ML030090139

Table of Contents - Safety Evaluation Report Related to the License Renewal of McGuire Nuclear Station, Units 1 and 2, Catawba Nuclear Station, Units 1 and 2

ML030090139
Person / Time
Site:	Mcguire, Catawba, McGuire
Issue date:	01/31/2003
From:	Office of Nuclear Reactor Regulation
To:
Franovich R, NRR/DRIP/RLEP, 415-1868
References
Download: ML030090139 (20)

Text

Safety Evaluation Report Related to the License Renewal of McGuire Nuclear Station, Units 1 and 2 Catawba Nuclear Station, Units 1 and 2 Docket Nos. 50-369, 50-370, 50-413, and 50-414 Duke Energy Corporation U.S. Nuclear Regulatory Commission Office of Nuclear Reactor Regulation January 2003

-ii-

-iii-ABSTRACT This safety evaluation report documents the Nuclear Regulatory Commissions (NRCs) review of Duke Energy Corporations (Dukes) application to renew the operating licenses for McGuire Nuclear Station, Units 1 and 2 (McGuire 1 and 2), and Catawba Nuclear Station, Units 1 and 2 (Catawba 1 and 2). The NRCs Office of Nuclear Reactor Regulation has reviewed the McGuire 1 and 2 and Catawba 1 and 2 license renewal application for compliance with the requirements of Title 10 of the Code of Federal Regulations, Part 54 (10 CFR Part 54),

Requirements for Renewal of Operating Licenses for Nuclear Power Plants, and prepared this report to document its findings.

On June 13, 2001, Duke submitted applications for renewal of McGuire 1 and 2 Operating License Nos. NPF-9 and NPF-17, which were issued pursuant to Section 103 of the Atomic Energy Act of 1954, as amended, for a period of up to 20 years beyond the current license expiration dates of June 12, 2021, and March 3, 2023, for McGuire 1 and 2, respectively. The McGuire nuclear facility is located 17 miles north-northwest of Charlotte, North Carolina, in Mecklenburg County. McGuire 1 and 2 are four-loop, Westinghouse pressurized-water reactors with nuclear steam supply systems designed to generate 3411 megawatts thermal, or 1129 megawatts electric.

In the same submittal of June 13, 2001, Duke requested renewal of the Catawba 1 and 2 Operating License Nos. NPF-35 and NPF-52, which were issued under Section 103 of the Atomic Energy Act of 1954, as amended, for a period of up to 19 years beyond the current license expiration dates of December 6, 2024, and February 24, 2026, respectively. The Catawba nuclear facility is located 18 miles southwest of Charlotte, North Carolina, in York County. Catawba 1 and 2 are four-loop, Westinghouse pressurized-water reactors with nuclear steam supply systems designed to generate 3411 megawatts thermal, or 1129 megawatts electric.

The NRC McGuire and Catawba license renewal project manager is Rani Franovich. Ms.

Franovich may be reached at 301-415-1868. Written correspondence should be addressed to the License Renewal and Environmental Impacts Program, U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001.

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-v-Table of Contents Abstract................................................................. -iii-Table of Contents.........................................................

-v-Abbreviations.......................................................... -xxiv-1 Introduction and General Discussion......................................... 1-1 1.1 Introduction........................................................ 1-1 1.2 License Renewal Background.......................................... 1-3 1.2.1 Safety Reviews................................................. 1-4 1.2.2 Environmental Reviews.......................................... 1-5 1.3 Summary of Principal Review Matters.................................... 1-6 1.3.1 Westinghouse Topical Reports..................................... 1-7 1.4 Summary of Open Items and Confirmatory Items........................... 1-8 2 Scoping and Screening................................................... 2-1 2.1 Scoping and Screening Methodology.................................... 2-1 2.1.1 Introduction.................................................... 2-1 2.1.2 Technical Information in the Application.............................. 2-1 2.1.2.1 Scoping Methodology

....................................... 2-2 2.1.2.2 Screening Methodology...................................... 2-3 2.1.3 Staff Evaluation................................................ 2-5 2.1.3.1 Evaluation of the Methodology for Identifying Systems, Structures, and Components Within the Scope of License Renewal................. 2-6 2.1.3.2 Evaluation of the Methodology for Identifying Structures and Components Subject to an Aging Management Review............. 2-11 2.1.4 Conclusions.................................................. 2-14 2.2 Plant-Level Scoping Results.......................................... 2-14 2.2.1 Introduction................................................... 2-14 2.2.2 Technical Information in the Application............................. 2-14 2.2.2.1 Systems, Structures and Components Within the Scope of License Renewal................................................. 2-14 2.2.2.2 Systems and Structures Not Within the Scope of License Renewal.... 2-15 2.2.3 Staff Evaluation............................................... 2-15 2.2.4 Conclusions.................................................. 2-17 2.3 System Scoping and Screening Results: Mechanical....................... 2-17 2.3.1 System Scoping and Screening Results: Reactor Coolant System........ 2-17 2.3.1.1 Reactor Coolant System.................................... 2-17 2.3.1.2 Class 1 Piping, Valves and Pumps

............................ 2-19 2.3.1.3 Pressurizer............................................... 2-21 2.3.1.4 Reactor Vessel and Control Rod Drive Mechanism (CRDM) Pressure Boundary................................................ 2-23 2.3.1.5 Reactor Vessel Internals (RVI)................................ 2-25 2.3.1.6 Steam Generator.......................................... 2-26 2.3.2 System Scoping and Screening Results: Engineered Safety Features..... 2-29 2.3.2.1 Annulus Ventilation System.................................. 2-29

