently in the central alarm station and the secondary alarm station, and the video image recording with real time playback capability can provide assessment of activities before and after each alarm annunciation within the perimeter barrier.
b) The central and secondary alarm stations are located inside the protected area, and the interior of each alarm station is not visible from the perimeter of the protected area.
c) The central and secondary alarm stations are designed and equipped such that, in the event of a single act, in accordance with the design basis threat of radiological sabotage, the design enables the survivability of equipment needed to maintain the functional capability of either alarm station to detect and assess alarms and communicate with onsite and offsite response personnel.
: 6. The vehicle barrier system is installed and located at the necessary stand-off distance to protect against the DBT vehicle bombs.
: 7. a) Vital equipment is located only within a vital area.
b) Access to vital equipment requires passage through the vital area barrier.
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: 8. Isolation zones and exterior areas within the protected area are provided with illumination to permit observation of abnormal presence or activity of persons or vehicles.
: 9. Emergency exits through the vital area boundaries are locked, alarmed, and equipped with a crash bar to allow for emergency egress.
: 10. Not used.
: 11. Not used.
: 12. Not used.
: 13. a) The central and secondary alarm stations have conventional (landline) telephone service with the main control room and local law enforcement authorities.
b) The central and secondary alarm stations are capable of continuous communications with security personnel.
c) Non-portable communication equipment in the central and secondary alarm stations remains operable from an independent power source in the event of loss of normal power.
: 14. Not used.
: 15. a) Security alarm devices including transmission lines to annunciators are tamper indicating and self-checking (e.g., an automatic indication is provided when failure of the alarm system or a component occurs, or when on standby power). Alarm annunciation shall indicate the type of alarm (e.g., intrusion alarms and emergency exit alarm) and location.
b) Intrusion detection and assessment systems concurrently provide visual displays and audible annunciation of alarms in the central and secondary alarm station.
: 16. Equipment exists to record onsite security alarm annunciation, including the location of the alarm, false alarm, alarm check, and tamper indication; and the type of alarm, location, alarm circuit, date, and time.
Table 2.6.9-1 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No.            Design Commitment                Inspections, Tests, Analyses        Acceptance Criteria 642  2.6.09.01    1. The external walls, doors,        See ITAAC Table 3.3-6, item 14. See ITAAC Table 3.3-6, item 14.
ceiling, and floors in the main control room, the central alarm station, and the secondary alarm station are bullet resistant to at least Underwriters Laboratory Ballistic Standard 752, level 4.
: 2. Not used C-378
 
Table 2.6.9-1 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No.          Design Commitment                Inspections, Tests, Analyses            Acceptance Criteria 643  2.6.09.03  3. Secondary security power          See ITAAC Table 3.3-6, item 16. See ITAACTable 3.3-6, item 16.
supply system for alarm annunciator equipment and non-portable communications equipment is located within the vital area.
644  2.6.09.04  4. Vital areas are locked and        See ITAAC Table 3.3-6, item 17. See ITAAC Table 3.3-6, item 17.
alarmed with active intrusion detection systems that annunciate in the central and secondary alarm stations upon intrusion into a vital area.
645  2.6.09.05a 5.a) Security alarm annunciation      Test, inspection, or a combination Security alarm annunciation and and video assessment                  of test and inspections of the    video assessment information is information is displayed              installed systems will be          displayed concurrently in the concurrently in the central alarm    performed.                        central alarm station and the station and the secondary alarm                                          secondary alarm station, and the station, and the video image                                            video image recording with real recording with real time                                                time playback capability provides playback capability can provide                                          assessment of activities before and assessment of activities before                                          after alarm annunciation within the and after each alarm                                                    perimeter barrier.
annunciation within the perimeter area barrier.
646  2.6.09.05b 5.b) The central and secondary        Inspections of the central and    The central and secondary alarm alarm stations are located inside    secondary alarm stations will be  stations are located inside the the protected area and the            performed.                        protected area and the interior of interior of each alarm station is                                        each alarm station is not visible not visible from the perimeter of                                        from the perimeter of the protected the protected area.                                                      area.
647  2.6.09.05c 5.c) The central and secondary        Inspections and/or analysis of the The central and secondary alarm alarm stations are designed and      central and secondary alarm        stations are designed and equipped equipped such that, in the event      station will be performed.        such that, in the event of a single of a single act, in accordance                                          act, in accordance with the design with the design basis threat of                                          basis threat of radiological radiological sabotage, the design                                        sabotage, equipment needed to enables the survivability of                                            maintain the functional capability equipment needed to maintain                                            of either alarm station to detect the functional capability of                                            and assess alarms and either alarm station to detect and                                      communicate with onsite and assess alarms and communicate                                            offsite response personnel exists.
with onsite and offsite response personnel.
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Table 2.6.9-1 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No.          Design Commitment                Inspections, Tests, Analyses            Acceptance Criteria 648  2.6.09.06  6. The vehicle barrier system is      Inspections and analysis will be    The vehicle barrier system will installed and located at the          performed for the vehicle barrier  protect against the DBT vehicle necessary stand-off distance to      system.                            bombs based upon the stand-off protect against the DBT vehicle                                          distance of the system.
bombs.
649  2.6.09.07a 7.a) Vital equipment is located      Inspection will be performed to    All vital equipment is located only only within a vital area.            confirm that vital equipment is    within a vital area.
located within a vital area.
650  2.6.09.07b 7.b) Access to vital equipment        Inspection will be performed to    Vital equipment is located within a requires passage through the          confirm that access to vital        protected area such that access to vital area barrier.                  equipment requires passage          vital equipment requires passage through the vital area barrier. through the vital area barrier.
651  2.6.09.08  8. Isolation zones and exterior      Inspection of the illumination in  The illumination in isolation zones areas within the protected area      the isolation zones and external    and exterior areas within the are provided with illumination to    areas of the protected area will be protected area is 0.2 foot candles permit observation of abnormal        performed.                          measured horizontally at ground presence or activity of persons or                                        level or, alternatively, sufficient to vehicles.                                                                permit observation.
652  2.6.09.09  9. Emergency exits through the        Test, inspection, or a combination  The emergency exits through the vital area boundaries are locked,    of tests and inspections of the    vital area boundaries are locked, alarmed, and equipped with a          emergency exits through the vital  alarmed, and equipped with a crash bar to allow for emergency      area boundaries will be performed. crash bar to allow for emergency egress.                                                                  egress.
: 10. Not used
: 11. Not used
: 12. Not used 653  2.6.09.13a 13.a) The central and secondary      Tests, inspections, or a            The central and secondary alarm alarm stations have conventional      combination of tests and            stations are equipped with (landline) telephone service with    inspections of the central and      conventional (landline) telephone the main control room and local      secondary alarm stations          service with the main control room law enforcement authorities.          conventional telephone services    and local law enforcement will be performed.                  authorities.
654  2.6.09.13b 13.b) The central and secondary      Tests, inspections, or a            The central and secondary alarm alarm stations are capable of        combination of tests and            stations are equipped with the continuous communication with        inspections of the central and      capability to continuously security personnel.                  secondary alarm stations          communicate with security continuous communication            officers, watchmen, armed capabilities will be performed. response individuals, or any security personnel that have responsibilities during a contingency event.
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Table 2.6.9-1 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No.          Design Commitment                Inspections, Tests, Analyses              Acceptance Criteria 655  2.6.09.13c 13.c) Non-portable                    Tests, inspections, or a              Non-portable communication communication equipment in the        combination of tests and              devices (including conventional central and secondary alarm          inspections of the non-portable      telephone systems) in the central stations remains operable from        communications equipment will        and secondary alarm stations are an independent power source in        be performed.                        wired to an independent power the event of loss of normal                                                supply that enables the system to power.                                                                      remain operable in the event of loss of normal power.
: 14. Not used.
656  2.6.09.15a 15.a) Security alarm devices,        A test will be performed to verify    A report exists and concludes that including transmission lines to      that security alarms, including      security alarm devices, including annunciators, are tamper              transmission lines to annunciators,  transmission lines to annunciators, indicating and self-checking          are tamper indicating and            are tamper indicating and (e.g., an automatic indication is    self-checking (e.g., an automatic    self-checking (e.g., an automatic provided when failure of the          indication is provided when failure  indication is provided when failure alarm system or a component          of the alarm system or a              of the alarm system or a occurs, or when on standby            component occurs, or when on          component occurs, or when the power). Alarm annunciation            standby power) and that alarm        system is on standby power) and shall indicate the type of alarm      annunciation indicates the type of    that alarm annunciation indicates (e.g., intrusion alarms and          alarm (e.g., intrusion alarms and    the type of alarm (e.g., intrusion emergency exit alarm) and            emergency exit alarms) and            alarms and emergency exit alarms) location.                            location.                            and location.
657  2.6.09.15b 15.b) Intrusion detection and        Tests will be performed on            The intrusion detection system assessment systems concurrently      intrusion detection and assessment    concurrently provides visual provide visual displays and          equipment.                            displays and audible annunciations audible annunciation of alarms                                              of alarms in both the central and in the central and secondary                                                secondary alarm stations.
alarm stations.
658  2.6.09.16  16. Equipment exists to record        Test, analysis, or a combination of  A report exists and concludes that onsite security alarm                test and analysis will be performed  equipment is capable of recording annunciation, including the          to ensure that equipment is          each onsite security alarm location of the alarm, false          capable of recording each onsite      annunciation, including the alarm, alarm check, and tamper        security alarm annunciation,          location of the alarm, false alarm, indication; and the type of alarm,    including the location of the alarm,  alarm check, and tamper location, alarm circuit, date, and    false alarm, alarm check, and        indication; and the type of alarm, time.                                tamper indication; and the type of    location, alarm circuit, date, and alarm, location, alarm circuit, date, time.
and time.
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C.2.6.9      Physical Security Table C.2.6.9-2 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No.            Design Commitment                  Inspections, Tests, Analyses        Acceptance Criteria 659  C.2.6.09.01  1. The external walls, doors, ceiling,    Type test, analysis, or a        The external walls, doors, and floors in the location within        combination of type test and    ceilings, and floors in the which the last access control function    analysis will be performed for  location within which the last for access to the protected area is      the external walls, doors,      access control function for performed are bullet-resistant to at      ceilings, and floors in the      access to the protected area is least Underwriters Laboratory            location within which the last  performed are bullet-resistant Ballistic Standard 752, level 4.          access control function for      to at least Underwriters access to the protected area is  Laboratory Ballistic performed.                      Standard 752, level 4.
660  C.2.6.09.02  2. Physical barriers for the protected    An inspection of the protected  Physical barriers at the area perimeter are not part of vital      area perimeter barrier will be  perimeter of the protected area area barriers.                            performed.                      are separated from any other barrier designated as a vital area barrier.
661  C.2.6.09.03a 3.a)      Isolation zones exist in        Inspections will be performed of Isolation zones exist in outdoor areas adjacent to the            the isolation zones in outdoor  outdoor areas adjacent to the physical barrier at the perimeter of      areas adjacent to the physical  physical barrier at the the protected area that allows 20 feet    barrier at the perimeter of the  perimeter of the protected area of observation on either side of the      protected area.                  and allow 20 feet of barrier. Where permanent buildings                                        observation and assessment of do not allow a 20 foot observation                                        the activities of people on distance on the inside of the                                              either side of the barrier.
protected area, the building walls are                                    Where permanent buildings immediately adjacent to, or an                                            do not allow a 20-foot integral part of, the protected area                                      observation and assessment barrier.                                                                  distance on the inside of the protected area, the building walls are immediately adjacent to, or an integral part of, the protected area barrier and the 20-foot observation and assessment distance does not apply.
662  C.2.6.09.03b 3.b)      The isolation zones are        Inspections will be performed of  The isolation zones are monitored with intrusion detection        the intrusion detection          equipped with intrusion equipment that provides the              equipment within the isolation    detection equipment that capability to detect and assess          zones.                            provides the capability to unauthorized persons.                                                      detect and assess unauthorized persons.
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Table C.2.6.9-2 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No.            Design Commitment                  Inspections, Tests, Analyses        Acceptance Criteria 663  C.2.6.09.04a 4. The intrusion detection and            Tests, inspections or a          The intrusion detection and assessment equipment at the              combination of tests and          assessment equipment at the protected area perimeter:                inspections of the intrusion      protected area perimeter:
a)  detects penetration or attempted    detection and assessment          a) detects penetration or penetration of the protected area    equipment at the protected area      attempted penetration of barrier and concurrently alarms      perimeter and its uninterruptible    the protected area barrier in both the Central Alarm Station    power supply will be performed.      and concurrently alarms in and Secondary Alarm Station;                                              the Central Alarm Station and Secondary Alarm Station; 664  C.2.6.09.04b 4. The intrusion detection and            Tests, inspections or a          The intrusion detection and assessment equipment at the              combination of tests and          assessment equipment at the protected area perimeter:                inspections of the intrusion      protected area perimeter:
b) remains operable from an              detection and assessment          b) remains operable from an uninterruptible power supply in      equipment at the protected area      uninterruptible power the event of the loss of normal      perimeter and its uninterruptible    supply in the event of the power.                              power supply will be performed.      loss of normal power.
665  C.2.6.09.05a 5. Access control points are              Tests, inspections, or            The access control points for established to:                          combination of tests and          the protected area:
a)  control personnel and vehicle        inspections of installed systems  a)  are configured to control access into the protected area.      and equipment at the access            personnel and vehicle control points to the protected        access.
area will be performed.
666  C.2.6.09.05b 5. Access control points are              Tests, inspections, or            The access control points for established to:                          combination of tests and          the protected area:
b) detect firearms, explosives, and      inspections of installed systems  b) include detection incendiary devices at the            and equipment at the access          equipment that is capable protected area personnel access      control points to the protected      of detecting firearms, points.                              area will be performed.              incendiary devices, and explosives at the protected area personnel access points.
667  C.2.6.09.06  6. An access control system with          A test of the access control      The access authorization numbered picture badges is installed      system with numbered picture      system with numbered picture for use by individuals who are            badges will be performed.        badges can identify and authorized access to protected areas                                        authorize protected area and and vital areas without escort.                                            vital area access only to those personnel with unescorted access authorization.
668  C.2.6.09.07  7. Access to vital equipment              Inspection will be performed to  Vital equipment is located physical barriers requires passage        confirm that access to vital      within a protected area such through the protected area perimeter      equipment physical barriers      that access to vital equipment barrier.                                  requires passage through the      physical barriers requires protected area perimeter barrier. passage through the protected area perimeter barrier.
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Table C.2.6.9-2 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No.            Design Commitment                    Inspections, Tests, Analyses        Acceptance Criteria 669  C.2.6.09.08a 8.a) Penetrations through the              Inspections will be performed of Penetrations and openings protected area barrier are secured and    penetrations through the        through the protected area monitored.                                protected area barrier.          barrier are secured and monitored.
670  C.2.6.09.08b 8.b) Unattended openings (such as          Inspections will be performed of Unattended openings (such as underground pathways) that intersect      unattended openings that        underground pathways) that the protected area boundary or vital      intersect the protected area    intersect the protected area area boundary will be protected by a      boundary or vital area boundary. boundary or vital area physical barrier and monitored by                                          boundary are protected by a intrusion detection equipment or                                            physical barrier and monitored provided surveillance at a frequency                                        by intrusion detection sufficient to detect exploitation.                                          equipment or provided surveillance at a frequency sufficient to detect exploitation.
671  C.2.6.09.09  9. Emergency exits through the            Tests, inspections, or a        Emergency exits through the protected area perimeter are alarmed      combination of tests and        protected area perimeter are and secured with locking devices to        inspections of emergency exits  alarmed and secured by allow for emergency egress.                through the protected area      locking devices that allow perimeter will be performed. prompt egress during an emergency.
C-384
 
2.6.10          Main Generation System No entry. Covered in Section 2.6.1, Main ac Power System.
2.6.11          Excitation and Voltage Regulation System No entry for this system.
C.2.6.12        Transmission Switchyard and Offsite Power System Table C.2.6.12-1 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No.              Design Commitment                    Inspections, Tests, Analyses          Acceptance Criteria 672  C.2.6.12.01  1. A minimum of one offsite circuit          Inspections of the as-built offsite At least one offsite circuit is supplies electric power from the            circuit will be performed.          provided from the transmission network to the interface                                            transmission switchyard with the onsite alternating current (ac)                                        interface to the interface with power system.                                                                    the onsite ac power system.
673  C.2.6.12.02  2. Each offsite power circuit                Analyses of the offsite power      A report exists and concludes interfacing with the onsite ac power        system will be performed to        that each as-built offsite system is adequately rated to supply        evaluate the as-built ratings of    circuit is rated to supply the assumed loads during normal, abnormal        each offsite circuit interfacing    load assumptions during and accident conditions.                    with the onsite ac power system    normal, abnormal and against the load assumptions.      accident conditions.
674  C.2.6.12.03  3. During steady state operation, each      Analyses of the as-built offsite    A report exists and concludes offsite power source is capable of          circuit will be performed to        that during steady state supplying required voltage to the            evaluate the capability of each    operation each as-built offsite interface with the onsite ac power          offsite circuit to supply the      circuit is capable of supplying system that will support operation of        voltage requirements at the        the voltage at the interface assumed loads during normal, abnormal        interface with the onsite ac        with the onsite ac power and accident conditions.                    power system.                      system that will support operation of assumed loads during normal, abnormal and accident conditions.
675  C.2.6.12.04  4. During steady state operation, each      Analyses of the as-built offsite    A report exists and concludes offsite circuit is capable of supplying      circuit will be performed to        that during steady state required frequency to the interface with    evaluate the capability of each    operation each as-built offsite the onsite ac power system that will        offsite circuit to supply the      circuit is capable of supplying support operation of assumed loads          frequency requirements at the      the frequency at the interface during normal, abnormal and accident        interface with the onsite ac        with onsite ac power system conditions.                                  power system.                      that will support operation of assumed loads during normal, abnormal and accident conditions.
C-385
 
Table C.2.6.12-1 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No.            Design Commitment                    Inspections, Tests, Analyses        Acceptance Criteria 676  C.2.6.12.05 5. The fault current contribution of        Analyses of the as-built offsite  A report exists and concludes each offsite circuit is compatible with    circuit will be performed to      the short circuit contribution the interrupting capability of the onsite  evaluate the fault current        of each as-built offsite circuit short circuit interrupting devices.        contribution of each offsite      at the interface with the onsite circuit at the interface with the ac power system is compatible onsite ac power system.          with the interrupting capability of the onsite fault current interrupting devices.
677  C.2.6.12.06 6. The reactor coolant pumps continue      Analyses of the as-built offsite  A report exists and concludes to receive power from either the main      power system will be performed    that voltage at the high-side of generator or the grid for a minimum of      to confirm that power will be    the generator stepup 3 seconds following a turbine trip.        available to the reactor coolant  transformer (GSU), and the pumps for a minimum of            RATs, does not drop more 3 seconds following a turbine    than 0.15 per unit (pu) from trip when the buses powering the  the pre-trip steady-state reactor coolant pumps are        voltage for a minimum of aligned to either the unit        3 seconds following a turbine auxiliary transformers (UATs) or  trip when the buses powering the reserve auxiliary            the reactor coolant pumps are transformers (RATs).              aligned to either the UATs or the RATs.
C-386
 
Table C.2.6.12-1 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No.                Design Commitment                  Inspections, Tests, Analyses        Acceptance Criteria 678  C.2.6.12.07.i 7) The credited GDC 17 off-site power        i) Analysis shall be used to      i) Alarm set points for the source is monitored by an open phase        determine the required alarm set  open phase condition condition monitoring system that can        points for the open phase        monitoring system to indicate detect the following at the high voltage    condition monitoring system to    the presence of open phase terminals of the transformer connecting      indicate the presence of open    conditions as described in the to the off-site source, over the full range  phase conditions described in the design commitment have been of transformer loading from no load to      design commitment.                determined by analysis.
full load:
(1) loss of one of the three phases of the offsite power source
: a. with a high impedance ground fault condition, or
: b. without a high impedance ground fault condition; or (2) loss of two of the three phases of the offsite power source
: a. with a high impedance ground fault condition, or
: b. without a high impedance ground fault condition.
Upon detection of any condition described above, the system will actuate an alarm in the main control room.
C-387
 
Table C.2.6.12-1 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No.                Design Commitment                    Inspections, Tests, Analyses        Acceptance Criteria 679  C.2.6.12.07.ii 7) The credited GDC 17 off-site power        ii) Testing of the credited        ii) Testing demonstrates the source is monitored by an open phase        GDC-17 off-site power source      credited GDC 17 off-site condition monitoring system that can        open phase condition monitoring    power source open phase detect the following at the high voltage    system will be performed using    condition monitoring system terminals of the transformer connecting      simulated signals to verify that  detects open phase conditions to the off-site source, over the full range  the as-built open phase condition  described in the design of transformer loading from no load to      monitoring system detects open    commitment and at the full load:                                  phase conditions described in the  established set points actuates design commitment and at the      an alarm in the main control (1) loss of one of the three phases of the  established set points actuates an room.
offsite power source                        alarm in the main control room.
: a. with a high impedance ground fault condition, or
: b. without a high impedance ground fault condition; or (2) loss of two of the three phases of the offsite power source
: a. with a high impedance ground fault condition, or
: b. without a high impedance ground fault condition.
Upon detection of any condition described above, the system will actuate an alarm in the main control room.
2.6.13 Offsite Retail Power System No entry for this system.
C-388
 
2.7        HVAC Systems 2.7.1            Nuclear Island Nonradioactive Ventilation System Design Description The nuclear island nonradioactive ventilation system (VBS) serves the main control room (MCR), control support area (CSA), Class 1E dc equipment rooms, Class 1E instrumentation and control (I&C) rooms, Class 1E electrical penetration rooms, Class 1E battery rooms, remote shutdown room (RSR), reactor coolant pump trip switchgear rooms, adjacent corridors, and passive containment cooling system (PCS) valve room during normal plant operation. The VBS consists of the following independent subsystems: the main control room/control support area HVAC subsystem, the class 1E electrical room HVAC subsystem, and the passive containment cooling system valve room heating and ventilation subsystem. The VBS provides heating, ventilation, and cooling to the areas served when ac power is available. The system provides breathable air to the control room and maintains the main control room and control support area areas at a slightly positive pressure with respect to the adjacent rooms and outside environment during normal operations. The VBS monitors the main control room supply air for radioactive particulate and iodine concentrations and provides filtration of main control room/control support area air during conditions of abnormal (high) airborne radioactivity. In addition, the VBS isolates the HVAC penetrations in the main control room boundary on "High-2" particulate or iodine radioactivity in the main control room supply air duct or on a loss of ac power for more than 10 minutes. The Sanitary Drainage System (SDS) also isolates a penetration in the main control room boundary on High-2 particulate or iodine radioactivity in the main control room supply air duct or on a loss of ac power for more than 10 minutes. Additional penetrations from the SDS and Potable Water System (PWS) into the main control room boundary are maintained leak tight using a loop seal in the piping, and the Waste Water System (WWS) is isolated using a normally closed safety related manual isolation valve. These features support operation of the main control room emergency habitability system (VES), and have been included in Tables 2.7.1-1 and 2.7.1-2.
The VBS is as shown in Figure 2.7.1-1 and the component locations of the VBS are as shown in Table 2.7.1-5.
: 1. The functional arrangement of the VBS is as described in the Design Description of this subsection 2.7.1.
: 2. a) The components identified in Table 2.7.1-1 as ASME Code Section III are designed and constructed in accordance with ASME Code Section III requirements.
b) The piping identified in Table 2.7.1-2 as ASME Code Section III is designed and constructed in accordance with ASME Code Section III requirements.
: 3. a) Pressure boundary welds in components identified in Table 2.7.1-1 as ASME Code Section III meet ASME Code Section III requirements.
b) Pressure boundary welds in piping identified in Table 2.7.1-2 as ASME Code Section III meet ASME Code Section III requirements.
C-389
: 4. a) The components identified in Table 2.7.1-1 as ASME Code Section III retain their pressure boundary integrity at their design pressure.
b) The piping identified in Table 2.7.1-2 as ASME Code Section III retains its pressure boundary integrity at its design pressure.
: 5. The seismic Category I equipment identified in Table 2.7.1-1 can withstand seismic design basis loads without loss of safety function.
: 6. a) The Class 1E components identified in Table 2.7.1-1 are powered from their respective Class 1E division.
b) Separation is provided between VBS Class 1E divisions, and between Class 1E divisions and non-Class 1E cable.
: 7. The VBS and SDS provide the safety-related function to isolate the pipes that penetrate the MCR pressure boundary.
: 8. The VBS provides the following nonsafety-related functions:
a) The VBS provides cooling to the MCR, CSA, RSR, and Class 1E electrical rooms.
b) The VBS provides ventilation cooling to the Class 1E battery rooms.
c) The VBS maintains MCR and CSA habitability when radioactivity is detected.
d) The VBS provides ventilation cooling via the ancillary equipment in Table 2.7.1-3 to the MCR and the division B&C Class 1E I&C rooms.
: 9. Safety-related displays identified in Table 2.7.1-1 can be retrieved in the MCR.
: 10. a) Controls exist in the MCR to cause the remotely operated valves identified in Table 2.7.1-1 to perform their active functions.
b) The valves identified in Table 2.7.1-1 as having protection and safety monitoring system (PMS) control perform their active safety function after receiving a signal from the PMS.
: 11. After loss of motive power, the valves identified in Table 2.7.1-1 assume the indicated loss of motive power position.
: 12. Controls exist in the MCR to cause the components identified in Table 2.7.1-3 to perform the listed function.
: 13. Displays of the parameters identified in Table 2.7.1-3 can be retrieved in the MCR.
: 14. The background noise level in the MCR and RSR does not exceed 65 dB(A) when the VBS is operating.
C-390
 
Table 2.7.1-1 ASME                        Class 1E/                                      Loss of Code          Remotely    Qual. for                                      Motive Section Seismic Operated      Harsh    Safety-Related    Control    Active  Power Equipment Name        Tag No. III    Cat. I  Valve      Envir.      Display      PMS/DAS(1) Function Position MCR Supply Air Isolation VBS-PL-V186  Yes    Yes      Yes        Yes/No        Yes          Yes/No  Transfer  As Is Valve                                                                      (Valve Position)            Closed MCR Supply Air Isolation VBS-PL-V187  Yes    Yes      Yes        Yes/No        Yes          Yes/No  Transfer  As Is Valve                                                                      (Valve Position)            Closed MCR Return Air          VBS-PL-V188  Yes    Yes      Yes        Yes/No        Yes          Yes/No  Transfer  As Is Isolation Valve                                                            (Valve Position)            Closed MCR Return Air          VBS-PL-V189  Yes    Yes      Yes        Yes/No        Yes          Yes/No  Transfer  As Is Isolation Valve                                                            (Valve Position)            Closed MCR Exhaust Air          VBS-PL-V190  Yes    Yes      Yes        Yes/No        Yes          Yes/No  Transfer  As Is Isolation Valve                                                            (Valve Position)            Closed MCR Exhaust Air          VBS-PL-V191  Yes    Yes      Yes        Yes/No        Yes          Yes/No  Transfer  As Is Isolation Valve                                                            (Valve Position)            Closed PWS MCR Isolation Valve  PWS-PL-V418  Yes    Yes      No          -/-          No            No    Transfer    -
Closed PWS MCR Isolation Valve  PWS-PL-V420  Yes    Yes      No          -/-          No            No    Transfer    -
Closed PWS MCR Vacuum Relief    PWS-PL-V498  Yes    Yes      No          -/-          No            No    Transfer    -
Open MCR SDS (Vent) Isolation SDS-PL-V001  Yes    Yes      Yes        Yes/No        Yes          Yes/No  Transfer  As Is Valve                                                                      (Valve Position)            Closed MCR SDS (Vent) Isolation SDS-PL-V002  Yes    Yes      Yes        Yes/No        Yes          Yes/No  Transfer  As Is Valve                                                                      (Valve Position)            Closed C-391
 
Table 2.7.1-1 ASME                        Class 1E/                                    Loss of Code          Remotely    Qual. for                                    Motive Section Seismic Operated      Harsh    Safety-Related  Control    Active  Power Equipment Name              Tag No. III    Cat. I  Valve      Envir.      Display    PMS/DAS(1) Function Position MCR WWS Isolation          WWS-PL-V506  Yes    Yes      No            -          No          No        -        -
Valve
: 1. DAS = diverse actuation system C-392
 
Table 2.7.1-2 ASME Code          Leak    Functional Capability Line Name            Line Number      Section III  Before Break      Required Main Control Room            VBS-L311          Yes            No              No Supply Main Control Room            VBS-L312          Yes            No              No Exhaust Main Control Room            VBS-L313          Yes            No              No Toilet Exhaust Main Control Room          SDS-PL-L035        Yes            No              No Sanitary Vent Line Main Control Room          SDS-PL-L030        Yes            No              No Sanitary Drain Line Main Control Room          PWS-PL-L319        Yes            No              No Water Line Main Control Room          PWS-PL-L320        Yes            No              No Water Line Main Control Room        WWS-PL-L808          Yes            No              No Waste Water Line Main Control Room        WWS-PL-L851          Yes            No              No Water Line Table 2.7.1-3 Equipment                    Tag No.            Display      Control Function Supplemental Air Filtration Unit      VBS-MA-03A            Yes              Start Fan A                                                    (Run Status)
Supplemental Air Filtration Unit      VBS-MA-03B            Yes              Start Fan B                                                    (Run Status)
MCR/CSA Supply Air Handling            VBS-MA-01A            Yes              Start Units (AHU) A Fans                    VBS-MA-02A        (Run Status)
MCR/CSA Supply AHU B Fans              VBS-MA-01B            Yes              Start VBS-MA-02B        (Run Status)
Division "A" and "C" Class 1E          VBS-MA-05A            Yes              Start Electrical Room AHU A Fans            VBS-MA-06A        (Run Status)
Division "A" and "C" Class 1E          VBS-MA-05C            Yes              Start Electrical Room AHU C Fans            VBS-MA-06C        (Run Status)
Division "B" and "D" Class 1E          VBS-MA-05B            Yes              Start Electrical Room AHU B Fans            VBS-MA-06B        (Run Status)
C-393
 
Table 2.7.1-3 Equipment                          Tag No.                    Display          Control Function Division "B" and "D" Class 1E              VBS-MA-05D                      Yes                    Start Electrical Room AHU D Fans                  VBS-MA-06D                  (Run Status)
Division "A" and "C" Class 1E              VBS-MA-07A                      Yes                    Start Battery Room Exhaust Fans                  VBS-MA-07C                  (Run Status)
Division "B" and "D" Class 1E              VBS-MA-07B                      Yes                    Start Battery Room Exhaust Fans                  VBS-MA-07D                  (Run Status)
MCR Ancillary Fans                          VBS-MA-10A                      No                      Run VBS-MA-10B Division B Room Ancillary Fan                VBS-MA-11                      No                      Run Division C Room Ancillary Fan                VBS-MA-12                      No                      Run Table 2.7.1-4 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No.              Design Commitment                    Inspections, Tests, Analyses          Acceptance Criteria 680  2.7.01.01    1. The functional arrangement of the        Inspection of the as-built system The as-built VBS conforms VBS is as described in the Design            will be performed.                with the functional Description of this subsection 2.7.1                                          arrangement described in the Design Description of this subsection 2.7.1.
681  2.7.01.02a    2.a) The components identified in            Inspection will be conducted of  The ASME Code Section III Table 2.7.1-1 as ASME Code                  the as-built components as        design reports exist for the as-Section III are designed and constructed    documented in the ASME design    built components identified in in accordance with ASME Code                reports.                          Table 2.7.1-1 as ASME Code Section III requirements.                                                      Section III.
682  2.7.01.02b    2.b) The piping identified in                Inspection will be conducted of  The ASME code Section III Table 2.7.1-2 as ASME Code                  the as-built components as        design reports exist for the Section III is designed and constructed      documented in the ASME design    as-built piping identified in in accordance with ASME Code                reports.                          Table 2.7.1-2 as ASME Code Section III requirements.                                                      Section III.
683  2.7.01.03a    3.a) Pressure boundary welds in              Inspection of the as-built        A report exists and concludes components identified in Table 2.7.1-1      pressure boundary welds will be  that the ASME Code as ASME Code Section III meet ASME          performed in accordance with      Section III requirements are Code Section III requirements.              the ASME Code Section III.        met for nondestructive examination of pressure boundary welds.
C-394
 
Table 2.7.1-4 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No.              Design Commitment                      Inspections, Tests, Analyses          Acceptance Criteria 684  2.7.01.03b  3.b) Pressure boundary welds in piping        Inspection of the as-built        A report exists and concludes identified in Table 2.7.1-2 as ASME          pressure boundary welds will be    that the ASME Code Code Section III meet ASME Code              performed in accordance with      Section III requirements are Section III requirements.                    the ASME Code Section III.        met for nondestructive examination of pressure boundary welds.
685  2.7.01.04a  4.a) The components identified in            A pressure test will be performed  A report exists and concludes Table 2.7.1-1 as ASME Code                    on the components required by      that the results of the pressure Section III retain their pressure            the ASME Code Section III to be    test of the components boundary integrity at their design            pressure tested.                  identified in Table 2.7.1-1 as pressure.                                                                        ASME Code Section III conform with the requirements of the ASME Code Section III.
686  2.7.01.04b  4.b) The piping identified in                A pressure test will be performed  A report exists and concludes Table 2.7.1-2 as ASME Code                    on the piping required by the      that the results of the pressure Section III retains its pressure boundary    ASME Code Section III to be        test of the piping identified in integrity at its design pressure.            pressure tested.                  Table 2.7.1-2 as ASME Code Section III conform with the requirements of the ASME Code Section III.
687  2.7.01.05.i  5. The seismic Category I equipment          i) Inspection will be performed    i) The seismic Category I identified in Table 2.7.1-1 can withstand    to verify that the seismic        equipment identified in seismic design basis loads without loss      Category I equipment identified    Table 2.7.1-1 is located on the of safety function.                          in Table 2.7.1-1 is located on the Nuclear Island.
Nuclear Island.
688  2.7.01.05.ii 5. The seismic Category I equipment          ii) Type tests, analyses, or a    ii) A report exists and identified in Table 2.7.1-1 can withstand    combination of type tests and      concludes that the seismic seismic design basis loads without loss      analyses of seismic Category I    Category I equipment can of safety function.                          equipment will be performed.      withstand seismic design basis loads without loss of safety function.
689  2.7.01.05.iii 5. The seismic Category I equipment          iii) Inspection will be performed  iii) A report exists and identified in Table 2.7.1-1 can withstand    for the existence of a report      concludes that the as-built seismic design basis loads without loss      verifying that the as-built        equipment including of safety function.                          equipment including anchorage      anchorage is seismically is seismically bounded by the      bounded by the tested or tested or analyzed conditions. analyzed conditions.
690  2.7.01.06a  6.a) The Class 1E components                  Testing will be performed on the  A simulated test signal exists identified in Table 2.7.1-1 are powered      VBS by providing a simulated      at the Class 1E equipment from their respective Class 1E division.      test signal in each Class 1E      identified in Table 2.7.1-1 division.                          when the assigned Class 1E division is provided the test signal.
C-395
 
Table 2.7.1-4 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No.            Design Commitment                    Inspections, Tests, Analyses          Acceptance Criteria 691  2.7.01.06b 6.b) Separation is provided between          See ITAAC Table 3.3-6,            See ITAAC Table 3.3-6, VBS Class 1E divisions, and between          item 7.d.                          item 7.d.
Class 1E divisions and non-Class 1E cable.
692  2.7.01.07  7. The VBS and SDS provide the              See item 10.b in this table.      See item 10.b in this table.
safety-related function to isolate the pipe that penetrates the MCR pressure boundary.
693  2.7.01.08a 8.a) The VBS provides cooling to the        See item 12 in this table.        See item 12 in this table.
MCR, CSA, RSR, and Class 1E electrical rooms.
694  2.7.01.08b 8.b) The VBS provides ventilation            See item 12 in this table.        See item 12 in this table.
cooling to the Class 1E battery rooms.
695  2.7.01.08c 8.c) The VBS maintains MCR and              See item 12 in this table.        See item 12 in this table.
CSA habitability when radioactivity is detected.
696  2.7.01.08d 8.d) The VBS provides ventilation            Testing will be performed on the  The fans start and run.
cooling via the ancillary equipment in      components in Table 2.7.1-3.
Table 2.7.1-3 to the MCR and the division B&C Class 1E I&C rooms.
697  2.7.01.09  9. Safety-related displays identified in    Inspection will be performed for  Safety-related displays Table 2.7.1-1 can be retrieved in the        retrievability of the safety-      identified in Table 2.7.1-1 can MCR.                                        related displays in the MCR.      be retrieved in the MCR.
698  2.7.01.10a 10.a) Controls exist in the MCR to          Stroke testing will be performed  Controls in the MCR operate cause the remotely operated valves          on the remotely operated valves    to cause the remotely operated identified in Table 2.7.1-1 to perform      identified in Table 2.7.1-1 using  valves identified in their active functions.                      the controls in the MCR.          Table 2.7.1-1 to perform their active functions.
699  2.7.01.10b 10.b) The valves identified in Table        Testing will be performed using    The valves identified in 2.7.1-1 as having PMS control perform        real or simulated signals into the Table 2.7.1-1 as having PMS their active safety function after          PMS.                              control perform their active receiving a signal from the PMS.                                                safety function after receiving a signal from PMS.
700  2.7.01.11  11. After loss of motive power, the          Testing of the remotely operated  Upon loss of motive power, remotely operated valves identified in      valves will be performed under    each remotely operated valves Table 2.7.1-1 assume the indicated loss      the conditions of loss of motive  identified in Table 2.7.1-1 of motive power position.                    power.                            assumes the indicated loss of motive power position.
C-396
 
Table 2.7.1-4 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No.            Design Commitment                    Inspections, Tests, Analyses        Acceptance Criteria 701  2.7.01.12 12. Controls exist in the MCR to cause      Testing will be performed on the Controls in the MCR operate the components identified in Table          components in Table 2.7.1-3      to cause the components listed 2.7.1-3 to perform the listed function.      using controls in the MCR.      in Table 2.7.1-3 to perform the listed functions.
702  2.7.01.13 13. Displays of the parameters              Inspection will be performed for The displays identified in identified in Table 2.7.1-3 can be          retrievability of the parameters Table 2.7.1-3 can be retrieved retrieved in the MCR.                        in the MCR.                      in the MCR.
703  2.7.01.14 14. The background noise level in the        The as-built VBS will be        The background noise level in MCR and RSR does not exceed                  operated, and background noise  the MCR and RSR does not 65 dB(A) when the VBS is operating.          levels in the MCR and RSR will  exceed 65 dB(A) when the be measured.                    VBS is operating.
C-397
 
Table 2.7.1-5 Component Name                              Tag No. Component Location Supplemental Air Filtration Unit A                      VBS-MS-01A  Auxiliary Building Supplemental Air Filtration Unit B                      VBS-MS-01B  Auxiliary Building MCR/CSA Supply Air Handling Unit A                      VBS-MS-02A  Auxiliary Building MCR/CSA Supply Air Handling Unit B                      VBS-MS-02B  Annex Building Division "A" and "C" Class 1E Electrical Room            VBS-MS-03A  Auxiliary Building AHU A Division "A" and "C" Class 1E Electrical Room            VBS-MS-03C  Auxiliary Building AHU C Division "B" and "D" Class 1E Electrical Room            VBS-MS-03B  Auxiliary Building AHU B Division "B" and "D" Class 1E Electrical Room            VBS-MS-03D  Auxiliary Building AHU D MCR Toilet Exhaust Fan                                    VBS-MA-04  Auxiliary Building Division "A&C" Class 1E Battery Room Exhaust            VBS-MA-07A  Auxiliary Building Fan Division "A&C" Class 1E Battery Room Exhaust            VBS-MA-07C  Auxiliary Building Fan Division "B&D" Class 1E Battery Room Exhaust            VBS-MA-07B  Auxiliary Building Fan Division "B&D" Class 1E Battery Room Exhaust            VBS-MA-07D  Auxiliary Building Fan PCS Valve Room Vent Fan                                  VBS-MA-08  Containment Shield Building CSA Toilet Exhaust Fan                                    VBS-MA-09  Annex Building MCR Ancillary Fan A                                      VBS-MA-10A  Auxiliary Building MCR Ancillary Fan B                                      VBS-MA-10B  Auxiliary Building Division B Ancillary Fan                                  VBS-MA-11  Auxiliary Building Division C Ancillary Fan                                  VBS-MA-12  Auxiliary Building C-398
 
Figure 2.7.1-1 (Sheet 1 of 2)
Nuclear Island Nonradioactive Ventilation System C-399
 
Figure 2.7.1-1 (Sheet 2 of 2)
Nuclear Island Nonradioactive Ventilation System C-400
 
2.7.2            Central Chilled Water System Design Description The plant heating, ventilation, and air conditioning (HVAC) systems require chilled water as a cooling medium to satisfy the ambient air temperature requirements for the plant. The central chilled water system (VWS) supplies chilled water to the HVAC systems and is functional during reactor full-power and shutdown operation. The VWS also provides chilled water to selected process systems.
The VWS is as shown in Figure 2.7.2-1 and the component locations of the VWS are as shown Table 2.7.2-3.
: 1. The functional arrangement of the VWS is as described in the Design Description of this Section 2.7.2.
: 2. The VWS provides the safety-related function of preserving containment integrity by isolation of the VWS lines penetrating the containment.
: 3. The VWS provides the following nonsafety-related functions:
a) The VWS provides chilled water to the supply air handling units serving the MCR, the Class 1E electrical rooms, and the unit coolers serving the RNS and CVS pump rooms.
b) The VWS air-cooled chillers transfer heat from the VWS to the surrounding atmosphere.
: 4. Controls exist in the MCR to cause the components identified in Table 2.7.2-1 to perform the listed function.
: 5. Displays of the parameters identified in Table 2.7.2-1 can be retrieved in the MCR.
C-401
 
Table 2.7.2-1 Control Equipment Name        Tag No.          Display      Function Air-cooled Chiller              VWS-MS-02            Yes          Start (Run Status)
Air-cooled Chiller              VWS-MS-03            Yes          Start (Run Status)
Air-cooled Chiller Pump          VWS-MP-02            Yes          Start (Run Status)
Air-cooled Chiller Pump          VWS-MP-03            Yes          Start (Run Status)
CVS Pump Room Unit Cooler Fan A VAS-MA-07A            Yes          Start (Run Status)
CVS Pump Room Unit Cooler Fan B VAS-MA-07B            Yes          Start (Run Status)
RNS Pump Room Unit Cooler Fan A VAS-MA-08A            Yes          Start (Run Status)
RNS Pump Room Unit Cooler Fan B VAS-MA-08B            Yes          Start (Run Status)
Air-cooled Chiller Water Valve  VWS-PL-V210            Yes        Open (Position Status)
Air-cooled Chiller Water Valve  VWS-PL-V253            Yes        Open (Position Status)
C-402
 
Table 2.7.2-2 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No.            Design Commitment                    Inspections, Tests, Analyses          Acceptance Criteria 704  2.7.02.01  1. The functional arrangement of the        Inspection of the as-built system The as-built VWS conforms VWS is as described in the Design            will be performed.                with the functional Description of this Section 2.7.2.                                            arrangement as described in the Design Description of this Section 2.7.2.
705  2.7.02.02  2. The applicable portions of the VWS        See ITAAC Table 2.2.1-3,          See ITAAC Table 2.2.1-3, provide the safety-related function of      items 1 and 7.                    items 1 and 7.
preserving containment integrity by isolation of the VWS lines penetrating the containment.
706  2.7.02.03a 3.a) The VWS provides chilled water          Testing will be performed by      The water flow to each to the supply air handling units serving    measuring the flow rates to the  cooling coil equals or exceeds the MCR, the Class 1E electrical rooms,      chilled water cooling coils.      the following:
and the unit coolers serving the RNS                                                Coil          Flow (gpm) and CVS pump rooms.                                                            VBS MY C01A/B 138 VBS MY C02A/C 108 VBS MY C02B/D 84 VAS MY C07A/B 24 VAS MY C12A/B 15 VAS MY C06A/B 15 707  2.7.02.03b 3.b) The VWS air-cooled chillers            Inspection will be performed for  A report exists and concludes transfer heat from the VWS to the            the existence of a report that    that the heat transfer rate of surrounding atmosphere.                      determines the heat transfer      each air-cooled chiller is capability of each air-cooled    greater than or equal to chiller.                          230 tons.
708  2.7.02.04  4. Controls exist in the MCR to cause        Testing will be performed on the  Controls in the MCR operate the components identified in Table          components in Table 2.7.2-1      to cause the components listed 2.7.2-1 to perform the listed function.      using controls in the MCR.        in Table 2.7.2-1 to perform the listed functions.
709  2.7.02.05  5. Displays of the parameters identified    Inspection will be performed for  The displays identified in in Table 2.7.2-1 can be retrieved in the    retrievability of parameters in  Table 2.7.2-1 can be retrieved MCR.                                        the MCR.                          in the MCR.
C-403
 
Table 2.7.2-3 Component Name      Tag No.      Component Location Water Chiller Pump A      VWS-MP-01A        Turbine Building Water Chiller Pump B      VWS-MP-01B        Turbine Building Air Cooled Chiller Pump 2  VWS-MP-02      Auxiliary Building Air Cooled Chiller Pump 3  VWS-MP-03      Auxiliary Building Water Chiller A          VWS-MS-01A        Turbine Building Water Chiller B          VWS-MS-01B        Turbine Building Air Cooled Chiller 2      VWS-MS-02      Auxiliary Building Air Cooled Chiller 3      VWS-MS-03      Auxiliary Building C-404
 
Figure 2.7.2-1 (Sheet 1 of 2)
Central Chilled Water System C-405
 
Figure 2.7.2-1 (Sheet 2 of 2)
Central Chilled Water System C-406
 
2.7.3          Annex/Auxiliary Building Nonradioactive Ventilation System Design Description The annex/auxiliary buildings nonradioactive HVAC system (VXS) serves the nonradioactive personnel and equipment areas, electrical equipment rooms, clean corridors, the ancillary diesel generator room and demineralized water deoxygenating room in the annex building, and the main steam isolation valve compartments, reactor trip switchgear rooms, and piping and electrical penetration areas in the auxiliary building. The VXS consists of the following independent subsystems: the general area HVAC subsystem, the switchgear room HVAC subsystem, the equipment room HVAC subsystem, the MSIV compartment HVAC subsystem, the mechanical equipment areas HVAC subsystem and the valve/piping penetration room HVAC subsystem.
The VXS is as shown in Figure 2.7.3-1 and the component locations of the VXS are as shown in Table 2.7.3-3.
: 1. The functional arrangement of the VXS is as described in the Design Description of this Section 2.7.3.
: 2. The VXS provides the following nonsafety-related functions:
a) The VXS provides cooling to the electrical switchgear, the battery charger, and the annex building nonradioactive air handling equipment rooms.
b) The VXS provides ventilation cooling to the electrical switchgear, the battery charger, and the annex building nonradioactive air handling equipment rooms when the ZOS operates during a loss of offsite power coincident with loss of chilled water.
: 3. Controls exist in the main control room (MCR) to cause the components identified in Table 2.7.3-1 to perform the listed function.
: 4. Displays of the parameters identified in Table 2.7.3-1 can be retrieved in the MCR.
Table 2.7.3-1 Control Equipment Name                            Tag No.                        Display          Function Switchgear Room Air Handling Units        VXS-MA-05A VXS-MA-06A                Yes (Run Status)        Start (AHU) A Fans Switchgear Room AHU B Fans                VXS-MA-05B VXS-MA-06B                Yes (Run Status)        Start Equipment Room AHU A Fans                VXS-MA-01A VXS-MA-02A                Yes (Run Status)        Start Equipment Room AHU B Fans                VXS-MA-01B VXS-MA-02B                Yes (Run Status)        Start C-407
 
Table 2.7.3-2 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No.            Design Commitment                    Inspections, Tests, Analyses        Acceptance Criteria 710  2.7.03.01  1. The functional arrangement of the        Inspection of the as-built system The as-built VXS conforms VXS is as described in the Design            will be performed.                with the functional Description of this Section 2.7.3.                                            arrangement described in the Design Description of this Section 2.7.3.
711  2.7.03.02a 2.a) The VXS provides cooling to the        See item 3 in this table.        See item 3 in this table.
electrical switchgear, the battery charger, and the annex building nonradioactive air handling equipment rooms when the ZOS operates and chilled water is available.
712  2.7.03.02b 2.b) The VXS provides ventilation            See item 3 in this table.        See item 3 in this table.
cooling to the electrical switchgear, the battery charger, and the annex building nonradioactive air handling equipment rooms when the ZOS operates during a loss of offsite power coincident with loss of chilled water.
713  2.7.03.03  3. Controls exist in the MCR to cause        Testing will be performed on the  Controls in the MCR operate the components identified in                components in Table 2.7.3-1      to cause the components listed Table 2.7.3-1 to perform the listed          using controls in the MCR.        in Table 2.7.3-1 to perform the function.                                                                      listed functions.
714  2.7.03.04  4. Displays of the parameters identified    Inspection will be performed for  The displays identified in in Table 2.7.3-1 can be retrieved in the    retrievability of the parameters  Table 2.7.3-1 can be retrieved MCR.                                        in the MCR.                      in the MCR.
C-408
 
Table 2.7.3-3 Component Name                          Tag No. Component Location Annex Building General Area AHU A                    VXS-MS-01A  Annex Building Annex Building General Area AHU B                    VXS-MS-01B  Annex Building Annex Building Equipment Room AHU A                  VXS-MS-02A  Annex Building Annex Building Equipment Room AHU B                  VXS-MS-02B  Annex Building MSIV Compartment A AHU-A                              VXS-MS-04A  Auxiliary Building MSIV Compartment B AHU-B                              VXS-MS-04B  Auxiliary Building MSIV Compartment B AHU-C                              VXS-MS-04C  Auxiliary Building MSIV Compartment A AHU-D                              VXS-MS-04D  Auxiliary Building Switchgear Room AHU A                                VXS-MS-05A  Annex Building Switchgear Room AHU B                                VXS-MS-05B  Annex Building Mechanical Equipment Area AHU Unit A                  VXS-MS-07A  Annex Building Mechanical Equipment Area AHU Unit B                  VXS-MS-07B  Annex Building Valve/Piping Penetration Room AHU A                  VXS-MS-08A  Auxiliary Building Valve/Piping Penetration Room AHU B                  VXS-MS-08B  Auxiliary Building Battery Room #1 Exhaust Fan                          VXS-MA-09A  Annex Building Battery Room #2 Exhaust Fan                          VXS-MA-09B  Annex Building Toilet Exhaust Fan                                    VXS-MA-13  Annex Building Annex Building Nonradioactive Air Handling          VXS-MY-W01A  Annex Building Equipment Room Unit Heater A Annex Building Nonradioactive Air Handling          VXS-MY-W01B  Annex Building Equipment Room Unit Heater B Annex Building Nonradioactive Air Handling          VXS-MY-W01C  Annex Building Equipment Room Unit Heater C C-409
 
Figure 2.7.3-1 (Sheet 1 of 2)
Annex/Auxiliary Building Nonradioactive Ventilation System C-410
 
Figure 2.7.3-1 (Sheet 2 of 2)
Annex/Auxiliary Building Nonradioactive Ventilation System C-411
 
2.7.4            Diesel Generator Building Ventilation System Design Description The diesel generator building ventilation system (VZS) provides ventilation cooling of the diesel generator building for the onsite standby power system. The VZS also provides heating and ventilation within the diesel oil transfer module enclosure. The VZS consists of the following subsystems: the normal diesel building heating and ventilation subsystem, the standby diesel building exhaust ventilation subsystem, the fuel oil day tank vault exhaust subsystem and the diesel oil transfer module enclosures ventilation and heating subsystem.
The VZS is as shown in Figure 2.7.4-1 and the component locations of the VZS are as shown in Table 2.7.4-3.
: 1. The functional arrangement of the VZS is as described in the Design Description of this Section 2.7.4.
: 2. The VZS provides the following nonsafety-related functions:
a) The VZS provides ventilation cooling to the diesel generator rooms when the diesel generators are operating.
b) The VZS provides ventilation cooling to the electrical equipment service modules when the diesel generators are operating.
c) The VZS provides normal heating and ventilation to the diesel oil transfer module enclosure.
: 3. Controls exist in the main control room (MCR) to cause the components identified in Table 2.7.4-1 to perform the listed functions.
: 4. Displays of the parameters identified in Table 2.7.4-1 can be retrieved in the MCR.
Table 2.7.4-1 Equipment Name                  Tag No.          Display        Control Function Diesel Generator Room A Standby          VZS-MY-V01A          Yes                Start Exhaust Fans                              VZS-MY-V02A      (Run Status)
Diesel Generator Room B Standby          VZS-MY-V01B          Yes                Start Exhaust Fans                              VZS-MY-V02B      (Run Status)
Service Module A Air Handling Units        VZS-MA-01A          Yes                Start (AHU) Supply Fan                                            (Run Status)
Service Module B AHU Supply Fan            VZS-MA-01B          Yes                Start (Run Status)
Diesel Oil Transfer Module Enclosure A    VZS-MY-V03A          Yes                Start Exhaust Fan                                                (Run Status)
C-412
 
Table 2.7.4-1 Equipment Name                            Tag No.              Display            Control Function Diesel Oil Transfer Module Enclosure A            VZS-MY-U03A                Yes                  Energize Electric Unit Heater                                                    (Run Status)
Diesel Oil Transfer Module Enclosure B            VZS-MY-V03B                Yes                    Start Exhaust Fan                                                              (Run Status)
Diesel Oil Transfer Module Enclosure B            VZS-MY-U03B                Yes                  Energize Electric Unit Heater                                                    (Run Status)
Table 2.7.4-2 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No.                Design Commitment                    Inspections, Tests, Analyses          Acceptance Criteria 715  2.7.04.01      1. The functional arrangement of the        Inspection of the as-built system  The as-built VZS conforms VZS is as described in the Design            will be performed.                  with the functional Description of this Section 2.7.4.                                              arrangement described in the Design Description of this Section 2.7.4.
716  2.7.04.02a    2.a) The VZS provides ventilation            See item 3 in this table.          See item 3 in this table.
cooling to the diesel generator rooms when the diesel generators are operating.
717  2.7.04.02b    2.b) The VZS provides ventilation            See item 3 in this table.          See item 3 in this table.
cooling to the electrical equipment service modules when the diesel generators are operating.
718  2.7.04.02c    2.c) The VZS provides normal heating        See item 3 in this table.          See item 3 in this table.
and ventilation to the diesel oil transfer module enclosure.
719  2.7.04.03      3. Controls exist in the MCR to cause        Testing will be performed on the    Controls in the MCR operate the components identified in                components in Table 2.7.4-1        to cause the components listed Table 2.7.4-1 to perform the listed          using controls in the MCR.          in Table 2.7.4-1 to perform the function.                                                                        listed functions.
720  2.7.04.04      4. Displays of the parameters identified    Inspection will be performed for    The displays identified in in Table 2.7.4-1 can be retrieved in the    retrievability of the parameters    Table 2.7.4-1 can be retrieved MCR.                                        in the MCR.                        in the MCR.
C-413
 
Table 2.7.4-3 Component Name                            Tag No. Component Location Service Module AHU A                                      VZS-MS-01A Diesel-Generator Building Service Module AHU B                                      VZS-MS-01B Diesel-Generator Building Diesel Oil Transfer Module Enclosure A Unit Heater      VZS-MY-U03A          Yard Diesel Oil Transfer Module Enclosure B Unit Heater      VZS-MY-U03B          Yard D/G Building Standby Exhaust Fan 1A                      VZS-MY-V01A Diesel-Generator Building D/G Building Standby Exhaust Fan 1B                      VZS-MY-V01B Diesel-Generator Building D/G Building Standby Exhaust Fan 2A                      VZS-MY-V02A Diesel-Generator Building D/G Building Standby Exhaust Fan 2B                      VZS-MY-V02B Diesel-Generator Building Diesel Oil Transfer Module Enclosure A Exhaust Fan      VZS-MY-V03A          Yard Diesel Oil Transfer Module Enclosure B Exhaust Fan      VZS-MY-V03B          Yard Fuel Oil Day Tank Vault Exhaust Fan                      VZS-MA-02A Diesel-Generator Building Fuel Oil Day Tank Vault Exhaust Fan                      VZS-MA-02B Diesel-Generator Building C-414
 
Figure 2.7.4-1 (Sheet 1 of 2)
Diesel Generator Building Ventilation System C-415
 
Figure 2.7.4-1 (Sheet 2 of 2)
Diesel Generator Building Ventilation System C-416
 
2.7.5            Radiologically Controlled Area Ventilation System Design Description The radiologically controlled area ventilation system (VAS) serves the fuel handling area of the auxiliary building, and the radiologically controlled portions of the auxiliary and annex buildings, except for the health physics and hot machine shop areas, which are provided with a separate ventilation system (VHS). The VAS consists of two subsystems: the auxiliary/annex building ventilation subsystem and the fuel handling area ventilation subsystem. The subsystems provide ventilation to maintain occupied areas, and access and equipment areas within their design temperature range. They provide outside air for plant personnel and prevent the unmonitored release of airborne radioactivity to the atmosphere or adjacent plant areas. The VAS automatically isolates selected building areas by closing the supply and exhaust duct isolation dampers and starts the containment air filtration system (VFS) when high airborne radioactivity in the exhaust air duct or high ambient pressure differential is detected.
The component locations of the VAS are as shown in Table 2.7.5-3.
: 1. The functional arrangement of the VAS is as described in the Design Description of this Section 2.7.5.
: 2. The VAS maintains each building area at a slightly negative pressure relative to the atmosphere or adjacent clean plant areas.
: 3. Displays of the parameters identified in Table 2.7.5-1 can be retrieved in the main control room (MCR).
Table 2.7.5-1 Equipment                                Tag No. Display    Control Function Annex Building Pressure Differential Indicator              VAS-032    Yes              -
Auxiliary Building Pressure Differential Indicator          VAS-033    Yes              -
Fuel Handling Area Pressure Differential Indicator          VAS-030    Yes              -
Note: Dash (-) indicates not applicable.
C-417
 
Table 2.7.5-2 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No.              Design Commitment                    Inspections, Tests, Analyses        Acceptance Criteria 721    2.7.05.01  1. The functional arrangement of the        Inspection of the as-built system The as-built VAS conforms VAS is as described in the Design            will be performed.                with the functional Description of this Section 2.7.5.                                            arrangement described in the Design Description of this Section 2.7.5.
722  2.7.05.02.i  2. The VAS maintains each building          i) Testing will be performed to  i) The time average pressure area at a slightly negative pressure        confirm that the VAS maintains    differential in the served areas relative to the atmosphere or adjacent      each building at a slightly      of the annex, fuel handling clean plant areas.                          negative pressure when            and radiologically controlled operating all VAS supply AHUs    auxiliary buildings as and all VAS exhaust fans.        measured by each of the instruments identified in Table 2.7.5-1 is negative.
723  2.7.05.02.ii 2. The VAS maintains each building          ii) Testing will be performed to  ii) A report exists and area at a slightly negative pressure        confirm the ventilation flow rate concludes that the calculated relative to the atmosphere or adjacent      through the auxiliary building    exhaust flow rate based on the clean plant areas.                          fuel handling area when          measured flow rates is greater operating all VAS supply AHUs    than or equal to 15,300 cfm.
and all VAS exhaust fans.
724  2.7.05.02.iii 2. The VAS maintains each building          iii) Testing will be performed to iii) A report exists and area at a slightly negative pressure        confirm the auxiliary building    concludes that the calculated relative to the atmosphere or adjacent      radiologically controlled area    exhaust flow rate based on the clean plant areas.                          ventilation flow rate when        measured flow rates is greater operating all VAS supply AHUs    than or equal to 22,500 cfm.
and all VAS exhaust fans.
725    2.7.05.03  3. Displays of the parameters identified    Inspection will be performed for  The displays identified in in Table 2.7.5-1 can be retrieved in the    retrievability of the parameters  Table 2.7.5-1 can be retrieved MCR.                                        in the MCR.                      in the MCR.
C-418
 
Table 2.7.5-3 Component Name                      Tag No. Component Location Auxiliary/Annex Building Supply AHU A          VAS-MS-01A  Annex Building Auxiliary/Annex Building Supply AHU B          VAS-MS-01B  Annex Building Fuel Handling Area Supply AHU A                VAS-MS-02A  Annex Building Fuel Handling Area Supply AHU B                VAS-MS-02B  Annex Building CVS Pump Room Unit Cooler A                    VAS-MS-05A  Auxiliary Building CVS Pump Room Unit Cooler B                    VAS-MS-05B  Auxiliary Building RNS Pump Room Unit Cooler A                    VAS-MS-06A  Auxiliary Building RNS Pump Room Unit Cooler B                    VAS-MS-06B  Auxiliary Building Auxiliary/Annex Building Exhaust Fan A          VAS-MA-02A  Auxiliary Building Auxiliary/Annex Building Exhaust Fan B          VAS-MA-02B  Auxiliary Building Fuel Handling Area Exhaust Fan A                VAS-MA-06A  Auxiliary Building Fuel Handling Area Exhaust Fan B                VAS-MA-06B  Auxiliary Building C-419
 
2.7.6            Containment Air Filtration System Design Description The containment air filtration system (VFS) provides intermittent flow of outdoor air to purge and filter the containment atmosphere of airborne radioactivity during normal plant operation, and continuous flow during hot or cold plant shutdown conditions to reduce airborne radioactivity levels for personnel access. The VFS can also provide filtered exhaust for the radiologically controlled area ventilation system (VAS) during abnormal conditions.
The VFS is as shown in Figure 2.7.6-1 and the component locations of the VFS are as shown in Table 2.7.6-3.
: 1. The functional arrangement of the VFS is as described in the Design Description of this Section 2.7.6.
: 2. The VFS provides the safety-related functions of preserving containment integrity by isolation of the VFS lines penetrating containment and providing vacuum relief for the containment vessel.
: 3. The VFS provides the intermittent flow of outdoor air to purge the containment atmosphere during normal plant operation, and continuous flow during hot or cold plant shutdown conditions.
: 4. Controls exist in the main control room (MCR) to cause the components identified in Table 2.7.6-1 to perform the listed function.
: 5. Displays of the parameters in Table 2.7.6-1 can be retrieved in the MCR.
Table 2.7.6-1 Control Equipment                        Tag No.      Display          Function Containment Air Handling Units (AHU) Supply    VFS-MA-01A        Yes              Start Fan A                                                          (Run Status)
Containment AHU Supply Fan B                    VFS-MA-01B        Yes              Start (Run Status)
Containment AHU Supply Fan A Flow Sensor          VFS-012A        Yes                -
Containment AHU Supply Fan B Flow Sensor          VFS-012B        Yes                -
Containment Exhaust Fan A                      VFS-MA-02A        Yes              Start (Run Status)
Containment Exhaust Fan B                      VFS-MA-02B        Yes              Start (Run Status)
Containment Exhaust Fan A Flow Sensor            VFS-011A        Yes                -
Containment Exhaust Fan B Flow Sensor            VFS-011B        Yes                -
C-420
 
Table 2.7.6-2 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No.              Design Commitment                    Inspections, Tests, Analyses        Acceptance Criteria 726    2.7.06.01  1. The functional arrangement of the        Inspection of the as-built system The as-built VFS conforms VFS is as described in the Design            will be performed.                with the functional Description of this Section 2.7.6.                                            arrangement described in the Design Description of this Section 2.7.6.
727  2.7.06.02.i  2. The VFS provides the safety-related      i) See ITAAC Table 2.2.1-3,      i) See ITAAC Table 2.2.1-3, functions of preserving containment          items 1 and 7.                    items 1 and 7.
integrity by isolation of the VFS lines penetrating containment and providing vacuum relief for the containment vessel.
728  2.7.06.02.ii 2. The VFS provides the safety-related      ii) Testing will be performed to  ii) The containment vacuum functions of preserving containment          demonstrate that remotely        relief isolation valves integrity by isolation of the VFS lines      operated containment vacuum      (VFS-PL-V800A and penetrating containment and providing        relief isolation valves open      VFS-PL-V800B) open within vacuum relief for the containment            within the required response      30 seconds.
vessel.                                      time.
729  2.7.06.03.i  3. The VFS provides the intermittent        i) Testing will be performed to  i) The flow rate measured at flow of outdoor air to purge the            confirm that containment supply  each fan is greater than or containment atmosphere during normal        AHU fan A when operated with      equal to 3,600 scfm.
plant operation, and continuous flow        containment exhaust fan A during hot or cold plant shutdown            provides a flow of outdoor air.
conditions.
730  2.7.06.03.ii 3. The VFS provides the intermittent        ii) Testing will be performed to  ii) The flow rate measured at flow of outdoor air to purge the            confirm that containment supply  each fan is greater than or containment atmosphere during normal        AHU fan B when operated with      equal to 3,600 scfm.
plant operation, and continuous flow        containment exhaust fan B during hot or cold plant shutdown            provides a flow of outdoor air.
conditions.
731  2.7.06.03.iii 3. The VFS provides the intermittent        iii) Inspection will be conducted iii) The nominal line size is flow of outdoor air to purge the            of the containment purge          36 in.
containment atmosphere during normal        discharge line (VFS-L204) plant operation, and continuous flow        penetrating the containment.
during hot or cold plant shutdown conditions.
732    2.7.06.04  4. Controls exist in the MCR to cause        Testing will be performed on the  Controls in the MCR operate the components identified in                components in Table 2.7.6-1      to cause the components listed Table 2.7.6-1 to perform the listed          using controls in the MCR.        in Table 2.7.6-1 to perform the function.                                                                      listed functions.
733    2.7.06.05  5. Displays of the parameters identified    Inspection will be performed for  The displays identified in in Table 2.7.6-1 can be retrieved in the    retrievability of the parameters  Table 2.7.6-1 can be retrieved MCR.                                        in the MCR.                      in the MCR.
C-421
 
Table 2.7.6-3 Component Name                          Tag No. Component Location Containment Air Filtration Supply AHU A            VFS-MS-01A  Annex Building Containment Air Filtration Supply AHU B            VFS-MS-01B  Annex Building Containment Air Filtration Exhaust Unit A          VFS-MS-02A  Annex Building Containment Air Filtration Exhaust Unit B          VFS-MS-02B  Annex Building C-422
 
Figure 2.7.6-1 Containment Air Filtration System C-423
 
2.7.7            Containment Recirculation Cooling System Design Description The containment recirculation cooling system (VCS) controls the containment air temperature and humidity during normal operation, refueling and shutdown.
The locations of the VCS are as shown in Table 2.7.7-3.
: 1. The functional arrangement of the VCS is as described in the Design Description of this Section 2.7.7.
: 2. Displays of the parameters identified in Table 2.7.7-1 can be retrieved in the main control room (MCR).
Table 2.7.7-1 Equipment Name                                      Tag No.                    Display Containment Temperature Channel                              VCS-061                      Yes Containment Fan Cooler Fan                              VCS-MA-01A                Yes (Run Status)
VCS-MA-01C                Yes (Run Status)
VCS-MA-01B                Yes (Run Status)
VCS-MA-01D                Yes (Run Status)
Note: Dash (-) indicates not applicable.
Table 2.7.7-2 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No.                Design Commitment                    Inspections, Tests, Analyses        Acceptance Criteria 734  2.7.07.01      1. The functional arrangement of the        Inspection of the as-built system The as-built VCS conforms VCS is as described in the Design          will be performed.                with the functional Description of this Section 2.7.7.                                            arrangement described in the Design Description of this Section 2.7.7.
735  2.7.07.02      2. Displays of the parameters identified    Inspection will be performed for  The displays identified in in Table 2.7.7-1 can be retrieved in the    retrievability of the parameters  Table 2.7.7-1 are retrieved in MCR.                                        in the MCR.                      the MCR.
C-424
 
Table 2.7.7-3 Component Name                              Tag No. Component Location Reactor Containment Recirculation Fan Coil Unit          VCS-MS-01A    Containment Assembly A Reactor Containment Recirculation Fan Coil Unit          VCS-MS-01B    Containment Assembly B 2.7.8          Radwaste Building HVAC System No ITAAC for this system.
2.7.9          Turbine Island Building Ventilation System No entry for this system.
2.7.10          Health Physics and Hot Machine Shop HVAC System No ITAAC for this system.
2.7.11          Hot Water Heating System No entry for this system.
C-425
 
3.0              Non-System Based Design Descriptions and ITAAC 3.1              Emergency Response Facilities Design Description The technical support center (TSC) is a facility from which management and technical support is provided to main control room (MCR) personnel during emergency conditions. The operations support center (OSC) provides an assembly area where operations support personnel report in an emergency. The control support area (CSA) is an area nearby the main control room from which support can be provided to the main control room.
: 1. The TSC has floor space of at least 75 ft2 per person for a minimum of 25 persons.
: 2. The TSC has voice communication equipment for communication with the MCR, emergency operations facility, OSC, and the U.S. Nuclear Regulatory Commission (NRC).
: 3. The plant parameters listed in Table 2.5.4-1, minimum inventory table, in subsection 2.5.4, Data Display and Processing System (DDS), with a "Yes" in the "Display" column, can be retrieved in the TSC.
: 4. The OSC has voice communication equipment for communication with the MCR and TSC.
: 5. The TSC and OSC are in different locations.
: 6. The CSA provides a habitable workspace environment.
Table 3.1-1 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No.              Design Commitment                Inspections, Tests, Analyses        Acceptance Criteria 736    3.1.00.01    1. The TSC has floor space of at        An inspection will be performed The TSC has at least 1875 ft2 of least 75 ft2 per person for a          of the TSC floor space.        floor space.
minimum of 25 persons.
737    3.1.00.02    2. The TSC has voice                    An inspection and test will be  Communications equipment is communication equipment for            performed of the TSC voice      installed, and voice transmission communication with the MCR,            communication equipment.        and reception are accomplished.
emergency operations facility, OSC, and the NRC.
738    3.1.00.03    3. The plant parameters listed in      An inspection will be performed The plant parameters listed in Table 2.5.4-1, minimum inventory        for retrievability of the plant Table 2.5.4-1, minimum table, in subsection 2.5.4, DDS,        parameters in the TSC.          inventory table, in with a "Yes" in the "Display"                                          subsection 2.5.4, DDS, with a column, can be retrieved in the                                        "Yes" in the "Display" column, TSC.                                                                    can be retrieved in the TSC.
739    3.1.00.04    4. The OSC has voice                    Inspection will be performed of Communications equipment is communication equipment for            the OSC voice communication    installed, and voice transmission communication with the MCR and          equipment.                      and reception are accomplished.
TSC.
C-426
 
Table 3.1-1 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No.            Design Commitment                Inspections, Tests, Analyses          Acceptance Criteria 740    3.1.00.05    5. The TSC and OSC are in              An inspection will be performed  The TSC and OSC are in different different locations.                  of the location of the TSC and  locations.
OSC.
741    3.1.00.06    6. The CSA provides a habitable        See ITAAC Table 2.7.1-4,        See ITAAC Table 2.7.1-4, workspace environment.                items 1, 8.a), 8.c), 12, and 13, items 1, 8.a), 8.c), 12, and 13, Nuclear Island Nonradioactive    Nuclear Island Nonradioactive Ventilation System.              Ventilation System.
3.2              Human Factors Engineering Design Description The AP1000 human-system interface (HSI) will be developed and implemented based upon a human factors engineering (HFE) program. Figure 3.2-1 illustrates the HFE program elements.
The HSI scope includes the design of the operation and control centers system (OCS) and each of the HSI resources. For the purposes of the HFE program, the OCS includes the main control room (MCR), the remote shutdown workstation (RSW), the local control stations, and the associated workstations for each of these centers. The HSI resources include the wall panel information system, alarm system, plant information system (nonsafety-related displays),
qualified data processing system (safety-related displays), and soft and dedicated controls.
Minimum inventories of controls, displays, and visual alerts are specified as part of the HSI for the MCR and the RSW.
The MCR provides a facility and resources for the safe control and operation of the plant. The MCR includes a minimum inventory of displays, visual alerts and fixed-position controls. Refer to item 8.a and Table 2.5.2-5 of subsection 2.5.2 for this minimum inventory.
The remote shutdown room (RSR) provides a facility and resources to establish and maintain safe shutdown conditions for the plant from a location outside of the MCR. The RSW includes a minimum inventory of displays, controls, and visual alerts. Refer to item 2 and Table 2.5.4-1 of subsection 2.5.4 for this minimum inventory. As stated in item 8.b of subsection 2.5.2, the protection and safety monitoring system (PMS) provides for the transfer of control capability from the MCR to the RSW.
The mission of local control stations is to provide the resources, outside of the MCR, for operations personnel to perform monitoring and control activities.
Implementation of the HFE program includes activity 1 below. The MCR includes design features specified by items 2 through 4 below. The RSW includes the design features specified by items 5 through 8 below. Local control stations include the design feature of item 9.
: 1. The HFE program verification and validation implementation plans are developed in accordance with the programmatic level description of the AP1000 human factors verification and validation plan. The implementation plans establish the methods for C-427
 
conducting evaluations of the integrated HSI design. The development of the HFE verification and validation plans are complete. The following documents were developed:
a) HSI task support verification - APP-OCS-GEH-220, AP1000 Human Factors Engineering Task Support Verification Plan, Westinghouse Electric Company LLC b) HFE design verification - APP-OCS-GEH-120, AP1000 Human Factors Engineering Design Verification Plan, Westinghouse Electric Company LLC c) Integrated system validation - APP-OCS-GEH-320, AP1000 Human Factors Engineering Integrated System Validation Plan, Westinghouse Electric Company LLC d) Issue resolution verification - APP-OCS-GEH-420, AP1000 Human Factors Engineering Discrepancy Resolution Process, Westinghouse Electric Company LLC e) Plant HFE/HSI (as designed at the time of plant startup) verification - APP-OCS-GEH-520, AP1000 Plant Startup Human Factors Engineering Verification Plan, Westinghouse Electric Company LLC
: 2. The MCR includes reactor operator workstations, supervisor workstation(s), safety-related displays, and safety-related controls.
: 3. The MCR provides a suitable workspace environment for use by MCR operators.
: 4. The HSI resources available to the MCR operators include the alarm system, plant information system (nonsafety-related displays), wall panel information system, nonsafety-related controls (soft and dedicated), and computerized procedure system.
: 5. The RSW includes reactor operator workstation(s) from which licensed operators perform remote shutdown operations.
: 6. The RSR provides a suitable workspace environment, separate from the MCR, for use by the RSW operators.
: 7. The HSI resources available at the RSW include the alarm system displays, the plant information system, and the controls.
: 8. The RSW and the available HSI permit execution of tasks by licensed operators to establish and maintain safe shutdown.
: 9. The capability to access displays and controls is provided (controls as assigned by the MCR operators) for local control and monitoring from selected locations throughout the plant.
C-428
 
Table 3.2.-1 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No.            Design Commitment                    Inspections, Tests, Analyses        Acceptance Criteria 742  3.2.00.01a  1. The HFE verification and validation    a) An evaluation of the          a) A report exists and program is performed in accordance        implementation of the HSI task  concludes that: Task support with the HFE verification and              support verification will be    verification was conducted in validation implementation plan and        performed.                      conformance with the includes the following activities:                                          implementation plan and a) HSI Task support verification                                            includes verification that the information and controls provided by the HSI match the display and control requirements generated by the function-based task analyses and the operational sequence analyses.
743  3.2.00.01b  1. The HFE verification and validation    b) An evaluation of the          b) A report exists and program is performed in accordance        implementation of the HFE        concludes that: HFE design with the HFE verification and              design verification will be      verification was conducted in validation implementation plan and        performed.                      conformance with the includes the following activities:                                          implementation plan and b) HFE design verification                                                  includes verification that the HSI design is consistent with the AP1000 specific design guidelines (compiled as specified in the third acceptance criteria of design commitment 3) developed for each HSI resource.
744  3.2.00.01c.i 1. The HFE verification and validation    c) (i) An evaluation of the      c) (i) A report exists and program is performed in accordance        implementation of the integrated concludes that: The test with the HFE verification and              system validation will be        scenarios listed in the validation implementation plan and        performed.                      implementation plan for includes the following activities:                                          integrated system validation c) Integrated system validation                                            were executed in conformance with the plan and noted human deficiencies were addressed.
C-429
 
Table 3.2.-1 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No.              Design Commitment                    Inspections, Tests, Analyses          Acceptance Criteria 745  3.2.00.01c.ii 1. The HFE verification and validation    c) (ii) Tests and analyses of the  c) (ii) A report exists and program is performed in accordance        following plant evolutions and      concludes that: The test and with the HFE verification and              transients, using a facility that  analysis results demonstrate validation implementation plan and        physically represents the MCR      that the MCR operators can includes the following activities:        configuration and dynamically      perform the following:
c) Integrated system validation            represents the MCR HSI and the      - Heat up and start up the operating characteristics and      plant to 100% power responses of the AP1000 design,
                                                                                                  - Shut down and cool will be performed:
down the plant to cold
                                                              - Normal plant heatup and          shutdown startup to 100% power
                                                                                                  - Bring the plant to safe
                                                              - Normal plant shutdown and        shutdown following the cooldown to cold shutdown          specified transients
                                                              - Transients: reactor trip and      - Bring the plant to a safe, turbine trip                        stable state following the
                                                              -    Accidents:                    specified accidents
                                                                    -  Small-break LOCA
                                                                    -  Large-break LOCA
                                                                    -  Steam line break
                                                                    -  Feedwater line break
                                                                    -  Steam generator tube rupture 746  3.2.00.01d  1. The HFE verification and validation    d) An evaluation of the            d) A report exists and program is performed in accordance        implementation of the HFE          concludes that: HFE design with the HFE verification and              design issue resolution            issue resolution verification validation implementation plan and        verification will be performed. was conducted in includes the following activities:                                            conformance with the d) Issue resolution verification                                              implementation plan and includes verification that human factors issues documented in the design issues tracking system have been addressed in the final design.
747  3.2.00.01e  1. The HFE verification and validation    e) An evaluation of the            e) A report exists and program is performed in accordance        implementation of the plant        concludes that: The plant with the HFE verification and              HFE/HSI (as designed at the        HFE/HSI, as designed at the validation implementation plan and        time of plant startup) verification time of plant startup, is includes the following activities:        will be performed.                  consistent with the HFE/HSI e) Plant HFE/HSI (as designed at the                                          verified in 1.a) through 1.d).
time of plant startup) verification C-430
 
Table 3.2.-1 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No.              Design Commitment                  Inspections, Tests, Analyses      Acceptance Criteria 748    3.2.00.02  2. The MCR includes reactor operator      An inspection of the MCR        The MCR includes reactor workstations, supervisor workstation(s),  workstations and control panels  operator workstations, safety-related displays, and safety-      will be performed.              supervisor workstation(s),
related controls.                                                          safety-related displays, and safety-related controls.
749  3.2.00.03.i  3. The MCR provides a suitable            i) See subsection 2.7.1, Nuclear i) See subsection 2.7.1, workspace environment for use by the      Island Nonradioactive            Nuclear Island Nonradioactive MCR operators.                            Ventilation System.              Ventilation System.
750  3.2.00.03.ii 3. The MCR provides a suitable            ii) See subsection 2.2.5, MCR    ii) See subsection 2.2.5, MCR workspace environment for use by the      Emergency Habitability System. Emergency Habitability MCR operators.                                                              System.
751  3.2.00.03.iii 3. The MCR provides a suitable            iii) See subsection 2.6.3, Class iii) See subsection 2.6.3, workspace environment for use by the      1E dc and UPS System.            Class 1E dc and UPS system.
MCR operators.
752  3.2.00.03.iv  3. The MCR provides a suitable            iv) See subsection 2.6.5,        iv) See subsection 2.6.5, workspace environment for use by the      Lighting System.                Lighting System.
MCR operators.
753  3.2.00.03.v  3. The MCR provides a suitable            v) See subsection 2.3.19,        v) See subsection 2.3.19, workspace environment for use by the      Communication System.            Communication System.
MCR operators.
754    3.2.00.04  4. The HSI resources available to the      An inspection of the HSI        The HSI (at the time of plant MCR operators include the alarm            resources available in the MCR  startup) includes an alarm system, plant information system          for the MCR operators will be    system, plant information (nonsafety-related displays), wall panel  performed.                      system (nonsafety-related information system, nonsafety-related                                      displays), wall panel controls (soft and dedicated), and                                          information system, computerized procedure system.                                              nonsafety-related controls (soft and dedicated), and computerized procedure system.
755    3.2.00.05  5. The RSW includes reactor operator      An inspection of the RSW will    The RSW includes reactor workstation(s) from which licensed        be performed.                    operator workstation(s).
operators perform remote shutdown operations.
756  3.2.00.06.i  6. The RSR provides a suitable            i) See subsection 2.7.1, Nuclear i) See subsection 2.7.1, workspace environment, separate from      Island Nonradioactive            Nuclear Island Nonradioactive the MCR, for use by the RSW                Ventilation System.              Ventilation System.
operators.
757  3.2.00.06.ii 6. The RSR provides a suitable            ii) See subsection 2.6.5,        ii) See subsection 2.6.5, workspace environment, separate from      Lighting System.                Lighting System.
the MCR, for use by the RSW operators.
C-431
 
Table 3.2.-1 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No.              Design Commitment                  Inspections, Tests, Analyses      Acceptance Criteria 758  3.2.00.06.iii 6. The RSR provides a suitable            iii) See subsection 2.3.19,      iii) See subsection 2.3.19, workspace environment, separate from      Communication System.            Communication System.
the MCR, for use by the RSW operators.
759  3.2.00.07    7. The HSI resources available at the      An inspection of the HSI        The as-built HSI at the RSW RSW include the alarm system displays,    resources available at the RSW  includes the alarm system the plant information system, and the      will be performed.              displays, the plant information controls.                                                                  system, and the controls.
760  3.2.00.08    8. The RSW and the available HSI          Test and analysis, using a      A report exists and concludes permit execution of tasks by licensed      workstation that physically      that the test and analysis operators to establish and maintain safe  represents the RSW and          results demonstrate that shutdown.                                  dynamically represents the RSW  licensed operators can achieve HSI and the operating            and maintain safe shutdown characteristics and responses of conditions from the RSW.
the AP1000, will be performed.
761  3.2.00.09    9. The capability to access displays and  An inspection of the local      The capability for local controls is provided (controls as          control and monitoring          control and monitoring from assigned by the MCR operators) for        capability is provided.          selected locations throughout local control and monitoring from                                          the plant exists.
selected locations throughout the plant.
C-432
 
Human Factors Engineering (HFE)
Design and Implementation Process Planning      Analysis            Design              V&V        Operation Operating Experience Review              Interface Design Functional                                            Design Requirements                                          Implementation Analysis and Functional          Procedure        Verification and HFE Program Allocation Management                      Development      Validation      Human Task                                                  Performance Analysis                                              Monitoring Training Staffing            Development Human Reliability Analysis Figure 3.2-1 Human Factors Engineering (HFE)
Design and Implementation Process C-433
 
3.3              Buildings Design Description The nuclear island structures include the containment (the steel containment vessel and the containment internal structure) and the shield and auxiliary buildings. The containment, shield and auxiliary buildings are structurally integrated on a common basemat which is embedded below the finished plant grade level. The containment vessel is a cylindrical welded steel vessel with elliptical upper and lower heads, supported by embedding a lower segment between the containment internal structures concrete and the basemat concrete. The containment internal structure is reinforced concrete with structural modules used for some walls and floors. The shield building cylinder is a composite steel and concrete (SC) structure except for the portion surrounded by the auxiliary building, which is reinforced concrete (RC). The shield building, in conjunction with the internal structures of the containment building, provides shielding for the reactor coolant system and the other radioactive systems and components housed in the containment. The shield building roof is a reinforced concrete structure containing an integral, steel lined passive containment cooling water storage tank. The auxiliary building is reinforced concrete and houses the safety-related mechanical and electrical equipment located outside the containment and shield buildings.
The portion of the annex building adjacent to the nuclear island is a structural steel and reinforced concrete seismic Category II structure and houses the control support area, non-1E electrical equipment, and hot machine shop.
The radwaste building is a steel framed structure and houses the low level waste processing and storage.
The turbine building is a non-safety related structure that houses the main turbine generator and the power conversion cycle equipment and auxiliaries. There is no safety-related equipment in the turbine building. The turbine building is located on a separate foundation. The turbine building structure is adjacent to the nuclear island structures consisting of the auxiliary building to the south and the annex building to the south and east. The turbine building consists of two separate superstructures, the first bay and the main area, both supported on a common reinforced concrete basemat. The first bay, next to the auxiliary building, consists of a combination of reinforced concrete walls and steel framing with reinforced concrete and steel grated floors. It is classified as a seismic Category II structure due to its immediate proximity to the auxiliary building. The main area of the turbine building, immediately to the north of the first bay, is a steel framed building with reinforced concrete and steel grated floors. It is classified as a non-seismic structure. The non-seismic portion of the turbine building is designed with eccentrically braced framing (EBF).
The diesel generator building is a non-safety related structure that houses the two standby diesel engine powered generators and the power conversion cycle equipment and auxiliaries.
There is no safety-related equipment in the diesel generator building. The diesel generator building is located on a separate foundation at a distance from the nuclear island structures.
The plant gas system (PGS) provides hydrogen, carbon dioxide, and nitrogen gases to the plant systems as required. The component locations of the PGS are located in the yard areas.
C-434
: 1. The physical arrangement of the nuclear island structures, the annex building, and the turbine building is as described in the Design Description of this Section 3.3, and as shown on Figures 3.3-1 through 3.3-14. The physical arrangement of the radwaste building and the diesel generator building is as described in the Design Description of this Section 3.3.
: 2. a) The nuclear island structures, including the critical sections listed in Table 3.3-7, are seismic Category I and are designed and constructed to withstand design basis loads, as specified in the Design Description, without loss of structural integrity and the safety-related functions. The design bases loads are those loads associated with:
* Normal plant operation (including dead loads, live loads, lateral earth pressure loads, and equipment loads, including hydrodynamic loads, temperature and equipment vibration);
* External events (including rain, snow, flood, tornado, tornado generated missiles and earthquake); and
* Internal events (including flood, pipe rupture, equipment failure, and equipment failure generated missiles).
b) Site grade level is located relative to floor elevation 100-0 per Table 3.3-5. Floor elevation 100-0 is defined as the elevation of the floor at design plant grade.
c) The containment and its penetrations are designed and constructed to ASME Code Section III, Class MC.(1) d) The containment and its penetrations retain their pressure boundary integrity associated with the design pressure.
e) The containment and its penetrations maintain the containment leakage rate less than the maximum allowable leakage rate associated with the peak containment pressure for the design basis accident.
f)  The key dimensions of the nuclear island structures are as defined on Table 3.3-5.
g) The containment vessel greater than 7 feet above the operating deck provides a heat transfer surface. A free volume exists inside the containment shell above the operating deck.
h) The containment free volume below elevation 108 provides containment floodup during a postulated loss-of-coolant accident.
: 3. Walls and floors of the nuclear island structures as defined on Table 3.3-1, except for designed openings and penetrations, provide shielding during normal operations.
: 4. a) Walls and floors of the annex building as defined on Table 3.3-1, except for designed openings and penetrations, provide shielding during normal operations.
b) The walls on the outside of the waste accumulation room in the radwaste building provide shielding from accumulated waste.
: 1. Containment isolation devices are addressed in subsection 2.2.1, Containment System.
C-435
 
c) The walls on the outside of the packaged waste storage room in the radwaste building provide shielding from stored waste.
: 5. a) Exterior walls and the basemat of the nuclear island have a water barrier up to site grade.
b) The boundaries between mechanical equipment rooms and the electrical and instrumentation and control (I&C) equipment rooms of the auxiliary building as identified in Table 3.3-2 are designed to prevent flooding of rooms that contain safety-related equipment up to the maximum flood level for each room defined in Table 3.3-2.
c) The boundaries between the following rooms, which contain safety-related equipment -
passive core cooling system (PXS) valve/accumulator room A (11205),
PXS valve/accumulator room B (11207), and chemical and volume system (CVS) room (11209) - are designed to prevent flooding between these rooms.
: 6. a) The radiologically controlled area of the auxiliary building between floor elevations 66-6 and 82-6 contains adequate volume to contain the liquid volume of faulted liquid radwaste system (WLS) storage tanks. The available room volumes of the radiologically controlled area of the auxiliary building between floor elevations 66-6 and 82-6 exceeds the volume of the liquid radwaste storage tanks (WLS-MT-05A, MT-05B, MT-06A, MT-06B, MT-07A, MT-07B, MT-07C, MT-11).
b) The radwaste building packaged waste storage room has a volume greater than or equal to 1293 cubic feet.
: 7. a) Class 1E electrical cables, fiber optic cables associated with only one division, and raceways are identified according to applicable color-coded Class 1E divisions.
b) Class 1E divisional electrical cables and communication cables associated with only one division are routed in their respective divisional raceways.
c) Separation is maintained between Class 1E divisions in accordance with the fire areas as identified in Table 3.3-3.
d) Physical separation is maintained between Class 1E divisions and between Class 1E divisions and non-Class 1E cables.
e) Class 1E communication cables which interconnect two divisions are routed and separated such that the Protection and Safety Monitoring System voting logic is not defeated by the loss of any single raceway or fire area.
: 8. Systems, structures, and components identified as essential targets are protected from the dynamic and environmental effects of postulated pipe ruptures.
: 9. The reactor cavity sump has a minimum concrete thickness as shown on Table 3.3-5 between the bottom of the sump and the steel containment.
: 10. The shield building roof and the passive containment cooling system (PCS) storage tank support and retain the PCS water. The passive containment cooling system tank has a stainless steel liner which provides a barrier on the inside surfaces of the tank. Leak chase channels are provided over the tank boundary liner welds.
C-436
: 11. Deleted.
: 12. The extended turbine generator axis intersects the shield building.
: 13. Separation is provided between the structural elements of the turbine, annex, and radwaste buildings and the nuclear island structure. This separation permits horizontal motion of the buildings in a safe shutdown earthquake without impact between structural elements of the buildings.
: 14. The external walls, doors, ceiling, and floors in the main control room, the central alarm station, and the secondary alarm station are bullet-resistant to at least Underwriters Laboratory Ballistic Standard 752, level 4.
: 15. Deleted.
: 16. Secondary security power supply system for alarm annunciator equipment and non-portable communications equipment is located within a vital area.
: 17. Vital areas are locked and alarmed with active intrusion detection systems that annunciate in the central and secondary alarm stations upon intrusion into a vital area.
: 18. Deleted.
C-437
 
Table 3.3-1 Definition of Wall Thicknesses for Nuclear Island Buildings, Turbine Building, and Annex Building(1)
Applicable Radiation Floor Elevation or                  Concrete            Shielding Wall Wall or Section Description                                  Column Lines                          Elevation Range                Thickness(2)(3)(4)(5)      (Yes/No)
Containment Building Internal Structure Shield Wall between Reactor Vessel Cavity and RCDT                E-W wall parallel with column line 7      From 71'-6" to 83'-0"                        3'-0"                  Yes Room West Reactor Vessel Cavity Wall                                  N-S wall parallel with column line N      From 83'-0" to 98'-0"                        7'-6"                  Yes North Reactor Vessel Cavity Wall                                  E-W wall parallel with column line 7      From 83'-0" to 98'-0"                        9'-0"                  Yes East Reactor Vessel Cavity Wall                                  N-S wall parallel with column line N      From 83'-0" to 98'-0"                        7'-6"                  Yes West Refueling Cavity Wall                                        N-S wall parallel with column line N      From 98'-0" to 135'-3"                        4'-0"                  Yes North Refueling Cavity Wall                                      E-W wall parallel with column line 7      From 98'-0" to 135'-3"                        4'-0"                  Yes East Refueling Cavity Wall                                        N-S wall parallel with column line N      From 98'-0" to 135'-3"                        4'-0"                  Yes South Refueling Cavity Wall                                      E-W wall parallel with column line 7      From 98'-0" to 135'-3"                        4'-0"                  Yes South wall of west steam generator compartment                    Not Applicable                            From 103'-0" to 153'-0"                      2'-6"                  Yes West wall of west steam generator compartment                    Not Applicable                            From 103'-0" to 153'-0"                      2'-6"                  Yes North wall of west steam generator compartment                    Not Applicable                            From 103'-0" to 153'-0"                      2'-6"                  Yes South wall of pressurizer compartment                            Not Applicable                            From 103'-0" to 153'-6"                      2'-6"                  Yes West wall of pressurizer compartment                              Not Applicable                            From 107'-2" to 160'-0"                      2'-6"                  Yes North wall of pressurizer compartment                            Not Applicable                            From 107'-2" to 160'-0"                      2'-6"                  Yes East wall of pressurizer compartment                              Not Applicable                            From 118'-6" to 160'-0"                      2'-6"                  Yes North-east wall of in-containment refueling water storage        Parallel to column line N                From 103'-0" to 135'-3"                      2'-6"                  No tank West wall of in-containment refueling water storage tank          Not applicable                            From 103'-0" to 135'-3"              5/8" steel plate with          No stiffeners South wall of east steam generator compartment                    Not Applicable                            From 87'-6" to 153'-0"                        2'-6"                  Yes
: 1. The column lines and floor elevations are identified and included on Figures 3.3-1 through 3.3-13.
: 2. These wall (and floor) thicknesses have a construction tolerance of + 1 inch, except for exterior walls below grade where the tolerance is +12 inches, - 1 inch.
: 3. For walls that are part of structural modules, the concrete thickness also includes the steel face plates.
: 4. For floors with steel surface plates, the concrete thickness also includes the plate thickness.
: 5. Where a wall (or a floor) has openings, the concrete thickness does not apply at the opening.
: 6. The elevation ranges for the shield building items are rounded to the nearest inch.
C-438
 
Table 3.3-1 (cont.)
Definition of Wall Thicknesses for Nuclear Island Buildings, Turbine Building, and Annex Building(1)
Applicable Radiation Floor Elevation or                Concrete          Shielding Wall Wall or Section Description                        Column Lines                    Elevation Range                Thickness(2)(3)          (Yes/No)
East wall of east steam generator compartment          Not Applicable                  From 94'-0" to 153'-0"                      2'-6"                Yes North wall of east steam generator compartment          Not Applicable                  From 87'-6" to 153'-0"                      2'-6"                Yes Shield Building  (6)
Shield Building Cylinder                                Not Applicable                  From 100'-0" to 248-6"                3'-0" (including            Yes 3/4 inch thick min.
steel plate liner on each face on portion not protected by auxiliary building)
Air Inlet                                              Not Applicable                  From 248-6 to 251'-6"                3-0" (including            Yes 3/4 inch thick min.
steel plate liner on each face)
From 251-6 to 254-6                3'-0" to 4'-6"            Yes (including 1 inch thick steel plate liner on each face)
From 254-6 to 266'-4"            4'-6" (including 1 inch        Yes thick min. steel plate liner on each face)
Tension Ring                                            Not Applicable                  From 266'-4" to 271'-6 (at top of    4'-6" (including            Yes plate)                              1-1/2 inch thick steel plate liner on each face)
Conical Roof                                            Not Applicable                  From 271'-6" to 293'-9"                3'-0" (including            Yes 1/2 inch thick min.
steel plate liner on bottom face), outside of PCS tank exterior wall PCS Tank External Cylindrical Wall                      Not Applicable                  From 293'-9" to 328'-9"                      2'-0"                Yes PCS Tank Internal Cylindrical Wall                      Not Applicable                  From 309'-4" to 329'-0"                      1'-6"                Yes PCS Tank Roof                                          Not Applicable                  328'-9" (Lowest) 329'-0" (Highest)          1'-3"                No C-439
 
Table 3.3-1 (cont.)
Definition of Wall Thicknesses for Nuclear Island Buildings, Turbine Building, and Annex Building(1)
Applicable Radiation Floor Elevation or              Concrete            Shielding Wall Wall or Section Description                          Column Lines                        Elevation Range            Thickness(2)(3)            (Yes/No)
Nuclear Island Basemat                                    Below shield building                From 60'-6" to containment vessel 6'-0" to 22'-0" (varies)        No or 82'-6" Auxiliary Building Walls/Floors Radiologically Controlled Column Line 1 wall                                        From I to N                          From 66'-6" to 100'-0"                      3'-0"                  No Column Line 1 wall                                        From I to 5'-6" east of L-2          From 100'-0" to 180'-0"                    2'-3"                  Yes Column Line 1 wall                                        From 5'-6" east of L-2 to N          From 100'-0" to 125'-0"                    3'-0"                  Yes Column Line 1 wall                                        From 5'-6" east of L-2 to N          From 125'-0" to 180'-0"                    2'-3"                  Yes Column Line 2 wall                                        From I to K-2                        From 66'-6" to 135'-3"                      2'-6"                  Yes Column Line 2 wall                                        From K-2 to L-2                      From 66'-6" to 135'-3"                      5'-0"                  Yes Column Line 2 wall                                        From L-2 to N                        From 98'-1" to 135'-3"                      2'-6"                  Yes Column Line 2 wall                                        From I to J-1                        From 135'-3" to 153'-0"                    2'-0"                  Yes Column Line 3 wall                                        From J-1 to J-2                      From 66'-6" to 82'-6"                      2'-6"                  Yes Column Line 3 wall                                        From J-1 to J-2                      From 100'-0" to 135'-3"                    2'-6"                  Yes Column Line 3 wall                                        From J-2 to K-2                      From 66'-6" to 135'-3"                      2'-6"                  Yes Column Line 3 wall                                        From K-2 to L-2                      From 66'-6" to 92'-8 1/2"                  2'-6"                  Yes Column Line 4 wall                                        From I to J-1                        From 66'-6" to 153'-0"                      2'-6"                  Yes Column Line 4 wall                                        From J-1 to J-2                      From 66'-6" to 92'-6"                      2'-6"                  Yes Column Line 4 wall                                        From J-1 to J-2                      From 107'-2" to 135'-3"                    2'-6"                  Yes Column Line 4 wall                                        From J-2 to K-2                      From 66'-6" to 135'-3"                      2'-6"                  Yes Column Line 4 wall                                        From I to intersection with shield    From 135'-3" to 180'-0"                    2'-0"                  Yes building wall Column Line 5 wall                                        From I to shield building; with      From 66'-6" to 160'-6"                      2'-0"                  Yes opening east of J-1 (below 107'-2" floor).
Column Line 7.1 wall                                      From I to 8' east of J-1              From 66'-6" to 82'-6"                      2'-0"                  Yes Column Line 7.2 wall                                      From I to 5'-6"east of J-1            From 66'-6" to 100'-0"                      2'-0"                  Yes Column Line I wall                                        From 1 to 7.3                        From 66'-6" to 100'-0"                      3'-0"                  No Column Line I wall                                        From 1 to 4                          From 100'-0" to 180'-0"                    2'-0"                  Yes Column Line I wall                                        From 4 to 5                          From 100'-0" to 160'-6"                    2'-0"                  No C-440
 
Table 3.3-1 (cont.)
Definition of Wall Thicknesses for Nuclear Island Buildings, Turbine Building, and Annex Building(1)
Applicable Radiation Floor Elevation or    Concrete        Shielding Wall Wall or Section Description                            Column Lines                      Elevation Range    Thickness(2)(3)      (Yes/No)
Column Line J-1 wall                                      From 1 to 2                          From 82'-6" to 100'-0"          2'-0"              Yes Column Line J-1 wall                                      From 2 to 4                          From 66'-6" to 135'-3"          2'-6"              Yes Column Line J-1 wall                                      From 2 to 4                          From 135'-3" to 153'-0"        2'-0"              Yes Column Line J-1 wall                                      From 4 to shield building            From 66'-6" to 107'-2"          2'-0"              Yes Column Line J-2 wall                                      From 2 to 4                          From 66'-6" to 135'-3"          2'-6"              Yes Column Line J-2 wall                                      From 4 to intersection with shield    From 66'-6" to 135'-3"          2'-0"              Yes building wall Column Line K-2 wall                                      From 2 to 4                          From 66'-6" to 135'-3"          4'-9"              Yes Column Line L-2 wall                                      From 2 to 4                          From 66'-6" to 135'-3"          4'-0"              Yes Column Line N wall                                        From 1 to 2                          From 66'-6" to 100'-0"          3'-0"              No Column Line N wall                                        From 1 to 12'-9" north of 1          From 100'-0" to 125'-0"        3'-9"              No Column Line N wall                                        From 1 to 12'-9" north of 1          From 125'-0" to 135'-0"        2'-0"              No Column Line N wall                                        From 12'-9" north of 1 to 2          From 100'-0" to 118'-2 1/2"    3'-0"              No Column Line N wall                                        From 12'-9" north of 1 to 2          From 118'-2 1/2" to 135'-3"    2'-0"              No Column Line N wall                                        From 1 to 2                          From 118'-2 1/2" to 135'-3"    2'-0"              Yes Column Line N wall                                        From 2 to 4                          From 66'-6" to 98'-1"          3'-0"              No Column Line N wall                                        From 2 to 4                          From 98'-1" to 135'-3"          5'-6"              Yes Column Line N wall                                        From 1 to 4                          From 135'-3" to 180'-0"        2'-0"              Yes Labyrinth Wall between Col. Line 3 and 4 and J-1 to 7'-3" Not Applicable                        From 82'-6" to 92'-6"          2'-6"              Yes from J-2 N-S Shield Wall (low wall)                                Between K-2 and L-2 extending        From 100'-0" to 107'-2"        2'-6"              Yes from column line 1 north N-S Shield Wall                                          Between K-2 and L-2 extending        From 100'-0" to 125'-0"        2'-3"              Yes from column line 1 north E-W Shield Wall                                          Between 1 and 2 extending from        From 100'-0" to 125'-0"        2'-9"              Yes column line N east Auxiliary Area Basemat                                    From 1-7.3 and I-N, excluding shield  From 60'-6" to 66'-6"          6'-0"              No building Floor                                                    From 1 to 2 and I to N                82'-6"                          2'-0"              Yes Floor                                                    From 2 to 4 and J-1 to J-2            82'-6"                          2'-0"              Yes C-441
 
Table 3.3-1 (cont.)
Definition of Wall Thicknesses for Nuclear Island Buildings, Turbine Building, and Annex Building(1)
Applicable Radiation Floor Elevation or  Concrete        Shielding Wall Wall or Section Description                            Column Lines                        Elevation Range  Thickness(2)(3)      (Yes/No)
Floor                                                    From 4 to 5 and J-1 to J-2              82'-6"                        0'-9"              Yes Pipe Chase Floor                                        From 2 to 5 and J-1 to J-2              92'-6"                        2'-0"              Yes Floor                                                    From 2 to 3 and J-2 to K-2              90'-3"                        3'-0"              Yes Floor                                                    From 3 to 4 and J-2 to K-2              92'-6"                        2'-0"              Yes Floor                                                    From 4 to 7.3 and I to J-1              82'-6"                        2'-0"              Yes Floor                                                    From 1 to 2 and I to N                  100'-0"                        3'-0"              Yes Floor                                                    From 2 to 4 and K-2 to L-2              92'-8 1/2"                  3'-2 1/2"            Yes Floor                                                    From I to J-2 and 4 to intersecting    107'-2"                        2'-0"              Yes vertical wall before column line 5 Floor                                                    From I to shield building wall and      105'-0"                        0'-9"              Yes from intersecting vertical wall before column line 5 to column line 5 Floor                                                    From 1 to 10'-0" north of 1 and L-2    125'-0"                        3'-0"              Yes to N Floor                                                    From 10'-0" north of 1 to 2 and L-2    118'-2 1/2"                    2'-0"              Yes to N Floor                                                    From 3 to 4 and J-2 to K-2              117'-6"                        2'-0"              Yes Floor                                                    From 2 to 4 and I to J-1                153'-0"                        0'-9"              Yes Roof                                                    From 1 to 4 and I to N                  180'-0"                        1'-3"              Yes Floor                                                    From 4 to short of column line 5 and    135'-5"                        0'-9"              Yes from I to intersection with shield building wall Floor                                                    From short of column line 5 to          133'-0"                        0'-9"              Yes column line 5 and from I to intersection with shield building wall Auxiliary Building Walls/Floors Non-Radiologically Controlled Column Line 11 wall                                      From I to Q                            From 66'-6" to 100'-0"        3'-0"              No Column Line 11 wall                                      From I to Q                            From 100'-0" to 117'-6"        2'-0"              Yes Column Line 11 wall                                      From I to L                            From 117'-6" to 153'-0"        2'-0"              Yes Column Line 11 wall                                      From L to M                            From 117'-6" to 135'-3"        4'-0"              Yes Column Line 11 wall                                      From M to P                            From 117'-6" to 135'-3"        2'-0"              Yes C-442
 
Table 3.3-1 (cont.)
Definition of Wall Thicknesses for Nuclear Island Buildings, Turbine Building, and Annex Building(1)
Applicable Radiation Floor Elevation or  Concrete        Shielding Wall Wall or Section Description                          Column Lines                        Elevation Range  Thickness(2)(3)      (Yes/No)
Column Line 11 wall                                    From P to Q                            From 117'-6" to 135'-3"        4'-0"              Yes Column Line 11 wall                                    From L to Q                            From 135'-3" to 153'-0"        2'-0"              Yes Column Line 7.3 wall                                    From I to shield building              From 66'-6" to 100'-0"        3'-0"              Yes Column Line 7.3 wall                                    From I to shield building              From 100'-0" to 160'-6"        2'-0"              No Column Line I wall                                      From 7.3 to 11                          From 66'-6" to 100'-0"        3'-0"              No Column Line I wall                                      From 7.3 to 11                          From 100'-0" to 153'-0"        2'-0"              No Column Line I wall                                      From 5 to 7.3                          From 100'-0" to 160'-6"        2'-0"              No Column Line J wall                                      From 7.3 to 11                          From 66'-6" to 117'-6"        2'-0"              No Column Line K wall                                      From 7.3 to 11                          From 60'-6" to 135'-3"        2'-0"              Yes Column Line L wall                                      From shield building wall to 11        From 60'-6" to 153'-0"        2'-0"              Yes Column Line M wall                                      From shield building wall to 11        From 66'-6" to 153'-0"        2'-0"              Yes Column Line P wall                                      From shield building wall to 11        From 66'-6" to 153'-0"        2'-0"              Yes Column Line Q wall                                      From shield building wall to 11        From 66'-6" to 100'-0"        3'-0"              No Column Line Q wall                                      From shield building wall to 11        From 100'-0" to 153'-0"        2'-0"              Yes Column Line 9.2 wall                                    From I to J and K to L                  From 117'-6" to 135'-3"        2'-0"              Yes Labyrinth Wall between Column Line 7.3 and 9.2 and J to J to K                                  From 117'-6" to 135'-3"        2'-0"              Yes K
Auxiliary Area Basemat                                  From 7.3-11 and I-Q, excluding          From 60'-6" to 66'-6"          6'-0"              No shield building Floor                                                  From 5 to 7.3 and I to shield          100'-0"                        2'-0"              Yes building wall Floor                                                  From K to L and shield building wall    100'-0"                        0'-9"              Yes to column line 10 Main Control Room Floor                                From 9.2 to 11 and I to L              117'-6"                        2'-0"              Yes Floor                                                  Bounded by shield bldg, 7.3, J, 9.2    117'-6"                        2'-0"              Yes and L Floor                                                  From 9.2 to 11 and L to Q              117'-6"                        2'-0"              Yes Floor                                                  From 5 to 7.3 and from I to            135'-3"                        0'-9"              Yes intersection with shield building wall C-443
 
Table 3.3-1 (cont.)
Definition of Wall Thicknesses for Nuclear Island Buildings, Turbine Building, and Annex Building(1)
Applicable Radiation Floor Elevation or        Concrete        Shielding Wall Wall or Section Description                      Column Lines                      Elevation Range          Thickness(2)(3)      (Yes/No)
Annex Building Column line 2 wall                                    From E to H                          From 107'-2" to 135'-3"              19 3/4"              Yes Column line 4 wall                                    From E to H                          From 107'-2" to 162'-6" & 166'-0"    2'-0"              Yes N-S Shield Wall between E and F                        From 2 to 4                          From 107'-2" to 135'-3"              1'-0"              Yes Column line 4.1 wall                                  From E to H                          From 107'-2" to 135'-3"              2'-0"              Yes E-W Labyrinth Wall between column                      Not Applicable                      From 100'-0" to 112'-0"              2'-0" line 7.1 and 7.8 and G to H N-S Labyrinth Wall between column                      Not Applicable                      From 100'-0" to 112'-0"              2'-0" line 7.8 and 9 and G to H E-W Labyrinth Wall between column                      Not Applicable                      From 100'-0" to 112'-0"              2'-0"              Yes line 7.1 and 7.8 and G to H N-S Shield Wall on Column line. F                      From 4.1 North                      From 100'-0" to 117'-6"              1'-0"              Yes Column Line 9 wall                                    From E to connecting wall            From 107'-2" to 117'-6"              2'-0"              Yes between G and H Column Line E wall                                    From 9 to 13                        From 100'-0" to 135'-3"              2'-0"              Yes Column Line 13 wall                                    From E to I.1                        From 100'-0" to 135'-3"              2'-0"              Yes Column Line I.1 wall                                  From 11.09 to 13                    From 100'-0" to 135'-3"              2'-0"              Yes Corridor Wall between G and H                          From 9 to 13                        From 100'-0" to 135'-3"              1'-6"              Yes Column Line 9 wall                                    From I to H                          From 117'-6" to 158'-0"              2'-0"              Yes Floor                                                  2 to 4 from shield wall between E    135'-3"                              0'-6"              Yes and F to column line H Floor                                                  From 4 to 4.1 and E to H            135'-3"                              1'-0"              Yes Floor                                                  From 9 to 13 and E to I.1            117'-6"                              0'-6"              Yes Floor                                                  From 9 to 13 and E to I.1            135'-3"                              0'-8"              Yes Containment Filtration Rm A (North Wall)              Between column line E to H          From 135'-3" to 158'-0"              1'-0"              Yes Containment Filtration Rm A (East wall)                Between column line E to F          From 135'-3" to 158'-0"              1'-0"              Yes Containment Filtration Rm A (West wall)                Between column line G to H          From 135'-3" to 158'-0"              1'-0"              Yes Containment Filtration Rm A (Floor)                    Between column line E to H          135'-3"                              1'-0"              Yes Containment Filtration Rm B (Floor)                    Between column line E to H          146'-3"                              0'-6"              Yes Containment Filtration Rm B (West wall)                Between column line G to H          From 146'-3" to 158'-0"              1'-0"              Yes C-444
 
Table 3.3-1 (cont.)
Definition of Wall Thicknesses for Nuclear Island Buildings, Turbine Building, and Annex Building(1)
Applicable Radiation Floor Elevation or  Concrete        Shielding Wall Wall or Section Description                      Column Lines                      Elevation Range  Thickness(2)(3)      (Yes/No)
Turbine Building Wall adjacent to Column Line I.2                      From Col. Line 11.05 to 11.2        From 100'-0" to 161'-0"        2'-0"              No Wall along Column Line 11.2                            From near I.2 to near Col. Line R  From 100'-0" to 161'-0"        2'-0"              No Wall adjacent to Column Line R                        From Col. Line 11.2 to Col. Line    From 100'-0" to 161'-0"        2'-0"              No 11.05 Wall along Column Line 11.05                          From near Col. Line R to Col.      From 100'-0" to 161'-0"        2'-0"              No Line Q From Col. Line K.4 to near Col. From 100'-0" to 161'-0"        2'-0"              No Line I.2 C-445
 
Table 3.3-2 Nuclear Island Building Room Boundaries Required to Have Flood Barrier Floors and Walls Between Room Number to Room Number Boundary/                          Room with Postulated Maximum Flood Level (inches)                Flooding Source      Adjacent Room Floor/36                                  12306                12211 Floor/3                                  12303              12203/12207 Floor/3                                  12313              12203/12207 Floor/1                                  12300          12201/12202/12207 12203/12204/12205 Floor/3                                  12312                12212 Wall/36                                  12306                12305 Floor/1                                  12401          12301/12302/12303 12312/12313 Wall/1                                  12401              12411/12412 Floor/36                                  12404                12304 Floor/4                                  12405                12305 Floor/36                                  12406                12306 Wall/36                                  12404                12401 Wall/1                                  12421                12452 Floor/3                                  12501          12401/12411/12412 Floor/3                                  12555          12421/12423/12422 Wall/36                              12156/12158          12111/12112 C-446
 
Table 3.3-3 Class 1E Divisions in Nuclear Island Fire Areas Class 1E Divisions Fire Area Number                          A              C            B  D Auxiliary Building Radiologically Controlled 1200 AF 01                          Yes            Yes            -  -
1204 AF 01                          Yes              -            -  -
Auxiliary Building Non-Radiologically Controlled 1200 AF 03                            -              -            Yes Yes 1201 AF 02                            -              -            Yes  -
1201 AF 03                            -              -            -  Yes 1201 AF 04                            -              -            Yes Yes 1201 AF 05                            -              -            Yes Yes 1201 AF 06                            -              -            Yes Yes 1202 AF 03                            -            Yes            -  -
1202 AF 04                          Yes              -            -  -
1220 AF 01                            -              -            Yes Yes 1220 AF 02                            -              -            -  Yes 1230 AF 01                          Yes            Yes            -  -
1230 AF 02                            -              -            Yes Yes 1240 AF 01                          Yes            Yes            -  -
1242 AF 02                          Yes                            -
Note: Dash (-) indicates not applicable.
Table 3.3-4 is not used.
C-447
 
Table 3.3-5 Key Dimensions of Nuclear Island Building Features Reference Dimension Key Dimension                    (Figure 3.3-14)    Nominal Dimension Tolerance Distance between Outside Surface of                  X1                91 ft-0 in    +3 ft walls at Column Line I & N when                                                        -1 ft Measured at Column Line 1 Distance from Outside Surface of wall at            X2                138 ft-0 in    +3 ft Column Line 1 to Column Line 7 when                                                    -1 ft Measured at Column Line I Distance from Outside Surface of wall at            X3                118 ft-0 in    +3 ft Column Line 11 to Column Line 7 when                                                  -1 ft Measured at Column Line I Distance between Outside Surface of                  X4                117 ft-6 in    +3 ft walls at Column Line I & Q when                                                        -1 ft Measured at Column Line 11 Distance from Outside Surface of wall at            X5                29 ft-0 in    +3 ft Column Line Q to Column Line N when                                                    -1 ft Measured at Column Line 11 Distance between Outside Surface of                  X6                72 ft-6 in    +3 ft shield building wall to shield building                                                -1 ft centerline when Measured on West Edge of Shield Building Distance between shield building                    X7                  7 ft-6 in    +/- 3 in centerline to Reactor Vessel centerline when Measured along Column Line N in North-South Direction Distance from Bottom of Containment                  -                  2 ft-8 in    +/- 3 in Sump to Top Surface of Embedded Containment Shell Distance from top of Basemat to Design              -                  33 ft-6 in    +/- 1 ft Plant Grade Distance of Design Plant Grade (Floor                -                      0 ft    +/- 3 ft-6 in elevation 100'-0") relative to Site Grade Distance from Design Plant Grade to Top              -                229 ft-0 in    +/- 1 ft Surface of Shield Building Roof C-448
 
Table 3.3-6 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No.              Design Commitment                    Inspections, Tests, Analyses          Acceptance Criteria 762    3.3.00.01    1. The physical arrangement of the          An inspection of the nuclear      The as-built nuclear island nuclear island structures and the annex    island structures, the annex      structures, the annex building, building is as described in the Design      building, the radwaste building,  the radwaste building, the Description of this Section 3.3 and        the turbine building, and the    turbine building, and the Figures 3.3-1 through 3.3-14. The          diesel generator building will be diesel generator building physical arrangement of the radwaste        performed.                        conform with the physical building, the turbine building, and the                                      arrangement as described in diesel generator building is as                                              the Design Description of this described in the Design Description of                                        Section 3.3 and Figures 3.3-1 this Section 3.3.                                                            through 3.3-14.
763  3.3.00.02a.i.a 2.a) The nuclear island structures,        i) An inspection of the nuclear  i.a) A report exists which including the critical sections listed in  island structures will be        reconciles deviations during Table 3.3-7, are seismic Category I and    performed. Deviations from the    construction and concludes are designed and constructed to            design due to as-built conditions that the as-built containment withstand design basis loads as            will be analyzed for the design  internal structures, including specified in the Design Description,        basis loads.                      the critical sections, conform without loss of structural integrity and                                      to the approved design and the safety-related functions.                                                will withstand the design basis loads specified in the Design Description without loss of structural integrity or the safety-related functions.
764  3.3.00.02a.i.b 2.a) The nuclear island structures,        i) An inspection of the nuclear  i.b) A report exists which including the critical sections listed in  island structures will be        reconciles deviations during Table 3.3-7, are seismic Category I and    performed. Deviations from the    construction and concludes that are designed and constructed to            design due to as-built conditions the as-built shield building withstand design basis loads as            will be analyzed for the design  structures, including the critical specified in the Design Description,        basis loads.                      sections, conform to the without loss of structural integrity and                                      approved design and will the safety-related functions.                                                withstand the design basis loads specified in the Design Description without loss of structural integrity or the safety-related functions.
C-449
 
Table 3.3-6 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No.              Design Commitment                    Inspections, Tests, Analyses        Acceptance Criteria 765  3.3.00.02a.i.c  2.a) The nuclear island structures,        i) An inspection of the nuclear  i.c) A report exists which including the critical sections listed in  island structures will be        reconciles deviations during Table 3.3-7, are seismic Category I and    performed. Deviations from the    construction and concludes that are designed and constructed to            design due to as-built conditions the as-built structures in the withstand design basis loads as            will be analyzed for the design  non-radiologically controlled specified in the Design Description,        basis loads.                      area of the auxiliary building, without loss of structural integrity and                                      including the critical sections, the safety-related functions.                                                conform to the approved design and will withstand the design basis loads specified in the Design Description without loss of structural integrity or the safety-related functions.
766  3.3.00.02a.i.d  2.a) The nuclear island structures,        i) An inspection of the nuclear  i.d) A report exists which including the critical sections listed in  island structures will be        reconciles deviations during Table 3.3-7, are seismic Category I and    performed. Deviations from the    construction and concludes are designed and constructed to            design due to as-built conditions that the as-built structures in withstand design basis loads as            will be analyzed for the design  the radiologically controlled specified in the Design Description,        basis loads.                      area of the auxiliary building, without loss of structural integrity and                                      including the critical sections, the safety-related functions.                                                conform to the approved design and will withstand the design basis loads specified in the Design Description without loss of structural integrity or the safety-related functions.
767  3.3.00.02a.ii.a 2.a) The nuclear island structures,        ii) An inspection of the as-built ii.a) A report exists that including the critical sections listed in  concrete thickness will be        concludes that the Table 3.3-7, are seismic Category I and    performed.                        containment internal are designed and constructed to                                              structures as-built concrete withstand design basis loads as                                              thicknesses conform to the specified in the Design Description,                                          building sections defined in without loss of structural integrity and                                      Table 3.3-1.
the safety-related functions.
768  3.3.00.02a.ii.b 2.a) The nuclear island structures,        ii) An inspection of the as-built ii.b) A report exists that including the critical sections listed in  concrete thickness will be        concludes that the as-built Table 3.3-7, are seismic Category I and    performed.                        concrete thicknesses of the are designed and constructed to                                              shield building sections withstand design basis loads as                                              conform to the building specified in the Design Description,                                          sections defined in without loss of structural integrity and                                      Table 3.3-1.
the safety-related functions.
C-450
 
Table 3.3-6 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No.                    Design Commitment                            Inspections, Tests, Analyses        Acceptance Criteria 769  3.3.00.02a.ii.c    2.a) The nuclear island structures,                  ii) An inspection of the as-built ii.c) A report exists that including the critical sections listed in            concrete thickness will be        concludes that as-built Table 3.3-7, are seismic Category I                  performed.                        concrete thicknesses of the and are designed and constructed to                                                    non-radiologically controlled withstand design basis loads as                                                        area of the auxiliary building specified in the Design Description,                                                  sections conform to the without loss of structural integrity and                                              building sections defined in the safety-related functions.                                                          Table 3.3-1.
770  3.3.00.02a.ii.d    2.a) The nuclear island structures,                  ii) An inspection of the as-built ii.d) A report exists that including the critical sections listed in            concrete thickness will be        concludes that the as-built Table 3.3-7, are seismic Category I                  performed.                        concrete thicknesses of the and are designed and constructed to                                                    radiologically controlled area withstand design basis loads as                                                        of the auxiliary building specified in the Design Description,                                                  sections conform to the without loss of structural integrity and                                              building sections defined in the safety-related functions.                                                          Table 3.3-1.
771  3.3.00.02a.ii.e    2.a) The nuclear island structures,                  ii) An inspection of the as-built ii.e) A report exists that including the critical sections listed in            concrete thickness will be        concludes that the as-built Table 3.3-7, are seismic Category I                  performed.                        concrete thicknesses of the and are designed and constructed to                                                    annex building sections withstand design basis loads as                                                        conform with the building specified in the Design Description,                                                  sections defined in without loss of structural integrity and                                              Table 3.3-1.
the safety-related functions.
772  3.3.00.02a.ii.f    2.a) The nuclear island structures,                  ii) An inspection of the as-built ii.f) A report exists that including the critical sections listed in            concrete thickness will be        concludes that the as-built Table 3.3-7, are seismic Category I                  performed.                        concrete thicknesses of the and are designed and constructed to                                                    turbine building sections withstand design basis loads as                                                        conform to the building specified in the Design Description,                                                  sections defined in without loss of structural integrity and                                              Table 3.3-1.
the safety-related functions.
773    3.3.00.02b      2.b) Site grade level is located relative            Inspection of the as-built site  Site grade is consistent with to floor elevation 100'-0" per                      grade will be conducted.          design plant grade within the Table 3.3-5.                                                                          dimension defined on Table 3.3-5.
774    3.3.00.02c      2.c) The containment and its                        See ITAAC Table 2.2.1-3,          See ITAAC Table 2.2.1-3, penetrations are designed and                        Items 2.a, 2.b, 3.a, and 3.b. Items 2.a, 2.b, 3.a, and 3.b.
constructed to ASME Code Section III, Class MC.(2)
: 2. Containment isolation devices are addressed in subsection 2.2.1, Containment System.
C-451
 
Table 3.3-6 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No.            Design Commitment                  Inspections, Tests, Analyses        Acceptance Criteria 775  3.3.00.02d 2.d) The containment and its              See ITAAC Table 2.2.1-3,          See ITAAC Table 2.2.1-3, penetrations retain their pressure        Items 4.a and 4.b.                Items 4.a and 4.b.
boundary integrity associated with the design pressure.
776  3.3.00.02e 2.e) The containment and its              See ITAAC Table 2.2.1-3,          See ITAAC Table 2.2.1-3, penetrations maintain the containment    Items 4.a, 4.b, and 7.            Items 4.a, 4.b, and 7.
leakage rate less than the maximum allowable leakage rate associated with the peak containment pressure for the design basis accident.
777  3.3.00.02f 2.f) The key dimensions of nuclear        An inspection will be performed  A report exists and concludes island structures are defined on          of the as-built configuration of  that the key dimensions of the Table 3.3-5.                              the nuclear island structures. as-built nuclear island structures are consistent with the dimensions defined on Table 3.3-5.
778  3.3.00.02g 2.g) The containment vessel greater      The maximum containment          The containment vessel than 7 feet above the operating deck      vessel inside height from the    maximum inside height from provides a heat transfer surface. A free  operating deck is measured and    the operating deck is 146'-7" volume exists inside the containment      the inner radius below the spring (with tolerance of +12", -6"),
shell above the operating deck.          line is measured at two          and the inside diameter is orthogonal radial directions at  130 feet nominal (with one elevation.                    tolerance of +12", -6").
779  3.3.00.02h 2.h) The free volume in the              An inspection will be performed  A report exists and concludes containment allows for floodup to        of the as-built containment      that the floodup volume of support long-term core cooling for        structures and equipment. The    this portion of the containment postulated loss-of-coolant accidents. portions of the containment      is less than 73,500 ft3 to an included in this inspection are  elevation of 108'.
the volumes that flood with a loss-of-coolant accident in passive core cooling system valve/equipment room B (11207). The in-containment refueling water storage tank volume is excluded from this inspection.
C-452
 
Table 3.3-6 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No.            Design Commitment                  Inspections, Tests, Analyses        Acceptance Criteria 780  3.3.00.03a 3. Walls and floors of the nuclear        Inspection of the as-built nuclear a) A report exists and island structures as defined on          island structures wall and floor  concludes that the shield walls Table 3.3-1 except for designed          thicknesses will be performed. and floors of the containment openings or penetrations provide                                            internal structures as defined shielding during normal operations.                                          in Table 3.3-1, except for designed openings or penetrations, are consistent with the concrete wall thicknesses provided in Table 3.3-1.
781  3.3.00.03b 3. Walls and floors of the nuclear        Inspection of the as-built nuclear b) A report exists and island structures as defined on          island structures wall and floor  concludes that the shield walls Table 3.3-1 except for designed          thicknesses will be performed. of the shield building openings or penetrations provide                                            structures as defined in Table shielding during normal operations.                                          3.3-1 except for designed openings or penetrations are consistent with the concrete wall thicknesses provided in Table 3.3-1.
782  3.3.00.03c 3. Walls and floors of the nuclear        Inspection of the as-built nuclear c) A report exists and island structures as defined on          island structures wall and floor  concludes that the shield walls Table 3.3-1 except for designed          thicknesses will be performed. and floors of the openings or penetrations provide                                            non-radiologically controlled shielding during normal operations.                                          area of the auxiliary building as defined in Table 3.3-1 except for designed openings or penetrations are consistent with the concrete wall thicknesses provided in Table 3.3-1.
783  3.3.00.03d 3. Walls and floors of the nuclear        Inspection of the as-built nuclear d) A report exists and island structures as defined on          island structures wall and floor  concludes that the shield walls Table 3.3-1 except for designed          thicknesses will be performed. and floors of the openings or penetrations provide                                            radiologically controlled area shielding during normal operations.                                          of the auxiliary building as defined in Table 3.3-1 except for designed openings or penetrations are consistent with the concrete wall thicknesses provided in Table 3.3-1.
C-453
 
Table 3.3-6 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No.            Design Commitment                  Inspections, Tests, Analyses        Acceptance Criteria 784  3.3.00.04a 4.a) Walls and floors of the annex        Inspection of the as-built annex A report exists and concludes building as defined on Table 3.3-1        building wall and floor          that the shield walls and floors except for designed openings or          thicknesses will be performed. of the annex building as penetrations provide shielding during                                      defined on Table 3.3-1 except normal operations.                                                        for designed openings or penetrations are consistent with the minimum concrete wall thicknesses provided in Table 3.3-1.
785  3.3.00.04b 4.b) Walls of the waste accumulation      Inspection of the as-built      A report exists and concludes room in the radwaste building except      radwaste building wall          that the shield walls of the for designed openings or penetrations    thicknesses will be performed. waste accumulation room in provide shielding during normal                                            the radwaste building except operations.                                                                for designed openings or penetrations are consistent with the minimum concrete wall thicknesses of 1'-4".
786  3.3.00.04c 4.c) Walls of the packaged waste          Inspection of the as-built      A report exists and concludes storage room in the radwaste building    radwaste building wall          that the shield walls of the except for designed openings or          thicknesses will be performed. packaged waste storage room penetrations provide shielding during                                      in the radwaste building normal operations.                                                        except for the wall shared with the waste accumulation room and designed openings or penetrations are consistent with the minimum concrete wall thicknesses of 2'.
787  3.3.00.05a 5.a) Exterior walls and the basemat of    An inspection of the as-built    A report exists that confirms the nuclear island have a water barrier  water barrier will be performed  that a water barrier exists on up to site grade.                        during construction.            the nuclear island exterior walls up to site grade.
788  3.3.00.05b 5.b) The boundaries between rooms        An inspection of the auxiliary  A report exists that confirms identified in Table 3.3-2 of the          building rooms will be          floors and walls as identified auxiliary building are designed to        performed.                      on Table 3.3-2 have provisions prevent flooding of rooms that contain                                    to prevent flooding between safety-related equipment.                                                  rooms up to the maximum flood levels for each room defined in Table 3.3-2.
C-454
 
Table 3.3-6 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No.            Design Commitment                  Inspections, Tests, Analyses        Acceptance Criteria 789  3.3.00.05c 5.c) The boundaries between the            An inspection of the boundaries  A report exists that confirms following rooms, which contain            between the following rooms      that flooding of the PXS safety-related equipment - PXS            which contain safety-related    Valve/ Accumulator Room A valve/accumulator room A (11205),          equipment - PXS Valve/          (11205), and the PXS valve/accumulator room B              Accumulator Room A (11205),      PXS/Accumulator Room B (11207), and CVS room (11209) - are        PXS Valve/Accumulator            (11207) is prevented to a designed to prevent flooding between      Room B (11207), and              maximum flood level as these rooms.                              CVS Room (11209) - will be      follows: PXS A 110'-2",
performed.                      PXS B 110'-1"; and of the CVS room (11209) to a maximum flood level of 110'-0".
790  3.3.00.06a 6.a) The available room volumes of        An inspection will be performed  A report exists and concludes the radiologically controlled area of      of the as-built radiologically  that the as-built available the auxiliary building between floor      controlled area of the auxiliary room volumes of the elevations 66'-6" and 82'-6" exceed the    building between floor          radiologically controlled area volume of the liquid radwaste storage      elevations 66'-6" and 82'-6" to  of the auxiliary building tanks (WLS-MT-05A, MT-05B,                define volume.                  between floor elevations MT-06A, MT-06B, MT-07A, MT-07B,                                            66'-6" and 82'-6" exceed the MT-07C, MT-11).                                                            volume of the liquid radwaste storage tanks (WLS-MT-05A, MT-05B, MT-06A, MT-06B, MT-07A, MT-07B, MT-07C, MT-11).
791  3.3.00.06b 6.b) The radwaste building package        An inspection of the radwaste    The volume of the radwaste waste storage room has a volume            building packaged waste storage  building packaged waste greater than or equal to 1293 cubic        room (50352) is performed.      storage room (50352) is feet.                                                                      greater than or equal to 1293 cubic feet.
792  3.3.00.07aa 7.a) Class 1E electrical cables,          Inspections of the as-built      a) Class 1E electrical cables, communication cables associated with      Class 1E cables and raceways    and communication cables only one division, and raceways are        will be conducted.              inside containment associated identified according to applicable                                          with only one division, and color-coded Class 1E divisions.                                            raceways are identified by the appropriate color code.
793  3.3.00.07ab 7.a) Class 1E electrical cables,          Inspections of the as-built      b) Class 1E electrical cables, communication cables associated with      Class 1E cables and raceways    and communication cables in only one division, and raceways are        will be conducted.              the non-radiologically identified according to applicable                                          controlled area of the auxiliary color-coded Class 1E divisions.                                            building associated with only one division, and raceways are identified by the appropriate color code.
C-455
 
Table 3.3-6 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No.            Design Commitment                    Inspections, Tests, Analyses      Acceptance Criteria 794  3.3.00.07ac 7.a) Class 1E electrical cables,            Inspections of the as-built    c) Class 1E electrical cables, communication cables associated with        Class 1E cables and raceways  and communication cables in only one division, and raceways are        will be conducted.            the radiologically controlled identified according to applicable                                        area of the auxiliary building color-coded Class 1E divisions.                                            associated with only one division, and raceways are identified by the appropriate color code.
795  3.3.00.07ba 7.b) Class 1E divisional electrical        Inspections of the as-built    a) Class 1E electrical cables cables and communication cables            Class 1E divisional cables and and communication cables associated with only one division are      raceways will be conducted. inside containment associated routed in their respective divisional                                      with only one division are raceways.                                                                  routed in raceways assigned to the same division. There are no other safety division electrical cables in a raceway assigned to a different division.
796  3.3.00.07bb 7.b) Class 1E divisional electrical        Inspections of the as-built    b) Class 1E electrical cables cables and communication cables            Class 1E divisional cables and and communication cables in associated with only one division are      raceways will be conducted. the non-radiologically routed in their respective divisional                                      controlled area of the auxiliary raceways.                                                                  building associated with only one division are routed in raceways assigned to the same division. There are no other safety division electrical cables in a raceway assigned to a different division.
797  3.3.00.07bc 7.b) Class 1E divisional electrical        Inspections of the as-built    c) Class 1E electrical cables cables and communication cables            Class 1E divisional cables and and communication cables in associated with only one division are      raceways will be conducted. the radiologically controlled routed in their respective divisional                                      area of the auxiliary building raceways.                                                                  associated with only one division are routed in raceways assigned to the same division. There are no other safety division electrical cables in a raceway assigned to a different division.
C-456
 
Table 3.3-6 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No.                Design Commitment                    Inspections, Tests, Analyses        Acceptance Criteria 798  3.3.00.07c.i.a  7.c) Separation is maintained between      i) Inspections of the as-built    i.a) Results of the inspection Class 1E divisions in accordance with      Class 1E division electrical      will confirm that the the fire areas as identified in            cables, communication cables      separation between Class 1E Table 3.3-3.                                associated with only one          divisions in the non-division, and raceways located in radiologically controlled area the fire areas identified in      of the auxiliary building is Table 3.3-3 will be conducted. consistent with Table 3.3-3.
799  3.3.00.07c.i.b  7.c) Separation is maintained between      i) Inspections of the as-built    i.b) Results of the inspection Class 1E divisions in accordance with      Class 1E division electrical      will confirm that the the fire areas as identified in            cables, communication cables      separation between Class 1E Table 3.3-3.                                associated with only one          divisions in the radiologically division, and raceways located in controlled area of the auxiliary the fire areas identified in      building is consistent with Table 3.3-3 will be conducted. Table 3.3-3.
800  3.3.00.07c.ii.a 7.c) Separation is maintained between      ii) Inspections of the as-built  ii.a) Results of the inspection Class 1E divisions in accordance with      fire barriers between the fire    will confirm that fire barriers the fire areas as identified in            areas identified in Table 3.3-3  exist between fire areas Table 3.3-3.                                will be conducted.                identified in Table 3.3-3 inside the non-radiologically controlled area of the auxiliary building.
801  3.3.00.07c.ii.b 7.c) Separation is maintained between      ii) Inspections of the as-built  ii.b) Results of the inspection Class 1E divisions in accordance with      fire barriers between the fire    will confirm that fire barriers the fire areas as identified in            areas identified in Table 3.3-3  exist between fire areas Table 3.3-3.                                will be conducted.                identified in Table 3.3-3 inside the radiologically controlled area of the auxiliary building.
802  3.3.00.07d.i  7.d) Physical separation is maintained      Inspections of the as-built      Results of the inspection will between Class 1E divisions and              Class 1E raceways will be        confirm that the separation between Class 1E divisions and non-        performed to confirm that the    between Class 1E raceways of Class 1E cables.                            separation between Class 1E      different divisions and raceways of different divisions  between Class 1E raceways and between Class 1E raceways    and non-Class 1E raceways is and non-Class 1E raceways is      consistent with the following:
consistent with the following:    i) Within the main control i) Within the main control room    room and remote shutdown and remote shutdown room, the      room, the vertical separation minimum vertical separation is    is 3 inches or more and the 3 inches and the minimum          horizontal separation is 1 inch horizontal separation is 1 inch. or more.
C-457
 
Table 3.3-6 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No.              Design Commitment                    Inspections, Tests, Analyses        Acceptance Criteria 803  3.3.00.07d.ii.a 7.d) Physical separation is maintained    Inspections of the as-built      Results of the inspection will between Class 1E divisions and            Class 1E raceways will be        confirm that the separation between Class 1E divisions and non-      performed to confirm that the    between Class 1E raceways of Class 1E cables.                          separation between Class 1E      different divisions and raceways of different divisions  between Class 1E raceways and between Class 1E raceways    and non-Class 1E raceways is and non-Class 1E raceways is    consistent with the following:
consistent with the following:  ii.a) Within other plant areas ii) Within other plant areas    inside containment (limited (limited hazard areas), the      hazard areas), the separation minimum separation is defined    meets one of the following:
by one of the following:        1) The vertical separation is
: 1) The minimum vertical          5 feet or more and the separation is 5 feet and the    horizontal separation is 3 feet minimum horizontal separation    or more except.
is 3 feet.                      2) The minimum vertical
: 2) The minimum vertical          separation is 12 inches and the separation is 12 inches and the  minimum horizontal minimum horizontal separation    separation is 6 inches for is 6 inches for raceways        raceways containing only containing only instrumentation  instrumentation and control and control and low-voltage      and low-voltage power cables power cables <2/0 AWG.          <2/0 AWG.
: 3) For configurations that      3) For configurations that involve exclusively limited      involve exclusively limited energy content cables            energy content cables (instrumentation and control),  (instrumentation and control),
the minimum vertical separation  the minimum vertical is 3 inches and the minimum      separation is 3 inches and the horizontal separation is 1 inch. minimum horizontal
: 4) For configurations involving  separation is 1 inch.
an enclosed raceway and an      4) For configurations that open raceway, the minimum        involve an enclosed raceway vertical separation is 1 inch if and an open raceway, the the enclosed raceway is below    minimum vertical separation the open raceway.                is 1 inch if the enclosed
: 5) For configuration involving  raceway is below the raceway.
enclosed raceways, the          5) For configurations that minimum separation is 1 inch in  involve enclosed raceways, both horizontal and vertical    the minimum vertical and directions.                      horizontal separation is 1 inch.
C-458
 
Table 3.3-6 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No.              Design Commitment                    Inspections, Tests, Analyses        Acceptance Criteria 804  3.3.00.07d.ii.b 7.d) Physical separation is maintained    Inspections of the as-built      Results of the inspection will between Class 1E divisions and            Class 1E raceways will be        confirm that the separation between Class 1E divisions and non-      performed to confirm that the    between Class 1E raceways of Class 1E cables.                          separation between Class 1E      different divisions and raceways of different divisions  between Class 1E raceways and between Class 1E raceways    and non-Class 1E raceways is and non-Class 1E raceways is    consistent with the following:
consistent with the following:  ii.b) Within other plant areas ii) Within other plant areas    inside the non-radiologically (limited hazard areas), the      controlled area of the auxiliary minimum separation is defined    building (limited hazard by one of the following:        areas), the separation meets
: 1) The minimum vertical          one of the following:
separation is 5 feet and the    1) The vertical separation is minimum horizontal separation    5 feet or more and the is 3 feet.                      horizontal separation is 3 feet
: 2) The minimum vertical          or more except.
separation is 12 inches and the  2) The minimum vertical minimum horizontal separation    separation is 12 inches and the is 6 inches for raceways        minimum horizontal containing only instrumentation  separation is 6 inches for and control and low-voltage      raceways containing only power cables <2/0 AWG.          instrumentation and control
: 3) For configurations that      and low-voltage power cables involve exclusively limited      < 2/0 AWG.
energy content cables            3) For configurations that (instrumentation and control),  involve exclusively limited the minimum vertical separation  energy content cables is 3 inches and the minimum      (instrumentation and control),
horizontal separation is 1 inch. the minimum vertical
: 4) For configurations involving  separation is 3 inches and the an enclosed raceway and an      minimum horizontal open raceway, the minimum        separation is 1 inch.
vertical separation is 1 inch if 4) For configurations that the enclosed raceway is below    involve an enclosed raceway, the open raceway.                the minimum vertical
: 5) For configuration involving  separation is 1 inch if the enclosed raceways, the          enclosed raceway is below the minimum separation is 1 inch in  raceway.
both horizontal and vertical    5) For configurations that directions.                      involve enclosed raceways, the minimum vertical and horizontal separation is 1 inch.
C-459
 
Table 3.3-6 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No.              Design Commitment                    Inspections, Tests, Analyses        Acceptance Criteria 805  3.3.00.07d.ii.c 7.d) Physical separation is maintained    Inspections of the as-built      Results of the inspection will between Class 1E divisions and            Class 1E raceways will be        confirm that the separation between Class 1E divisions and non-      performed to confirm that the    between Class 1E raceways of Class 1E cables.                          separation between Class 1E      different divisions and raceways of different divisions  between Class 1E raceways and between Class 1E raceways    and non-Class 1E raceways is and non-Class 1E raceways is    consistent with the following:
consistent with the following:  ii.c) Within other plant areas ii) Within other plant areas    inside the radiologically (limited hazard areas), the      controlled area of the auxiliary minimum separation is defined    building (limited hazard by one of the following:        areas), the separation meets
: 1) The minimum vertical          one of the following:
separation is 5 feet and the    1) The vertical separation is minimum horizontal separation    5 feet or more and the is 3 feet.                      horizontal separation is 3 feet
: 2) The minimum vertical          or more except.
separation is 12 inches and the  2) The minimum vertical minimum horizontal separation    separation is 12 inches and the is 6 inches for raceways        minimum horizontal containing only instrumentation  separation is 6 inches for and control and low-voltage      raceways containing only power cables <2/0 AWG.          instrumentation and control
: 3) For configurations that      and low-voltage power cables involve exclusively limited      < 2/0 AWG.
energy content cables            3) For configurations that (instrumentation and control),  involve exclusively limited the minimum vertical separation  energy content cables is 3 inches and the minimum      (instrumentation and control),
horizontal separation is 1 inch. the minimum vertical
: 4) For configurations involving  separation is 3 inches and the an enclosed raceway and an      minimum horizontal open raceway, the minimum        separation is 1 inch.
vertical separation is 1 inch if 4) For configurations that the enclosed raceway is below    involve an enclosed raceway the open raceway.                and an open raceway, the
: 5) For configuration involving  minimum vertical separation enclosed raceways, the          is 1 inch if the enclosed minimum separation is 1 inch in  raceway is below the raceway.
both horizontal and vertical    5) For configurations that directions.                      involve enclosed raceways, the minimum vertical and horizontal separation is 1 inch.
C-460
 
Table 3.3-6 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No.              Design Commitment                    Inspections, Tests, Analyses        Acceptance Criteria 806  3.3.00.07d.iii.a 7.d) Physical separation is maintained    Inspections of the as-built      Results of the inspection will between Class 1E divisions and            Class 1E raceways will be        confirm that the separation between Class 1E divisions and non-      performed to confirm that the    between Class 1E raceways of Class 1E cables.                          separation between Class 1E      different divisions and raceways of different divisions  between Class 1E raceways and between Class 1E raceways    and non-Class 1E raceways is and non-Class 1E raceways is      consistent with the following:
consistent with the following:    iii.a) Where minimum iii) Where minimum separation    separation distances are not distances are not maintained, the met inside containment, the circuits are run in enclosed      circuits are run in enclosed raceways or barriers are          raceways or barriers are provided.                        provided.
807  3.3.00.07d.iii.b 7.d) Physical separation is maintained    Inspections of the as-built      Results of the inspection will between Class 1E divisions and            Class 1E raceways will be        confirm that the separation between Class 1E divisions and non-      performed to confirm that the    between Class 1E raceways of Class 1E cables.                          separation between Class 1E      different divisions and raceways of different divisions  between Class 1E raceways and between Class 1E raceways    and non-Class 1E raceways is and non-Class 1E raceways is      consistent with the following:
consistent with the following:    iii.b) Where minimum iii) Where minimum separation    separation distances are not distances are not maintained, the met inside the circuits are run in enclosed      non-radiologically controlled raceways or barriers are          area of the auxiliary building, provided.                        the circuits are run in enclosed raceways or barriers are provided.
808  3.3.00.07d.iii.c 7.d) Physical separation is maintained    Inspections of the as-built      Results of the inspection will between Class 1E divisions and            Class 1E raceways will be        confirm that the separation between Class 1E divisions and non-      performed to confirm that the    between Class 1E raceways of Class 1E cables.                          separation between Class 1E      different divisions and raceways of different divisions  between Class 1E raceways and between Class 1E raceways    and non-Class 1E raceways is and non-Class 1E raceways is      consistent with the following:
consistent with the following:    iii.c) Where minimum iii) Where minimum separation    separation distances are not distances are not maintained, the met inside the radiologically circuits are run in enclosed      controlled area of the auxiliary raceways or barriers are          building, the circuits are run in provided.                        enclosed raceways or barriers are provided.
C-461
 
Table 3.3-6 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No.              Design Commitment                  Inspections, Tests, Analyses        Acceptance Criteria 809  3.3.00.07d.iv.a 7.d) Physical separation is maintained    Inspections of the as-built      Results of the inspection will between Class 1E divisions and            Class 1E raceways will be        confirm that the separation between Class 1E divisions and non-      performed to confirm that the    between Class 1E raceways of Class 1E cables.                          separation between Class 1E      different divisions and raceways of different divisions  between Class 1E raceways and between Class 1E raceways    and non-Class 1E raceways is and non-Class 1E raceways is    consistent with the following:
consistent with the following:  iv.a) For areas inside iv) Separation distances less    containment, a report exists than those specified above and  and concludes that separation not run in enclosed raceways or  distances less than those provided with barriers are based specified above and not on analysis                      provided with enclosed raceways or barriers have been analyzed.
810  3.3.00.07d.iv.b 7.d) Physical separation is maintained    Inspections of the as-built      Results of the inspection will between Class 1E divisions and            Class 1E raceways will be        confirm that the separation between Class 1E divisions and non-      performed to confirm that the    between Class 1E raceways of Class 1E cables.                          separation between Class 1E      different divisions and raceways of different divisions  between Class 1E raceways and between Class 1E raceways    and non-Class 1E raceways is and non-Class 1E raceways is    consistent with the following:
consistent with the following:  iv.b) For areas inside the iv) Separation distances less    non-radiologically controlled than those specified above and  area of the auxiliary building, not run in enclosed raceways or  a report exists and concludes provided with barriers are based that separation distances less on analysis                      than those specified above and not provided with enclosed raceways or barriers have been analyzed.
C-462
 
Table 3.3-6 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No.              Design Commitment                  Inspections, Tests, Analyses        Acceptance Criteria 811  3.3.00.07d.iv.c 7.d) Physical separation is maintained    Inspections of the as-built      Results of the inspection will between Class 1E divisions and            Class 1E raceways will be        confirm that the separation between Class 1E divisions and non-      performed to confirm that the    between Class 1E raceways of Class 1E cables.                          separation between Class 1E      different divisions and raceways of different divisions  between Class 1E raceways and between Class 1E raceways    and non-Class 1E raceways is and non-Class 1E raceways is      consistent with the following:
consistent with the following:    iv.c) For areas inside the iv) Separation distances less    radiologically controlled area than those specified above and    of the auxiliary building, a not run in enclosed raceways or  report exists and concludes provided with barriers are based  that separation distances less on analysis                      than those specified above and not provided with enclosed raceways or barriers have been analyzed.
812  3.3.00.07d.v.a  7.d) Physical separation is maintained    Inspections of the as-built      Results of the inspection will between Class 1E divisions and            Class 1E raceways will be        confirm that the separation between Class 1E divisions and non-      performed to confirm that the    between Class 1E raceways of Class 1E cables.                          separation between Class 1E      different divisions and raceways of different divisions  between Class 1E raceways and between Class 1E raceways    and non-Class 1E raceways is and non-Class 1E raceways is      consistent with the following:
consistent with the following:    v.a) For areas inside v) Non-Class 1E wiring that is    containment, non-Class 1E not separated from Class 1E or    wiring that is not separated associated wiring by the          from Class 1E or associated minimum separation distance or    wiring by the minimum by a barrier or analyzed is      separation distance or by a considered as associated circuits barrier or analyzed is treated and subject to Class 1E          as Class 1E wiring.
requirements.
C-463
 
Table 3.3-6 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No.              Design Commitment                  Inspections, Tests, Analyses          Acceptance Criteria 813  3.3.00.07d.v.b 7.d) Physical separation is maintained    Inspections of the as-built      Results of the inspection will between Class 1E divisions and            Class 1E raceways will be        confirm that the separation between Class 1E divisions and non-        performed to confirm that the    between Class 1E raceways of Class 1E cables.                          separation between Class 1E      different divisions and raceways of different divisions  between Class 1E raceways and between Class 1E raceways    and non-Class 1E raceways is and non-Class 1E raceways is      consistent with the following:
consistent with the following:    v.b) For areas inside the v) Non-Class 1E wiring that is    non-radiologically controlled not separated from Class 1E or    area of the auxiliary building, associated wiring by the          non-Class 1E wiring that is minimum separation distance or    not separated from Class 1E by a barrier or analyzed is      or associated wiring by the considered as associated circuits minimum separation distance and subject to Class 1E          or by a barrier or analyzed is requirements.                    treated as Class 1E wiring.
814  3.3.00.07d.v.c 7.d) Physical separation is maintained    Inspections of the as-built      Results of the inspection will between Class 1E divisions and            Class 1E raceways will be        confirm that the separation between Class 1E divisions and non-        performed to confirm that the    between Class 1E raceways of Class 1E cables.                          separation between Class 1E      different divisions and raceways of different divisions  between Class 1E raceways and between Class 1E raceways    and non-Class 1E raceways is and non-Class 1E raceways is      consistent with the following:
consistent with the following:    v.c) For areas inside the v) Non-Class 1E wiring that is    radiologically controlled area not separated from Class 1E or    of the auxiliary building, non-associated wiring by the          Class 1E wiring that is not minimum separation distance or    separated from Class 1E or by a barrier or analyzed is      associated wiring by the considered as associated circuits minimum separation distance and subject to Class 1E          or by a barrier or analyzed is requirements.                    treated as Class 1E wiring.
815    3.3.00.07e  7.e) Class 1E communication cables        Inspections of the as-built      Class 1E communication which interconnect two divisions are      Class 1E communication cables    cables which interconnect two routed and separated such that the        will be conducted.                divisions are routed and Protection and Safety Monitoring                                            separated such that the System voting logic is not defeated by                                      Protection and Safety the loss of any single raceway or fire                                      Monitoring System voting area.                                                                        logic is not defeated by the loss of any single raceway or fire area.
C-464
 
Table 3.3-6 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No.              Design Commitment                    Inspections, Tests, Analyses          Acceptance Criteria 816    3.3.00.08  8. Systems, structures, and                Following as-built                An as-built Pipe Rupture components identified as essential          reconciliation, an inspection will Hazard Analysis Report exists targets are protected from the dynamic      be performed of the as-built high  and concludes that systems, and environmental effects of                and moderate energy pipe          structures, and components postulated pipe ruptures.                  rupture mitigation features for    identified as essential targets systems, structures, and          can withstand the effects of components identified as          postulated pipe rupture essential targets.                without loss of required safety function.
817    3.3.00.09  9. The reactor cavity sump has a            An inspection of the as-built      A report exists and concludes minimum concrete thickness as shown        containment building internal      that the reactor cavity sump in Table 3.3-5 between the bottom of        structures will be performed.      has a minimum concrete the sump and the steel containment.                                            thickness as shown on Table 3.3-5 between the bottom of the sump and the steel containment.
818  3.3.00.10.i  10. The shield building roof and PCS        i) A test will be performed to    i) A report exists and storage tank support and retain the        measure the leakage from the      concludes that total water flow PCS water sources. The PCS storage          PCS storage tank based on          from the leak chase collection tank has a stainless steel liner which      measuring the water flow out of    system does not exceed provides a barrier on the inside            the leak chase collection system. 10 gal/hr.
surfaces of the tank. Leak chase channels are provided on the tank boundary liner welds.
819  3.3.00.10.ii 10. The shield building roof and PCS        ii) An inspection of the PCS      ii) A report exists and storage tank support and retain the        storage tank exterior tank        concludes that inspection and PCS water sources. The PCS storage          boundary and shield building      measurement of the PCS tank has a stainless steel liner which      tension ring will be performed    storage tank and the tension provides a barrier on the inside            before and after filling of the    ring structure, before and after surfaces of the tank. Leak chase            PCS storage tank to the overflow  filling of the tank, shows channels are provided on the tank          level. The vertical elevation of  structural behavior under boundary liner welds.                      the shield building roof will be  normal loads to be acceptable.
measured at a location at the outer radius of the roof (tension ring) and at a location on the same azimuth at the outer radius of the PCS storage tank before and after filling the PCS storage tank.
C-465
 
Table 3.3-6 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No.              Design Commitment                    Inspections, Tests, Analyses        Acceptance Criteria 820  3.3.00.10.iii 10. The shield building roof and PCS        iii) An inspection of the PCS    iii) A report exists and storage tank support and retain the        storage tank exterior tank      concludes that there is no PCS water sources. The PCS storage          boundary and shield building    visible water leakage from the tank has a stainless steel liner which      tension ring will be performed  PCS storage tank through the provides a barrier on the inside            before and after filling of the  concrete and that there is no surfaces of the tank. Leak chase            PCS storage tank to the overflow visible excessive cracking in channels are provided on the tank          level. The boundaries of the PCS the boundaries of the PCS boundary liner welds.                      storage tank and the shield      storage tank and the shield building roof above the tension  building roof above the ring will be inspected visually  tension ring.
for excessive concrete cracking.
: 11. Deleted 821  3.3.00.12    12. The extended turbine generator          An inspection of the as-built    The extended axis of the axis intersects the shield building.        turbine generator will be        turbine generator intersects performed.                      the shield building.
822  3.3.00.13    13. Separation is provided between          An inspection of the separation  The minimum horizontal the structural elements of the turbine,    of the nuclear island from the  clearance above floor annex and radwaste buildings and the        annex, radwaste and turbine      elevation 100-0 between the nuclear island structure. This              building structures will be      structural elements of the separation permits horizontal motion        performed. The inspection will  annex and radwaste buildings of the buildings in the safe shutdown      verify the specified horizontal  and the nuclear island is earthquake without impact between          clearance between structural    4 inches. The minimum structural elements of the buildings.      elements of the adjacent        horizontal clearance above buildings, consisting of the    floor elevation 100-0 reinforced concrete walls and    between the structural slabs, structural steel columns  elements of the turbine and floor beams.                building and the nuclear island is 4 inches.
823  3.3.00.14    14. The external walls, doors, ceiling,    Type test, analysis, or a        A report exists and concludes and floors in the main control room,        combination of type test and    that the external walls, doors, the central alarm station, and the          analysis will be performed for  ceilings, and floors in the secondary alarm station are                the external walls, doors,      main control room, the central bullet-resistant to at least Underwriters  ceilings, and floors in the main alarm station, and the Laboratory Ballistic Standard 752,          control room, the central alarm  secondary alarm station are level 4.                                    station, and the secondary alarm bullet-resistant to at least station.                        Underwriters Laboratory Ballistic Standard 752, level 4.
: 15. Deleted C-466
 
Table 3.3-6 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No.          Design Commitment                    Inspections, Tests, Analyses        Acceptance Criteria 824  3.3.00.16 16. Secondary security power supply        An inspection will be performed    Secondary security power system for alarm annunciator              to ensure that the location of the supply equipment for alarm equipment and non-portable                secondary security power supply    annunciator equipment and communications equipment is located        equipment for alarm annunciator    non-portable communication within a vital area.                      equipment and non-portable        equipment is located within a communications equipment is        vital area.
within a vital area.
825  3.3.00.17 17. Vital areas are locked and alarmed    An inspection of the as-built      Vital areas are locked and with active intrusion detection systems    vital areas, and central and      alarmed with active intrusion that annunciate in the central and        secondary alarm stations are      detection systems and secondary alarm stations upon              performed.                        intrusion is detected and intrusion into a vital area.                                                  annunciated in both the central and secondary alarm stations.
: 18. Deleted C-467
 
Table 3.3-7 Nuclear Island Critical Structural Sections Containment Internal Structures South west wall of the refueling cavity South wall of the west steam generator cavity North east wall of the in-containment refueling water storage tank In-containment refueling water storage tank steel wall Column supporting the operating floor Auxiliary and Shield Building South wall of auxiliary building (column line 1), elevation 66'-6" to elevation 180'-0" Interior wall of auxiliary building (column line 7.3), elevation 66'-6" to elevation 160'-6" West wall of main control room in auxiliary building (column line L), elevation 117'-6" to elevation 153'-0" North wall of MSIV east compartment (column line 11 between lines L and M), elevation 117'-6" to elevation 153'-0" Roof slab at elevation 180'-0" adjacent to shield building cylinder Floor slab on metal decking at elevation 135'-3" 2'-0" slab in auxiliary building (tagging room ceiling) at elevation 135'-3" Finned floor in the main control room at elevation 135'-3" Shield building roof, exterior wall of the PCS water storage tank Shield building roof, interior wall of the PCS water storage tank Shield building roof, tension ring and air inlets Divider wall between the spent fuel pool and the fuel transfer canal Shield building SC cylinder Shield building SC to RC connection Nuclear Island Basemat Below Auxiliary Building Bay between reference column lines 9.1 and 11, and K and L Bay between reference column lines 1 and 2 and K-2 and N Figures 3.3-1 through 3.3-14 contain Security-Related Information. (See Attachment 1 to Turkey Point Unit 7 COL Appendix C)
C-468
 
3.4      Initial Test Program No ITAAC for this system.
3.5            Radiation Monitoring Design Description Radiation monitoring is provided for those plant areas where there is a significant potential for airborne contamination, for those process and effluent streams where contamination is possible, and in accessible areas to provide indication of unusual radiological events as identified in Tables 3.5-1, 3.5-2, 3.5-3, 3.5-4, and 3.5-5. The radiation monitoring component locations are as shown in Table 3.5-7.
: 1. The seismic Category I equipment identified in Table 3.5-1 can withstand seismic design basis loads without loss of safety function.
: 2. The Class 1E equipment identified in Table 3.5-1 as being qualified for a harsh environment can withstand the environmental conditions that would exist before, during, and following a design basis accident without loss of safety function for the time required to perform the safety function.
: 3. Separation is provided between system Class 1E divisions, and between Class 1E divisions and non-Class 1E cable.
: 4. Safety-related displays identified in Table 3.5-1 can be retrieved in the main control room (MCR).
: 5. The process radiation monitors listed in Table 3.5-2 are provided.
: 6. The effluent radiation monitors listed in Table 3.5-3 are provided.
: 7. The airborne radiation monitors listed in Table 3.5-4 are provided.
: 8. The area radiation monitors listed in Table 3.5-5 are provided.
C-469
 
Table 3.5-1 Qual. for      Safety-Seismic                        Harsh          Related Equipment Name                Tag No.            Cat. I        Class 1E        Envir.        Display Containment High Range            PXS-RE160              Yes            Yes          Yes            Yes Monitor Containment High Range            PXS-RE161              Yes            Yes          Yes            Yes Monitor Containment High Range            PXS-RE162              Yes            Yes          Yes            Yes Monitor Containment High Range            PXS-RE163              Yes            Yes          Yes            Yes Monitor MCR Radiation Monitoring          VBS-JS01A              Yes            Yes          No            No Package A(1)
MCR Radiation Monitoring          VBS-JS01B              Yes            Yes          No            No Package B(1)
Containment Atmosphere            PSS-RE026              Yes            No            No            No Monitor (Gaseous)
Containment Atmosphere            PSS-RE027              Yes            No            No            No Monitor (gaseous, for RCS pressure boundary leakage detection)
Notes: (1) Each MCR Radiation Monitoring Package includes particulate, iodine and gaseous radiation monitors.
C-470
 
Table 3.5-2 Process Radiation Monitors Equipment List                                          Equipment No.
Steam Generator Blowdown                                            BDS-RE010 Steam Generator Blowdown                                            BDS-RE011 Component Cooling Water                                              CCS-RE001 Main Steam Line(1)                                                  SGS-RY026 Main Steam Line(1)                                                  SGS-RY027 Service Water Blowdown                                              SWS-RE008 Primary Sampling System Liquid Sample                                PSS-RE050 Primary Sampling System Gaseous Sample                              PSS-RE052 Containment Air Filtration Exhaust                                  VFS-RE001 Gaseous Radwaste Discharge                                          WGS-RE017 Note:
: 1. Each main steam line monitor includes a noble gas detector and primary-to-secondary side leak detector.
Table 3.5-3 Effluent Radiation Monitors Equipment List                                          Equipment No.
Plant Vent (Normal Range Particulate)                                VFS-RE101 Plant Vent (Normal Range Iodine)                                    VFS-RE102 Plant Vent (Normal Range Radiogas)                                  VFS-RE103 Plant Vent (Mid Range Radiogas)                                    VFS-RE104A Plant Vent (High Range Radiogas)                                    VFS-RE104B Turbine Island Vent(1)                                              TDS-RY001 Liquid Radwaste Discharge                                          WLS-RE229 Wastewater Discharge                                                WWS-RE021 Note:
: 1. The turbine island vent includes a low and a high range detector.
C-471
 
Table 3.5-4 Airborne Radiation Monitors Equipment List                                              Equipment No.
Fuel Handling Area Exhaust Radiation Monitor                                    VAS-RE001 Auxiliary Building Exhaust Radiation Monitor                                    VAS-RE002 Annex Building Exhaust Radiation Monitor                                        VAS-RE003 Health Physics and Hot Machine Shop Exhaust                                      VHS-RE001 Radiation Monitor Radwaste Building Exhaust Radiation Monitor                                      VRS-RE023 Table 3.5-5 Area Radiation Monitors Primary Sampling Room                                                            RMS-RE008 Containment Area - Personnel Hatch                                              RMS-RE009 Operating Deck (135'-3" Elevation)
Main Control Room                                                                RMS-RE010 Chemistry Laboratory                                                            RMS-RE011 Fuel Handling Area 1                                                            RMS-RE012 Rail Car Bay/Filter Storage Area (Auxiliary Building                            RMS-RE013 Loading Bay)
Liquid and Gaseous Radwaste Area(1)                                              RMS-RY014 Control Support Area                                                            RMS-RE016 Radwaste Building Mobile Systems Facility                                        RMS-RE017 Hot Machine Shop                                                                RMS-RE018 Annex Staging and Storage Area                                                  RMS-RE019 Fuel Handling Area 2                                                            RMS-RE020 Containment Area - Personnel Hatch                                              RMS-RE021 Maintenance Level (100'-0" Elevation)
Note:
: 1. This monitor includes multiple detectors to monitor the areas of interest.
C-472
 
Table 3.5-6 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No.              Design Commitment                    Inspections, Tests, Analyses        Acceptance Criteria 826  3.5.00.01.i  1. The seismic Category I equipment        i) Inspection will be performed  i) The seismic Category I identified in Table 3.5-1 can withstand    to verify that the seismic        equipment identified in seismic design basis loads without loss    Category I equipment identified  Table 3.5-1 is located on the of safety function.                        in Table 3.5-1 is located on the  Nuclear Island.
Nuclear Island.
827  3.5.00.01.ii 1. The seismic Category I equipment        ii) Type tests, analyses, or a    ii) A report exists and identified in Table 3.5-1 can withstand    combination of type tests and    concludes that the seismic seismic design basis loads without loss    analyses of seismic Category I    Category I equipment can of safety function.                        equipment will be performed.      withstand seismic design basis loads without loss of safety function.
828  3.5.00.01.iii 1. The seismic Category I equipment        iii) Inspection will be performed iii) A report exists and identified in Table 3.5-1 can withstand    for the existence of a report    concludes that the as-built seismic design basis loads without loss    verifying that the as-built      equipment including of safety function.                        equipment including anchorage    anchorage is seismically is seismically bounded by the    bounded by the tested or tested or analyzed conditions. analyzed conditions.
829  3.5.00.02.i  2. The Class 1E equipment identified in    i) Type tests, analyses, or a    i) A report exists and Table 3.5-1 as being qualified for a        combination of type tests and    concludes that Class 1E harsh environment can withstand the        analyses will be performed on    equipment identified in environmental conditions that would        Class 1E equipment located in a  Table 3.5-1 as being located in exist before, during, and following a      harsh environment.                a harsh environment can design basis accident without loss of                                        withstand the environmental safety function for the time required to                                      conditions that would exist perform the safety function.                                                  before, during, and following a design basis accident without loss of safety function for the time required to perform the safety function.
830  3.5.00.02.ii 2. The Class 1E equipment identified in    ii) Inspection will be performed  ii) A report exists and Table 3.5-1 as being qualified for a        of the as-built Class 1E          concludes that the as-built harsh environment can withstand the        equipment and the associated      Class 1E equipment and the environmental conditions that would        wiring, cables, and terminations  associated wiring, cables, and exist before, during, and following a      located in a harsh environment. terminations identified in design basis accident without loss of                                        Table 3.5-1 as being qualified safety function for the time required to                                      for a harsh environment are perform the safety function.                                                  bounded by type tests, analyses, or a combination of type tests and analyses.
831    3.5.00.03  3. Separation is provided between          See ITAAC Table 3.3-6,            See ITAAC Table 3.3-6, system Class 1E divisions, and between      item 7.d).                        item 7.d).
Class 1E divisions and non-Class 1E cable.
C-473
 
Table 3.5-6 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No.                Design Commitment                    Inspections, Tests, Analyses        Acceptance Criteria 832  3.5.00.04    4. Safety-related displays identified in    Inspection will be performed for  Safety-related displays Table 3.5-1 can be retrieved in the        retrievability of the displays in identified in Table 3.5-1 can MCR.                                        the MCR.                          be retrieved in the MCR.
833  3.5.00.05    5. The process radiation monitors listed    Inspection for the existence of  Each of the monitors listed in in Table 3.5-2 are provided.                the monitors will be performed. Table 3.5-2 exists.
834  3.5.00.06    6. The effluent radiation monitors listed  Inspection for the existence of  Each of the monitors listed in in Table 3.5-3 are provided.                the monitors will be performed. Table 3.5-3 exists.
835  3.5.00.07    7. The airborne radiation monitors          Inspection for the existence of  Each of the monitors listed in listed in Table 3.5-4 are provided.        the monitors will be performed. Table 3.5-4 exists.
836  3.5.00.08    8. The area radiation monitors listed in    Inspection for the existence of  Each of the monitors listed in Table 3.5-5 are provided.                  the monitors will be performed. Table 3.5-5 exists.
Table 3.5-7 Component Component Name                                      Tag No.                  Location Containment High Range Radiation Monitor                            PXS-RE160                Containment Containment High Range Radiation Monitor                            PXS-RE161                Containment Containment High Range Radiation Monitor                            PXS-RE162                Containment Containment High Range Radiation Monitor                            PXS-RE163                Containment MCR Radiation Monitoring Package A                                  VBS-RY01A              Auxiliary Building MCR Radiation Monitoring Package B                                  VBS-RY01B              Auxiliary Building Containment Atmosphere Radiation Monitor (Gaseous)                    PSS-RE026            Auxiliary Building Containment Atmosphere Radiation Monitor (gaseous,                    PSS-RE027            Auxiliary Building for RCS pressure boundary leakage detection)
Steam Generator Blowdown Radiation Monitor                          BDS-RE010              Turbine Building Steam Generator Blowdown Radiation Monitor                          BDS-RE011              Turbine Building Component Cooling Water Radiation Monitor                            CCS-RE001              Turbine Building Main Steam Line Radiation Monitor                                    SGS-RY026              Auxiliary Building Main Steam Line Radiation Monitor                                    SGS-RY027              Auxiliary Building Service Water Blowdown Radiation Monitor                            SWS-RE008              Turbine Building C-474
 
Table 3.5-7 Component Component Name                                Tag No.      Location Primary Sampling System Liquid Sample Radiation                PSS-RE050 Auxiliary Building Monitor Primary Sampling System Gaseous Sample Radiation              PSS-RE052 Auxiliary Building Monitor Containment Air Filtration Exhaust Radiation Monitor          VFS-RE001  Annex Building Gaseous Radwaste Discharge Radiation Monitor                  WGS-RE017  Auxiliary Building Plant Vent (Normal Range Particulate) Radiation              VFS-RE101  Auxiliary Building Monitor Plant Vent (Normal Range Iodine) Radiation Monitor            VFS-RE102  Auxiliary Building Plant Vent (Normal Range Radiogas) Radiation Monitor          VFS-RE103  Auxiliary Building Plant Vent (Mid Range Radiogas) Radiation Monitor            VFS-RE104A Auxiliary Building Plant Vent (High Range Radiogas) Radiation Monitor            VFS-RE104B Auxiliary Building Turbine Island Vent Radiation Monitor                        TDS-RY001  Turbine Building Liquid Radwaste Discharge Monitor                            WLS-RE229  Radwaste Building Wastewater Discharge Radiation Monitor                        WWS-RE021  Turbine Building Fuel Handling Area Exhaust Radiation Monitor                  VAS-RE001  Auxiliary Building Auxiliary Building Exhaust Radiation Monitor                  VAS-RE002  Auxiliary Building Annex Building Exhaust Radiation Monitor                      VAS-RE003  Auxiliary Building Health Physics and Hot Machine Shop Exhaust                  VHS-RE001  Annex Building Radiation Monitor Radwaste Building Exhaust Radiation Monitor                  VRS-RE023  Radwaste Building Primary Sampling Room                                        RMS-RE008  Auxiliary Building Containment Area - Personnel Hatch - Operating Deck          RMS-RE009  Auxiliary Building Main Control Room                                            RMS-RE010  Auxiliary Building Chemistry Laboratory                                          RMS-RE011  Auxiliary Building Fuel Handling Area 1                                          RMS-RE012  Auxiliary Building Rail Car Bay/Filter Storage Area (Auxiliary Building          RMS-RE013  Auxiliary Building Loading Bay)
Liquid and Gaseous Radwaste Area                              RMS-RY014  Radwaste Building Control Support Area                                          RMS-RE016  Annex Building Radwaste Building Mobile Systems Facility                    RMS-RE017  Radwaste Building C-475
 
Table 3.5-7 Component Component Name                                      Tag No.                Location Hot Machine Shop                                                  RMS-RE018              Annex Building Annex Staging and Storage Area                                    RMS-RE019              Annex Building Fuel Handling Area 2                                              RMS-RE020            Auxiliary Building Containment Area - Personnel Hatch - Maintenance                  RMS-RE021            Auxiliary Building Level 3.6              Reactor Coolant Pressure Boundary Leak Detection Design Description The reactor coolant pressure boundary leakage detection monitoring provides a means of detecting and quantifying the reactor coolant leakage. To detect unidentified leakage inside containment, the following diverse methods are provided to quantify and assist in locating the leakage:
* Containment Sump Level
* Reactor Coolant System Inventory Balance
* Containment Atmosphere Radiation Leakage detection monitoring is accomplished using instrumentation and other components of several systems.
: 1. The diverse leak detection methods provide the nonsafety-related function of detecting small leaks when RCS leakage indicates possible reactor coolant pressure boundary degradation.
Table 3.6-1 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No.                Design Commitment                  Inspections, Tests, Analyses      Acceptance Criteria 837  3.6.00.01.i    1. The diverse leak detection methods      See sections:                  See sections:
provide the nonsafety-related function    i) See ITAAC Table 2.3.10-4,    i) See ITAAC Table 2.3.10-4, of detecting small leaks when RCS          Item 7.a for the sump level    Item 7.a for the sump level leakage indicates possible reactor        measuring instruments WLS-034  measuring instruments coolant pressure boundary degradation. and WLS-035.                    WLS-034 and WLS-035.
838  3.6.00.01.ii  1. The diverse leak detection methods      See sections:                  See ITAAC sections:
provide the nonsafety-related function    ii) See ITAAC Table 3.5-6,      ii) See ITAAC Table 3.5-6, of detecting small leaks when RCS          Item 1 for the containment      Item 1 for the containment leakage indicates possible reactor        atmosphere radioactivity        atmosphere radioactivity coolant pressure boundary degradation. monitor PSS-RE027.              monitor PSS-RE027.
C-476
 
Table 3.6-1 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No.              Design Commitment                  Inspections, Tests, Analyses      Acceptance Criteria 839  3.6.00.01.iii 1. The diverse leak detection methods      See sections:                    See sections:
provide the nonsafety-related function    iii) See ITAAC Table 2.1.2-4,    iii) See ITAAC Table 2.1.2-4, of detecting small leaks when RCS          Items 5a, 7a, and 10 for the    Items 5a, 7a, and 10 for the leakage indicates possible reactor        pressurizer level measuring      pressurizer level measuring coolant pressure boundary degradation. instruments RCS-195A,            instruments RCS-195A, RCS-195B, RCS-195C, and          RCS-195B, RCS-195C, and RCS-195D.                        RCS-195D.
840  3.6.00.01.iv  1. The diverse leak detection methods      See sections:                    See sections:
provide the nonsafety-related function    iv) See ITAAC Table 2.1.2-4,    iv) See ITAAC Table 2.1.2-4, of detecting small leaks when RCS          Items 5a and 7a for the RCS hot  Items 5a and 7a for the RCS leakage indicates possible reactor        and cold leg temperature        hot and cold leg temperature coolant pressure boundary degradation. instruments RCS-121A,            instruments RCS-121A, RCS-121B, RCS-121C,              RCS-121B, RCS-121C, RCS-121D, RCS-122A,              RCS-121D, RCS-122A, RCS-122B, RCS-122C,              RCS-122B, RCS-122C, RCS-122D, RCS-131A,              RCS-122D, RCS-131A, RCS-131B, RCS-131C,              RCS-131B, RCS-131C, RCS-131D, RCS-132A,              RCS-131D, RCS-132A, RCS-132B, RCS-132C, and          RCS-132B, RCS-132C, and RCS-132D.                        RCS-132D.
841  3.6.00.01.v  1. The diverse leak detection methods      See sections:                    See sections:
provide the nonsafety-related function    v) See ITAAC Table 2.1.2-4,      v) See ITAAC Table 2.1.2-4, of detecting small leaks when RCS          Items 5a, 7a, and 10 for the RCS Items 5a, 7a, and 10 for the leakage indicates possible reactor        pressure instruments RCS-140A,  RCS pressure instruments coolant pressure boundary degradation. RCS-140B, RCS-140C, and          RCS-140A, RCS-140B, RCS-140D.                        RCS-140C, and RCS-140D.
842  3.6.00.01.vi  1. The diverse leak detection methods      See sections:                    See sections:
provide the nonsafety-related function    vi) See ITAAC Table 2.3.2-4,    vi) See ITAAC Table 2.3.2-4, of detecting small leaks when RCS          Item 13 for the letdown and      Item 13 for the letdown and leakage indicates possible reactor        makeup flow instruments          makeup flow instruments coolant pressure boundary degradation. CVS-001 and CVS-025.            CVS-001 and CVS-025.
843  3.6.00.01.vii 1. The diverse leak detection methods      vii) See ITAAC Table 2.3.10-4,  vii) See ITAAC provide the nonsafety-related function    Item 10 for the reactor coolant  Table 2.3.10-4, Item 10 for the of detecting small leaks when RCS          drain tank level instrument      reactor coolant drain tank leakage indicates possible reactor        WLS-002.                        level instrument WLS-002.
coolant pressure boundary degradation.
C-477
 
3.7              Design Reliability Assurance Program The Design Reliability Assurance Program (D-RAP) is a program that will be performed during the detailed design and equipment specification phase prior to initial fuel load. The D-RAP evaluates and sets priorities for the structures, systems, and components (SSCs) in the design, based on their degree of risk significance. The risk-significant components are listed in Table 3.7-1.
The objective of the D-RAP program is to provide reasonable assurance that risk-significant SSCs (Table 3.7-1) are designed such that: (1) assumptions from the risk analysis are utilized, (2) SSCs (Table 3.7-1) when challenged, function in accordance with the assumed reliability, (3) SSCs (Table 3.7-1) whose failure results in a reactor trip, function in accordance with the assumed reliability, and (4) maintenance actions to achieve the assumed reliability are identified.
: 1. The D-RAP ensures that the design of SSCs within the scope of the reliability assurance program (Table 3.7-1) is consistent with the risk insights and key assumptions (e.g., SSC design, reliability, and availability).
Table 3.7-1 Risk-Significant Components Equipment Name                                        Tag No.
Component Cooling Water System (CCS)
Component Cooling Water Pumps                                          CCS-MP-01A/B Containment System (CNS)
Containment Vessel                                                      CNS-MV-01 Hydrogen Igniters                                                  VLS-EH-1 through -64 Chemical and Volume Control System (CVS)
Makeup Pumps                                                          CVS-MP-01A/B Makeup Pump Suction and Discharge Check Valves                          CVS-PL-V113 CVS-PL-V160A/B Letdown Discharge Isolation Valves                                      CVS-PL-V045 CVS-PL-V047 Diverse Actuation System (DAS)
DAS Processor Cabinets and Control Panel (used to provide                DAS-JD-001 automatic and manual actuation)                                          DAS-JD-002 DAS-JD-003 DAS-JD-004 OCS-JC-020 Annex Building UPS Distribution Panels                            EDS1-EA-1, EDS1-EA-14, (provide power to DAS)                                            EDS2-EA-1, EDS2-EA-14 Rod Drive MG Sets (Field Breakers)                                    PLS-MG-01A/B C-478
 
Table 3.7-1 Risk-Significant Components Equipment Name                                            Tag No.
Containment Isolation Valves Controlled by DAS                          CVS-PL-V045, -V047 VFS-PL-V003, -V004, -V009, -V010 WLS-PL-V055, -V057 Main ac Power System (ECS)
Reactor Coolant Pump Switchgear                                        ECS-ES-31, -32, -41, -42,
                                                                          -51, -52, -61, -62 Ancillary Diesel Generators                                                ECS-MS-01, -02 6900 Vac Buses                                                              ECS-ES-1, -2 Main and Startup Feedwater System (FWS)
Startup Feedwater Pumps                                                    FWS-MP-03A/B General I&C IRWST Level Sensors                                                  PXS-045, -046, -047, -048 RCS Hot Leg Level Sensors                                                    RCS-160A/B Pressurizer Pressure Sensors                                              RCS-191A/B/C/D Pressurizer Level Sensors                                                  RCS-195A/B/C/D Steam Generator Narrow-Range Level Sensors                            SGS-001, -002, -003, -004,
                                                                        -005, -006, -007, -008 Steam Generator Wide-Range Level Sensors                              SGS-011, -012, -013, -014,
                                                                        -015, -016, -017, -018 Main Steam Line Pressure Sensors                                      SGS-030, -031, -032, -033,
                                                                        -034, -035, -036, -037 Main Feedwater Wide-Range Flow Sensors                                FWS-050B/D/F, -051B/D/F Startup Feedwater Flow Sensors                                          SGS-055A/B, -056A/B CMT Level Sensors                                                PXS-011A/B/C/D, -012A/B/C/D,
                                                                    -013A/B/C/D, -014A/B/C/D Class 1E dc Power and Uninterruptible Power System (IDS) 250 Vdc 24-Hour Batteries                                        IDSA-DB-1A/B, IDSB-DB-1A/B, IDSC-DB-1A/B, IDSD-DB-1A/B 250 Vdc 24-Hour Buses                                                  IDSA-DS-1, IDSB-DS-1 IDSC-DS-1, IDSD-DS-1 250 Vdc 24-Hour Battery Chargers                                      IDSA-DC-1, IDSB-DC-1, IDSC-DC-1, IDSD-DC-1 250 Vdc and 120 Vac Distribution Panels                              IDSA-DD-1, IDSA-EA-1/-2, IDSB-DD-1, IDSB-EA-1/-2/-3, IDSC-DD-1, IDSC-EA-1/-2/-3, IDSD-DD-1, IDSD-EA-1/-2 C-479
 
Table 3.7-1 Risk-Significant Components Equipment Name                                          Tag No.
Fused Transfer Switch Boxes                                        IDSA-DF-1, IDSB-DF-1/-2, IDSC-DF-1/-2, IDSD-DF-1 250 Vdc Motor Control Centers                                        IDSA-DK-1, IDSB-DK-1, IDSC-DK-1, IDSD-DK-1 250 Vdc 24-Hour Inverters                                            IDSA-DU-1, IDSB-DU-1, IDSC-DU-1, IDSD-DU-1 Passive Containment Cooling System (PCS)
Recirculation Pumps                                                      PCS-MP-01A/B PCCWST Drain Isolation Valves                                          PCS-PL-V001A/B/C Plant Control System (PLS)
PLS Actuation Software (used to provide control functions)            Refer to Table 3.7-2 PLS Actuation Hardware (used to provide control                        Refer to Table 3.7-2 functions)
Protection and Monitoring System (PMS)
PMS Actuation Software (used to provide automatic control      Refer to Tables 2.5.2-2 and 2.5.2-3 functions)
PMS Actuation Hardware (used to provide automatic              Refer to Tables 2.5.2-2 and 2.5.2-3 control functions)
MCR 1E Displays and System Level Controls                              OCS-JC-010, -011 Reactor Trip Switchgear                                            PMS-JD-RTS A01/02, B01/02, C01/02, D01/02 Passive Core Cooling System (PXS)
IRWST Vents                                                                PXS-MT-03 IRWST Screens                                                          PXS-MY-Y01A/B/C Containment Recirculation Screens                                      PXS-MY-Y02A/B CMT Discharge Isolation Valves                                    PXS-PL-V014A/B, -V015A/B CMT Discharge Check Valves                                        PXS-PL-V016A/B, -V017A/B Accumulator Discharge Check Valves                                PXS-PL-V028A/B, -V029A/B PRHR HX Control Valves                                                  PXS-PL-V108A/B Containment Recirculation Squib Valves                            PXS-PL-V118A/B, -V120A/B IRWST Injection Check Valves                                      PXS-PL-V122A/B, -V124A/B IRWST Injection Squib Valves                                      PXS-PL-V123A/B, -V125A/B IRWST Gutter Bypass Isolation Valves                                    PXS-PL-V130A/B C-480
 
Table 3.7-1 Risk-Significant Components Equipment Name                                              Tag No.
Reactor Coolant System (RCS)
ADS Stage 1/2/3 Valves (MOVs)                                        RCS-PL-V001A/B, -V011A/B RCS-PL-V002A/B, -V012A/B RCS-PL-V003A/B, -V013A/B ADS Stage 4 Valves (Squibs)                                              RCS-PL-V004A/B/C/D Pressurizer Safety Valves                                                  RCS-PL-V005A/B Reactor Vessel Insulation Water Inlet and Steam Vent                          RCS-MN-01 Devices Reactor Cavity Doorway Damper                                                        -
Fuel Assemblies                                              157 assemblies with tag numbers beginning with RXS-FA Normal Residual Heat Removal System (RNS)
Residual Heat Removal Pumps                                                  RNS-MP-01A/B RNS Motor-Operated Valves                                          RNS-PL-V011, -V022, -V023, -V055 RNS Stop Check Valves                                                      RNS-PL-V015A/B RNS Check Valves                                                            RNS-PL-V017A/B RNS Check Valves                                                    RNS-PL-V007A/B, -V013, -V056 Spent Fuel Cooling System (SFS)
Spent Fuel Cooling Pumps                                                      SFS-MP-01A/B Steam Generator System (SGS)
Main Steam Safety Valves                                              SGS-PL-V030A/B, -V031A/B,
                                                                          -V032A/B, -V033A/B,
                                                                          -V034A/B, -V035A/B Main Steam Line Isolation Valves                                            SGS-PL-V040A/B Main Feedwater Isolation Valves                                            SGS-PL-V057A/B Service Water System (SWS)
Service Water Cooling Tower Fans                                            SWS-MA-01A/B Service Water Pumps                                                          SWS-MP-01A/B Nuclear Island Nonradioactive Ventilation System (VBS)
MCR Ancillary Fans                                                          VBS-MA-10A/B I&C Room B/C Ancillary Fans                                                  VBS-MA-11, -12 C-481
 
Table 3.7-1 Risk-Significant Components Equipment Name                                        Tag No.
Containment Air Filtration System (VFS)
Containment Purge Isolation Valves                                      VFS-PL-V003 VFS-PL-V004 VFS-PL-V009 VFS-PL-V010 Chilled Water System (VWS)
Air Cooled Chiller Pumps                                                VWS-MP-02, -03 Air Cooled Chillers                                                    VWS-MS-02, -03 Liquid Radwaste System (WLS)
Sump Containment Isolation Valves                                        WLS-PL-V055 WLS-PL-V057 Onsite Standby Power System (ZOS)
Engine Room Exhaust Fans                                            VZS-MY-V01A/B, -V02A/B Onsite Diesel Generators                                                ZOS-MS-05A/B Note: Dash (-) indicates not applicable.
C-482
 
Table 3.7-2 PLS D-RAP Control Functions CVS Reactor Makeup RNS Reactor Injection from cask loading pit Startup Feedwater from CST Spent Fuel Cooling Component Cooling of RNS and SFS Heat Exchangers Service Water Cooling of CCS Heat Exchangers Onsite Diesel Generators Hydrogen Ignitors C-483
 
Table 3.7-3 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No.            Design Commitment                    Inspections, Tests, Analyses      Acceptance Criteria 844  3.7.00.01 1. The D-RAP ensures that the design          An analysis will confirm that An analysis report documents of SSCs within the scope of the              the design of RAP SSCs        that safety-related SSCs reliability assurance program                identified in Table 3.7-1 has  identified in Table 3.7-1 have (Table 3.7-1) is consistent with the risk    been completed in accordance  been designed in accordance insights and key assumptions (e.g., SSC      with applicable D-RAP          with a 10 CFR 50 Appendix B design, reliability, and availability).      activities.                    quality program.
An analysis report documents that non-safety-related SSCs identified in Table 3.7-1 have been designed in accordance with a program that satisfies quality assurance requirements for SSCs important to investment protection.
C-484
 
C.3.8          Emergency Planning ITAAC C.3.8.1.1      Emergency Classification System Table C.3.8-1 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No.          Program Commitment                Inspections, Tests, Analyses            Acceptance Criteria 845  C.3.8.01.01.01 1.1 A standard emergency              1.1.1 An inspection of the main    1.1.1 The specified parameters classification and emergency          control room, Technical Support    are retrievable in the main action level (EAL) scheme exists,      Center (TSC), and Emergency        control room, TSC and EOF, and identifies facility system and    Operations Facility (EOF) will      and the ranges of the displays effluent parameters constituting      be performed to verify that they    encompass the values specified the bases for the classification      have displays for retrieving        in the Emergency Classification scheme. [D.1**]                        facility system and effluent        and EAL technical basis
[**D.1 corresponds to NUREG-          parameters as specified in the      document for the unit.
0654/ FEMA-REP-1 evaluation            Emergency Classification and criteria.]                            EAL technical basis document for the unit, and the displays are functional.
846  C.3.8.01.01.02 1.1 A standard emergency              1.1.2 An analysis of the EAL        1.1.2 The ranges available in classification and emergency          technical bases will be            the main control room, TSC, action level (EAL) scheme exists,      performed to verify as-built, site- and EOF envelop the values for and identifies facility system and    specific implementation of the      the specific parameters effluent parameters constituting      EAL scheme.                        identified in the EALs in the bases for the classification                                          Emergency Plan, Annex 2 and scheme. [D.1**]                                                            3, Attachment 1.
[**D.1 corresponds to NUREG-0654/ FEMA-REP-1 evaluation criteria.]
C-485
 
C.3.8.1.2      Notification Methods and Procedures Table C.3.8-1 (continued)
Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No.          Program Commitment                Inspections, Tests, Analyses          Acceptance Criteria 847  C.3.8.01.02.01 2.1 The means exist to notify          2.1 A test will be performed to  2.1 The State of Florida and the responsible State and local            demonstrate the capabilities for  counties of Miami-Dade, and organizations within 15 minutes        providing initial notification to Monroe received notification after the licensee declares an        the offsite authorities after a  within 15 minutes after the emergency. [E.1]                      simulated emergency              declaration of an emergency in classification.                  the main control room and the EOF.
848  C.3.8.01.02.02 2.2 The means exist to notify          2.2 A test of the primary and    2.2 A test of the primary and emergency response personnel.          backup emergency response        backup ERO notification
[E.2]                                  organization (ERO) notification  systems results in:
systems will be performed.
* ERO personnel received the notification message;
* Mobilization communication was validated by personnel response to the notification system or by telephone
* Response to electronic notification and plant page system was demonstrated during normal working hours, and off hours.
849  C.3.8.01.02.03 2.3 The means exists to notify and    2.3 A full test of the alert and  2.3 Notification and clear provide instructions to the            notification system and          instructions to the public are populace within the plume              emergency alert system            accomplished in accordance exposure emergency planning            capabilities will be conducted. with the emergency plan zone (EPZ). [E.6]                                                        requirements.
C-486
 
C.3.8.1.3        Emergency Communications Table C.3.8-1 (continued)
Inspections, Tests, Analyses, and Acceptance Criteria No.      ITAAC No.            Program Commitment              Inspections, Tests, Analyses        Acceptance Criteria 850      C.3.8.01.03.01    3.1 The means exists for          3.1 A test will be performed    3.1 Communications (both communications between the        of the capabilities. The test    primary and secondary main control room, TSC, EOF,      for the contact with the        methods/systems) are principal State and local          principal EOCs and the field    established among the main emergency operations centers      monitoring teams will be from    control room and the EOF (EOCs), and field monitoring      the main control room and the    with the State of Florida teams. [F.1.d]                    EOF. The TSC                    Division of Emergency communication with the main      Management warning point control room and the EOF        and EOC, Miami-Dade will be performed.              County warning point and EOC, and Monroe County warning point and EOC.
Communications are established between the main control room and the EOF with the Turkey Point Nuclear Plant (PTN) field monitoring teams.
851      C.3.8.01.03.02    3.2 The means exists for          3.2 A test is performed of the  3.2 Communications are communications from the main      capabilities to communicate      established from the main control room, TSC and EOF to      using the emergency              control room, TSC and EOF the Nuclear Regulatory            notification system from the    to the NRC headquarters and Commission (NRC)                  main control room, TSC and      regional office EOCs using headquarters and regional          EOF to the NRC headquarters      the emergency notification office EOCs (including            and regional office EOCs.        system. The TSC and EOF establishment of the              The health physics network is    demonstrated emergency response data            tested to ensure                communications with the system (ERDS) or its successor    communications between the      NRC operations center using system between the onsite          TSC and EOF with the NRC        the health physics network.
computer system and the NRC        operations center. The ERDS      The access port for ERDS, or operations center). [F.1.f]        is established, or its successor its successor system, is system, between the onsite      provided and successfully computer systems and the        completes a transfer of data NRC operations center.          from the unit to the NRC operations center.
C-487
 
C.3.8.1.4      Public Education and Information Table C.3.8-1 (continued)
Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No.            Program Commitment                Inspections, Tests, Analyses        Acceptance Criteria 852  C.3.8.01.04.01    4.1 The licensee has provided        4.1 An inspection of the          4.1 The ENC includes space that may be used for a        facility/area provided for the    equipment to support the ENC limited number of news media.        news media will be performed      operations, including
[G.3.b]                              in the emergency news center      communications with the EOF (ENC). The space provides        and State and county EOCs.
adequate equipment to support    Designated space is available the ENC operation, including      for news media briefings.
communications with the site and with the EOCs in the State and counties as well as a limited number of news media.
C.3.8.1.5      Emergency Facilities and Equipment Table C.3.8-1 (continued)
Inspections, Tests, Analyses, and Acceptance Criteria No.      ITAAC No.              Program Commitment              Inspections, Tests, Analyses      Acceptance Criteria 853    C.3.8.01.05.01.01    5.1 The licensee has                5.1 An inspection of the TSC  5.1.1 The TSC has at least established a TSC and onsite        and OSC will be performed,    3,000 square feet of floor operations support center          including a test of their      space consistent with (OSC). [H.1]                        capabilities.                  NUREG-0696 (75 square feet/person) and is large enough for required systems, equipment, records and storage.
854    C.3.8.01.05.01.02    5.1 The licensee has                5.1 An inspection of the TSC  5.1.2 The TSC is located established a TSC and onsite        and OSC will be performed,    outside the Protected Area, operations support center          including a test of their      and procedures are in place to (OSC). [H.1]                        capabilities.                  enhance passage through security checkpoints expeditiously.
855    C.3.8.01.05.01.03    5.1 The licensee has                5.1 An inspection of the TSC  5.1.3 Communications established a TSC and onsite        and OSC will be performed,    equipment is installed and operations support center          including a test of their      voice transmission and (OSC). [H.1]                        capabilities.                  reception are accomplished between the main control room, the OSC, and EOF.
C-488
 
Table C.3.8-1 (continued)
Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No.          Program Commitment              Inspections, Tests, Analyses      Acceptance Criteria 856  C.3.8.01.05.01.04 5.1 The licensee has              5.1 An inspection of the TSC  5.1.4 The TSC ventilation established a TSC and onsite      and OSC will be performed,    system includes a high-operations support center          including a test of their    efficiency particulate air (OSC). [H.1]                      capabilities.                (HEPA), and charcoal filter and radiation monitors are installed. Controls and displays exist in the TSC to control and monitor the status of the TSC ventilation system including heating and cooling, and the activation of the HEPA and charcoal filter system upon detection of high radiation in the TSC.
857  C.3.8.01.05.01.05 5.1 The licensee has              5.1 An inspection of the TSC  5.1.5 The TSC has the means established a TSC and onsite      and OSC will be performed,    to receive, store, process, and operations support center          including a test of their    display plant and (OSC). [H.1]                      capabilities.                environmental information, as listed in design control document (DCD) Table 7.5-1 and Final Safety Analysis Report (FSAR) Table 7.5-201, and to initiate emergency measures and conduct emergency assessment.
858  C.3.8.01.05.01.06 5.1 The licensee has              5.1 An inspection of the TSC  5.1.6 A reliable and backup established a TSC and onsite      and OSC will be performed,    electrical power supply is operations support center          including a test of their    available for the TSC.
(OSC). [H.1]                      capabilities.
859  C.3.8.01.05.01.07 5.1 The licensee has              5.1 An inspection of the TSC  5.1.7 There is an OSC located established a TSC and onsite      and OSC will be performed,    inside the Protected Area. It operations support center          including a test of their    is separate from the main (OSC). [H.1]                      capabilities.                control room.
860  C.3.8.01.05.01.08 5.1 The licensee has              5.1 An inspection of the TSC  5.1.8 Communications established a TSC and onsite      and OSC will be performed,    equipment is installed, and operations support center          including a test of their    voice transmission and (OSC). [H.1]                      capabilities.                reception are accomplished between the OSC and OSC teams, the TSC and the main control room.
C-489
 
Table C.3.8-1 (continued)
Inspections, Tests, Analyses, and Acceptance Criteria No.      ITAAC No.              Program Commitment            Inspections, Tests, Analyses        Acceptance Criteria 861    C.3.8.01.05.02.01      5.2 The licensee has              5.2 An inspection of the EOF  5.2.1 The EOF working space established an EOF. [H.2]          will be performed, including  is a minimum of 5625 square a test of the capabilities. feet consistent with NUREG-0696 (75 square feet/person) and is large enough for required systems, equipment, records, and storage.
862    C.3.8.01.05.02.02      5.2 The licensee has              5.2 An inspection of the EOF  5.2.2 Communications established an EOF. [H.2]          will be performed, including  equipment is installed, and a test of the capabilities. voice transmission and reception are accomplished between the main control room, TSC, EOF, field monitoring teams, NRC, State and county agencies, and ENC.
863    C.3.8.01.05.02.03      5.2 The licensee has              5.2 An inspection of the EOF  5.2.3 Radiological data established an EOF. [H.2]          will be performed, including  identified in each Plan Annex, a test of the capabilities. meteorological data, and plant system data pertinent to determining offsite protective measures as listed in DCD Table 7.5-1 and FSAR Table 7.5-201 are available and displayed in the EOF, when activated.
C.3.8.1.6        Accident Assessment Table C.3.8-1 (continued)
Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No.              Program Commitment              Inspections, Tests, Analyses        Acceptance Criteria 864    C.3.8.01.06.01    6.1 The means exist to provide      6.1 A test will be performed to 6.1 The means are available to initial and continuing              demonstrate that the means        provide initial and radiological assessment              exist to provide initial and      continuing radiological throughout the course of an          continuing radiological            assessment through displays accident. [I.2]                      assessment throughout the          of instrumentation indicators course of an accident through      in the main control room, the plant computer or              TSC and EOF during the communications with the main      course of drills and/or control room, TSC, and EOF        exercises.
during the course of drills and/or exercises.
C-490
 
Table C.3.8-1 (continued)
Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No.          Program Commitment                Inspections, Tests, Analyses        Acceptance Criteria 865  C.3.8.01.06.02 6.2 The means exist to              6.2 A test will be performed to  6.2 Emergency plan determine the source term of        demonstrate that the means        implementing procedures releases of radioactive material    exist to determine the source    (EPIPs), through use in within plant systems, and the        term of releases of radioactive  training and drills, provide magnitude of the release of          material within plant systems,    direction to accurately radioactive materials based on      and the magnitude of the          calculate the source terms and plant system parameters and          release of radioactive materials  the magnitude of the release of effluent monitors. [I.3]            based on plant system            postulated accident scenario parameters and effluent          releases.
monitors.
866  C.3.8.01.06.03 6.3 The means exist to              6.3 A test will be performed to  6.3 Demonstrate that the continuously assess the impact      provide evidence that the        means exist to continuously of the release of radioactive        impact of a radiological release  assess the impact of the release materials to the environment,        to the environment is able to be  of radioactive materials to the accounting for the relationship      assessed by using the            environment, accounting for between effluent monitor            relationship between effluent    the relationship between readings, and onsite and offsite    monitor readings, and onsite      effluent monitor readings, and exposures and contamination for      and offsite exposures and        onsite and offsite exposures various meteorological              contamination for various        and contamination for various conditions. [I.4]                    meteorological conditions.        meteorological conditions under drill conditions.
867  C.3.8.01.06.04 6.4 The means exist to acquire      6.4 A test will be performed to  6.4 Meteorological data exists and evaluate meteorological          acquire and evaluate              at the EOF, TSC, main control information. [I.5]                  meteorological data/              room, offsite NRC operations information.                      center, and the State of Florida, and that this data is in the format needed for the appropriate EPIPs.
868  C.3.8.01.06.05 6.5 The means exist to              6.5 A test will be performed of  6.5 The release rate and determine the release rate and      the capabilities to determine the projected doses can be projected doses if the              release rate and projected doses  determined with off-scale or instrumentation used for            if the instrumentation used for  inoperable instrumentation assessment is off-scale or          assessment is off-scale or        during training or a drill.
inoperable. [I.6]                    inoperable.
869  C.3.8.01.06.06 6.6 The means exist for field        6.6 A test will be performed of  6.6 The field monitoring teams monitoring within the plume          the capabilities for field        were dispatched and exposure EPZ. [I.7]                  monitoring within the plume      demonstrated ability to locate exposure EPZ.                    and monitor a radiological release within the plume exposure EPZ.
870  C.3.8.01.06.07 6.7 The means exist to make          6.7 A test will be performed of  6.7 The field monitoring teams rapid assessments of actual or      the capabilities to make rapid    were activated. They potential magnitude and              assessments of actual or          demonstrate an ability to make locations of radiological hazards    potential magnitude and          rapid assessment of actual or C-491
 
Table C.3.8-1 (continued)
Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No.          Program Commitment              Inspections, Tests, Analyses        Acceptance Criteria through liquid or gaseous release    locations of radiological        potential magnitude and pathways, including activation,      hazards through liquid or        locations of any radiological notification means, field team      gaseous release pathways,        hazards through simulated composition, transportation,        including activation,            liquid or gaseous release communication, monitoring            notification means, field team  pathways. A qualified field equipment, and estimated            composition, transportation,    monitoring team was notified, deployment times. [I.8]              communication, monitoring        activated, briefed, and equipment, and estimated        dispatched from the EOF deployment times.                during a radiological release scenario. The team demonstrated the procedural guidance in team composition, use of monitoring equipment, communication from the field, and locating specific sampling locations.
871  C.3.8.01.06.08 6.8 The capability exists to        6.8 A test will be performed of  6.8 A field monitoring team detect and measure radioiodine      the capabilities to detect and  was dispatched during a concentrations in air in the        measure radioiodine              radiological release scenario plume exposure EPZ, as low as        concentrations in air in the    and demonstrated the use of 10-7 &#xb5;Ci/cc (microcuries per        plume exposure EPZ, as low as    sampling and detection cubic centimeter) under field        10-7 &#xb5;Ci/cc under field          equipment for air conditions. [I.9]                    conditions.                      concentrations in the plume exposure EPZ, as low as 10-7
                                                                                          &#xb5;Ci/cc.
872  C.3.8.01.06.09 6.9 The means exist to estimate      6.9 A test will be performed of  6.9 The means are available to integrated dose from the            the capabilities to estimate    estimate integrated dose from projected and actual dose rates,    integrated dose from the        the dose assessment program and for comparing these              projected and actual dose rates, and the field monitoring team estimates with the                  and for comparing these          reading during a radioactive Environmental Protection            estimates with the EPA          release scenario. The results Agency (EPA) protective action      protective action guides.        were compared with the EPA guides. [I.10]                                                        protective action guides.
C-492
 
C.3.8.1.7      Protective Response Table C.3.8-1 (continued)
Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No.            Program Commitment                  Inspections, Tests, Analyses      Acceptance Criteria 873  C.3.8.01.07.01 7.1 The means exist to warn and          7.1 A test will be performed of 7.1 Means exist to advise onsite individuals of an          the capabilities to warn and    successfully warn and advise emergency, including those in areas      advise onsite individuals of an onsite individuals including:
controlled by the operator, including:    emergency, including those in
[J.1]                                    the Owner-Controlled Area, and
* nonessential employees the immediate vicinity.
* employees not having emergency
* visitors assignments
* contractor and construction
* visitors                                                                  personnel
* contractor and construction personnel
* other personnel within the Owner-Controlled Area, and
* other persons who may be in the                                          the immediate vicinity.
public access areas, on or passing through the site, or within the Owner-Controlled Area.
C-493
 
C.3.8.1.8      Exercises and Drills Table C.3.8-1 (continued)
Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No.              Program Commitment                  Inspections, Tests, Analyses          Acceptance Criteria 874  C.3.8.01.08.01. 8.1 Licensee conducts a full              8.1 A full participation exercise 8.1.1 The exercise is 01        participation exercise to evaluate        (test) will be conducted within  completed within the specified major portions of emergency response      the specified time periods of    time periods of 10 CFR Part capabilities, which includes              Appendix E to 10 CFR Part 50.
50, Appendix E; onsite participation by the State and local agency within the plume exposure                                            exercise objectives listed EPZ, and the State within the                                              below have been met, and ingestion control EPZ. [N.1]                                                there are no uncorrected onsite exercise deficiencies.
A. Accident Assessment and Classification
: 1. Demonstrate the ability to identify initiating conditions, determine emergency action level (EAL) parameters, and correctly classify the emergency throughout the exercise.
Standard Criteria:
: a. Determine the correct highest emergency classification level based on events which were in progress, considering past events and their impact on the current conditions, within 15 minutes from the time the initiating condition(s) or EAL is identified.
B. Notifications
: 1. Demonstrate the ability to alert, notify and mobilize site emergency response personnel.
Standard Criteria:
: a. Complete the designated checklist and perform the C-494
 
Table C.3.8-1 (continued)
Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No. Program Commitment                Inspections, Tests, Analyses      Acceptance Criteria announcement concerning the initial event classification of Alert or higher.
: b. Activate the emergency recall system within 5 minutes of the initial event classification for an Alert or higher.
: 2. Demonstrate the ability to notify responsible State and local government agencies within 15 minutes and the NRC within 60 minutes after declaring an emergency.
Standard Criteria:
: a. Transmit information using the designated checklist in accordance with approved EPIPs within 15 minutes of event classification.
: b. Transmit information using the designated checklist in accordance with approved EPIPs within 60 minutes of last transmittal for a follow-up notification to State and local authorities.
: c. Transmit information using designated checklist within 60 minutes of event classification for an initial notification of the NRC.
: 3. Demonstrate the ability to warn or advise onsite individuals of emergency conditions.
Standard Criteria:
: a. Initiate notification of onsite individuals (via plant C-495
 
Table C.3.8-1 (continued)
Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No. Program Commitment                Inspections, Tests, Analyses      Acceptance Criteria page or telephone) using designated checklist.
: 4. Demonstrate the capability of the Alert and Notification System (ANS) for the public, to operate properly when required.
Standard Criteria:
: a. 94 percent of the sirens operate properly as indicated by the siren feedback system.
C. Emergency Response
: 1. Demonstrate the capability to direct and control emergency operations.
Standard Criteria:
: a. Command and control is demonstrated by the main control room in the early phase of the emergency and by the TSC within 60 minutes from notification of an Alert or higher event classification with at least minimum staffing.
: 2. Demonstrate the ability to transfer emergency direction from the main control room (simulator) to the TSC.
Standard Criteria:
: a. Evaluation of briefings that were conducted prior to turnover responsibility.
Personnel document transfer of duties.
: 3. Demonstrate the ability to prepare for 24-hour staffing requirements.
C-496
 
Table C.3.8-1 (continued)
Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No. Program Commitment                Inspections, Tests, Analyses      Acceptance Criteria Standard Criteria:
: a. Complete 24-hour staff assignments.
: 4. Demonstrate the ability to perform assembly and accountability for all personnel in the Protected Area within 30 minutes of an emergency requiring Protected Area assembly and accountability.
Standard Criteria:
: a. Protected Area personnel assembly and accountability completed within 30 minutes of an emergency requiring Protected Area assembly and accountability.
D. Emergency Response Facilities
: 1. Demonstrate activation of the OSC and the TSC and EOF within 60 minutes of event classification with at least minimum staffing.
Standard Criteria:
: a. The TSC and OSC are activated within 60 minutes from notification of an Alert or higher event classification with at least minimum staffing.
: b. The EOF is activated within 60 minutes from notification of a Site Area Emergency or higher event classification with at least minimum staffing.
: 2. Demonstrate the adequacy of equipment, security C-497
 
Table C.3.8-1 (continued)
Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No. Program Commitment                Inspections, Tests, Analyses      Acceptance Criteria provisions, and habitability precautions for the TSC, OSC, EOF and ENC, as appropriate.
Standard Criteria:
: a. Evaluation of the adequacy of the emergency equipment in the emergency response facilities including availability and general consistency with the EPIPs.
: b. The security manager implements and follows applicable EPIPs.
: c. The radiation protection manager (TSC) implements the designated checklist if an onsite/offsite release has occurred.
: d. Demonstrate the capability of TSC and EOF equipment and data displays to clearly identify and reflect the affected unit.
: 3. Demonstrate the adequacy of communications for all emergency support resources.
Standard Criteria:
: a. Emergency response communications listed in the EPIPs are available and operational.
: b. Communications systems are tested in accordance with the TSC, OSC, EOF and ENC activation checklists.
: c. Emergency response facility personnel are able to operate all specified communications systems.
C-498
 
Table C.3.8-1 (continued)
Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No. Program Commitment                Inspections, Tests, Analyses      Acceptance Criteria
: d. Clear primary and backup communications links are established and maintained for the duration of the exercise.
E. Radiological Assessment and Control
: 1. Demonstrate the ability to obtain onsite radiological surveys and samples.
Standard Criteria:
: a. Radiation Protection Technicians demonstrate the ability to obtain appropriate instruments (range and type) and perform surveys.
: b. Airborne samples are taken when the conditions indicate the need for the information.
: 2. Demonstrate the ability to continuously monitor and control radiation exposure to emergency workers.
Standard Criteria:
: a. Emergency workers are issued self-reading dosimeters when radiation levels require, and exposures are controlled to 10 CFR Part 20 limits (unless the emergency coordinator authorizes emergency limits for onsite ERO personnel and the emergency offsite manager authorizes emergency exposures for offsite ERO personnel).
: b. Exposure records are available either from the Site database or a hard copy dose report.
C-499
 
Table C.3.8-1 (continued)
Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No. Program Commitment                Inspections, Tests, Analyses      Acceptance Criteria
: c. Emergency workers include Security and personnel within all emergency facilities.
: 3. Demonstrate the ability to assemble and dispatch field monitoring teams within 60 minutes from the decision to do so.
Standard Criteria:
: a. One field monitoring team is ready to be deployed within 60 minutes of being requested and no later than 90 minutes from the declaration of an Alert or higher.
: 4. Demonstrate the ability to satisfactorily collect and disseminate field team data.
Standard Criteria:
: a. Field team data to be collected is dose rate or counts per minute (cpm) from the plume, both open and closed window, and air sample (gross/net cpm) for particulate and iodine, if applicable.
: b. Radiological data is satisfactorily disseminated from the field team to the dose assessment coordinator.
: 5. Demonstrate the ability to develop dose projections.
Standard Criteria:
: a. The on-shift Chemistry Technician performs timely and accurate dose projections, in accordance with the EPIPs.
: 6. Demonstrate the ability to develop appropriate Protective C-500
 
Table C.3.8-1 (continued)
Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No.              Program Commitment                  Inspections, Tests, Analyses          Acceptance Criteria Action Recommendations (PARs), and notify appropriate authorities within 15 minutes of a General Emergency declaration or changes in parameters that affect the previously issued PARs.
Standard Criteria:
: a. Total Effective Dose Equivalent (TEDE) and Committed Dose Equivalent (CDE) dose projections from the dose assessment computer code or a backup method are established in accordance with the EPIPs.
: b. PARs are developed within 15 minutes of data availability.
: c. PARs are transmitted via voice, fax, or electronically within 15 minutes as required by the EPIPs.
875  C.3.8.01.08.01. 8.1 Licensee conducts a full              8.1 A full participation exercise 8.1.2 Onsite emergency 02        participation exercise to evaluate        (test) will be conducted within  response personnel were major portions of emergency response      the specified time periods of    mobilized in sufficient capabilities, which includes              Appendix E to 10 CFR Part 50. numbers to fill emergency participation by the State and local                                        response positions identified agency within the plume exposure                                            in the Radiological EPZ, and the State within the                                              Emergency Plan, Part 2, ingestion control EPZ. [N.1]                                                Section B, Emergency Response Organization, and they successfully performed their assigned responsibilities.
C-501
 
Table C.3.8-1 (continued)
Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No.              Program Commitment                  Inspections, Tests, Analyses          Acceptance Criteria 876  C.3.8.01.08.01. 8.1 Licensee conducts a full              8.1 A full participation exercise  8.1.3 The exercise was 03        participation exercise to evaluate        (test) will be conducted within    completed within the specified major portions of emergency response      the specified time periods of      time periods of Appendix E to capabilities, which includes              Appendix E to 10 CFR Part 50.      10 CFR Part 50, offsite participation by the State and local                                          exercise objectives were met, agency within the plume exposure                                              and there were no uncorrected EPZ, and the State within the                                                offsite exercise deficiencies, ingestion control EPZ. [N.1]                                                  or a license condition requires offsite deficiencies to be corrected prior to operation above 5 percent of rated power.
C.3.8.1.9        Implementing Procedures Table C.3.8-1 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No.              Program Commitment              Inspections, Tests, Analyses          Acceptance Criteria 877    C.3.8.01.09.01    9.1 The licensee has submitted      9.1 Confirm that the submittal    9.1 The date of the submittal detailed implementing procedures    letter was submitted on time.      letter from the licensee for its emergency plan no less                                          demonstrates that the detailed than 180 days prior to fuel load.                                      EPIPs for the onsite emergency plan were submitted no less than 180 days prior to fuel load.
C-502
 
C.3.8.2      Pipe Rupture Hazard Analysis Table C.3.8-2 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No.            Program Commitment                    Inspections, Tests, Analyses      Acceptance Criteria 878  C.3.8.02.01 1. Systems, structures, and components      Inspection of the as-designed    An as-designed pipe rupture (SSCs), that are required to be            pipe rupture hazard analysis    hazard analysis report exists functional during and following a          report will be conducted. The    and concludes that the design basis event shall be protected      report documents the analyses to analysis performed for high against or qualified to withstand the      determine where protection      and moderate energy piping dynamic and environmental effects          features are necessary to        confirms the protection of associated with analyses of postulated      mitigate the consequence of a    systems, structures, and failures in high and moderate energy        pipe break. Pipe break events    components required to be piping.                                    involving high-energy fluid      functional during and systems are analyzed for the    following a design basis effects of pipe whip, jet        event.
impingement, flooding, room pressurization, and temperature effects. Pipe break events involving moderate-energy fluid systems are analyzed for wetting from spray, flooding, and other environmental effects, as appropriate.
C-503
 
C.3.8.3      Piping Design Table C.3.8-3 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No.          Program Commitment                    Inspections, Tests, Analyses      Acceptance Criteria 879  C.3.8.03.01 1. The ASME Code Section III piping        Inspection of ASME Code        ASME Code Design Report(s) is designed in accordance with ASME        Design Reports (NCA- 3550)      (NCA-3550) (certified, when Code Section III requirements.            and required documents will be  required by ASME Code) conducted for the set of lines  exist and conclude that the chosen to demonstrate          design of the piping for lines compliance.                    chosen to demonstrate all aspects of the piping design complies with the requirements of ASME Code Section III.
C-504
 
C.3.8.4        Waterproof Membrane Table C.3.8-4 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No.              Design Commitment                      Inspections, Tests, Analyses          Acceptance Criteria 880  C.3.8.04.01  1. The friction coefficient to resist        Testing will be performed to      A report exists and documents sliding is  0.55.                            confirm that the mudmat-          that the as-built waterproof waterproofing-mudmat interface    system (mudmat-beneath the Nuclear Island        waterproofing-mudmat basemat has a coefficient of      interface) has a coefficient of friction to resist sliding        friction of  0.55 as of  0.55.                        demonstrated through material qualification testing.
C.3.8.5        Concrete Fill Table C.3.8-5 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No.              Design Commitment                      Inspections, Tests, Analyses          Acceptance Criteria 881  C.3.8.05.01  1. First lift of concrete fill placed under  Delivery tickets will be prepared  The first lift of concrete fill the nuclear island basemat, containment      according to ACI 311.5 and        (minimum thickness of 2.5 building, shield building, and auxiliary      inspected to ensure that the first feet) meets durability building meets durability requirements        lift of concrete fill (minimum    requirements of ACI 201.2R-of ACI 201.2R-08, Table 6.3 for Class        thickness of 2.5 feet) meets      08, Table 6.3 for Class 2 2 sulfate exposure.                          durability requirements of ACI    sulfate exposure.
201.2R-08, Table 6.3 for Class 2 sulfate exposure.
882  C.3.8.05.02a 2. Concrete fill placed under the            (a) Testing will be performed in  (a) The mean 28-day nuclear island basemat, containment          accordance with ACI 311.5 to      compressive strength of the building, shield building, and auxiliary      determine the mean compressive    concrete fill is equal to or building is designed, constructed, and        strength of the concrete fill. greater than 1500 psi.
tested as specified in ACI 207.1R-05.
883  C.3.8.05.02b 2. Concrete fill placed under the            (b) Inspection will be performed  (b) Methods used to control nuclear island basemat, containment          to ensure that methods used to    thermal cracking are in building, shield building, and auxiliary      control thermal cracking are in    accordance with ACI 207.1R-building is designed, constructed, and        accordance with ACI 207.1R-05. 05.
tested as specified in ACI 207.1R-05.
C-505
 
C.3.8.6        Seismic Category I Structure Foundation Grouting (i)
Table C.3.8-6 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No.                Design Commitment                    Inspections, Tests, Analyses          Acceptance Criteria 884  C.3.8.06.01.i 1. Inside the region defined by the          i) Testing and analysis will be    i) The grout closure criteria, diaphragm walls, drilling and pressure      performed through a grout test      when used in conjunction with grouting is performed. The grout            program to define grout closure    the specified borehole closure criteria, when used in              criteria for both the Grouted      spacing, will ensure that any conjunction with the specified grout        Zone and Extended Grouted          voids remaining in the borehole spacing:                            Zone, as follows:                  Grouted Zone are structurally insignificant and ensure that
* Will result in any remaining voids
* For both the Grouted Zone and any voids remaining in the between El. -35 +/- 2 feet and El. -60        Extended Grouted Zone, the Extended Grouted Zone are
                      +/- 2 feet (the Grouted Zone) being            grout test program will equal to or less than 20 feet.
structurally insignificant, which is        identify and define grout accomplished through drilling and            closure criteria for grout pressure grouting of primary and            consistency to ensure the grout secondary grout boreholes, and, if          flows into and fills potential necessary, as indicated by site data,        voids in the vicinity of each tertiary and quaternary grout                grout borehole, and boreholes; and
* For the Grouted Zone, the
* Will result in any remaining voids            grout test program will between El. -60 +/- 2 feet and El. -110        identify and define grout
                      +/- 2 feet (the Extended Grouted Zone)        closure criteria for identifying having a maximum equivalent                  when each grout borehole has spherical diameter of equal to or less      been filled and pressurized than 20 feet, which is accomplished          with grout and filling may through drilling and pressure                cease or tertiary or quaternary grouting of primary grout boreholes          grout boreholes are necessary, and, if necessary, as indicated by site      and data, secondary grout boreholes.
* For the Extended Grouted Zone, the grout test program will identify and define grout closure criteria for identifying when each grout borehole has been filled and pressurized with grout and filling may cease or secondary grout boreholes are necessary.
C-506
 
Table C.3.8-6 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No.                  Design Commitment                    Inspections, Tests, Analyses        Acceptance Criteria 885  C.3.8.06.01.ii  1. Inside the region defined by the          ii) Inspections and analysis will ii) Grout closure criteria as diaphragm walls, drilling and pressure      be performed of the as-built      established in the grout test grouting is performed. The grout            locations, depth and spacing of  program are met inside the closure criteria, when used in              all grout boreholes, both with    region defined by the conjunction with the specified grout        respect to the Grouted Zone and  diaphragm walls and the grout borehole spacing:                            the Extended Grouted Zone, and    boreholes meet the following the grout data associated with    requirements:
* Will result in any remaining voids each grout borehole and zone.
between El. -35 +/- 2 feet and El. -60 +/- 2
* For the Grouted and feet (the Grouted Zone) being                                                  Extended Grouted Zones, structurally insignificant, which is                                          primary grout boreholes are accomplished through drilling and                                              drilled throughout the entire pressure grouting of primary and                                              interior region defined by the secondary grout boreholes, and, if                                            diaphragm walls and with necessary, as indicated by site data,                                          spacing of less than or equal tertiary and quaternary grout boreholes;                                      to 20 feet on center at the and                                                                            ground surface,
* Will result in any remaining voids
* For the Grouted Zone, between El. -60 +/- 2 feet and El. -110 +/-                                        secondary grout boreholes are 2 feet (the Extended Grouted Zone)                                            drilled throughout the entire having a maximum equivalent spherical                                          interior region defined by the diameter of equal to or less than 20 feet,                                    diaphragm walls and are offset which is accomplished through drilling                                        from primary grout boreholes and pressure grouting of primary grout                                        such that a secondary grout boreholes and, if necessary, as indicated                                      borehole is at the center of the by site data, secondary grout boreholes.                                      square formed by four adjacent primary grout boreholes at the ground surface, and
* Each additional grout borehole (tertiary or quaternary) drilled to meet grout closure criteria for the Grouted Zone is located based on a documented engineering evaluation consistent with the grout closure criteria
* Each additional grout borehole (secondary) drilled to meet grout closure criteria for the Extended Grouted Zone is located based on a documented engineering evaluation consistent with the grout closure criteria.
(i) All elevations are presented in the North American Vertical Datum of 1988 (NAVD88).
C-507}}

Latest revision as of 10:47, 9 January 2025

COL Appendix C, ITAAC
ML17088A321
Person / Time
Site: Turkey Point  NextEra Energy icon.png
Issue date: 04/12/2018
From:
Office of New Reactors
To:
Hoellman J P/NRO/DNRL/LB4/301-415-5481
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ML17088A330 List:
References
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