-vi-2.3.2.2 Containment Isolation System................................ 2-34 2.3.2.3 Containment Air Return Exchange and Hydrogen Skimmer System... 2-36 2.3.2.4 Containment Spray System.................................. 2-38 2.3.2.5 Containment Valve Injection Water System...................... 2-40 2.3.2.6 Refueling Water System.................................... 2-41 2.3.2.7 Residual Heat Removal System............................... 2-44 2.3.2.8 Safety Injection System..................................... 2-47 2.3.2.9 Miscellaneous Instrumentation System......................... 2-48 2.3.3 System Scoping and Screening Results: Auxiliary Systems............. 2-50 2.3.3.1 Auxiliary Building Ventilation System........................... 2-50 2.3.3.2 Boron Recycle System...................................... 2-55 2.3.3.3 Building Heating Water System............................... 2-56 2.3.3.4 Chemical and Volume Control System.......................... 2-58 2.3.3.5 Component Cooling System

................................. 2-60 2.3.3.6 Condenser Circulating Water System.......................... 2-65 2.3.3.7 Containment Ventilation Systems............................. 2-70 2.3.3.8 Control Area Ventilation System and Chilled Water System......... 2-71 2.3.3.9 Conventional Waste Water Treatment System................... 2-82 2.3.3.10 Diesel Building Ventilation System............................ 2-84 2.3.3.11 Diesel Generator Air Intake and Exhaust System................ 2-88 2.3.3.12 Diesel Generator Cooling Water System....................... 2-90 2.3.3.13 Diesel Generator Crankcase Vacuum System................... 2-92 2.3.3.14 Diesel Generator Fuel Oil System............................ 2-94 2.3.3.15 Diesel Generator Lube Oil System............................ 2-97 2.3.3.16 Diesel Generator Room Sump Pump System.................. 2-100 2.3.3.17 Diesel Generator Starting Air System

........................ 2-102 2.3.3.18 Drinking Water System................................... 2-105 2.3.3.19 Fire Protection System.................................... 2-107 2.3.3.20 Fuel Handling Building Ventilation System..................... 2-119 2.3.3.21 Groundwater Drainage System............................. 2-124 2.3.3.22 Hydrogen Bulk Storage System............................. 2-126 2.3.3.23 Instrument Air System.................................... 2-127 2.3.3.24 Liquid Waste System..................................... 2-129 2.3.3.25 Miscellaneous Structures Ventilation System................... 2-132 2.3.3.26 Nitrogen System........................................ 2-134 2.3.3.27 Nuclear Sampling System................................. 2-138 2.3.3.28 Nuclear Service Water System............................. 2-140 2.3.3.29 Nuclear Service Water Pump Structure Ventilation System........ 2-142 2.3.3.30 Nuclear Solid Waste Disposal System........................ 2-145 2.3.3.31 Reactor Coolant Pump Motor Oil Collection Sub-System.......... 2-147 2.3.3.32 Reactor Coolant System (Non-Class 1 Components)............ 2-150 2.3.3.33 Recirculated Cooling Water System

......................... 2-151 2.3.3.34 Spent Fuel Cooling System................................ 2-154 2.3.3.35 Standby Shutdown Diesel................................. 2-156 2.3.3.36 Turbine Building Sump Pump System........................ 2-160 2.3.3.37 Turbine Building Ventilation System.......................... 2-162 2.3.3.38 Waste Gas System...................................... 2-165

-vii-2.3.4 System Scoping and Screening Results: Steam and Power Conversion Systems

........................................................ 2-168 2.3.4.1 Auxiliary Feedwater System................................. 2-168 2.3.4.2 Auxiliary Steam System.................................... 2-170 2.3.4.3 Condensate System....................................... 2-172 2.3.4.4 Condensate Storage System................................ 2-173 2.3.4.5 Feedwater System........................................ 2-175 2.3.4.6 Feedwater Pump Turbine Exhaust System..................... 2-176 2.3.4.7 Feedwater Pump Turbine Hydraulic Oil System.................. 2-178 2.3.4.8 Main Steam System....................................... 2-179 2.3.4.9 Main Steam Supply to Auxiliary Equipment..................... 2-181 2.3.4.10 Main Steam Vent to Atmosphere System...................... 2-182 2.3.4.11 Main Turbine Hydraulic Oil System.......................... 2-184 2.3.4.12 Main Turbine Lube Oil and Purification System................. 2-185 2.4 Scoping and Screening Results: Structures............................. 2-187 2.4.1 Reactor Buildings............................................. 2-187 2.4.1.1 Concrete Shield Building................................... 2-187 2.4.1.2 Steel Containment........................................ 2-190 2.4.1.3 Reactor Building Internal Structures

.......................... 2-192 2.4.2 Other Structures.............................................. 2-194 2.4.2.1 Auxiliary Buildings........................................ 2-195 2.4.2.2 Condenser Cooling Water Intake Structure..................... 2-198 2.4.2.3 Nuclear Service Water Structures............................ 2-200 2.4.2.4 Standby Nuclear Service Water Pond Dam..................... 2-202 2.4.2.5 Standby Shutdown Facility.................................. 2-204 2.4.2.6 Turbine Buildings (including Service Building)................... 2-205 2.4.2.7 Unit Vent Stack.......................................... 2-207 2.4.2.8 Yard Structures.......................................... 2-207 2.4.3 Component Supports.......................................... 2-209 2.4.3.1 Technical Information in the Application........................ 2-210 2.4.3.2 Staff Evaluation.......................................... 2-210 2.4.3.3 Conclusions............................................. 2-212 2.5 Scoping and Screening Results: Electrical and Instrumentation and Controls... 2-213 2.5.1 Technical Information in the Application............................ 2-213 2.5.2 Staff Evaluation.............................................. 2-213 2.5.2.1 Identification of Passive Components......................... 2-214 2.5.2.2 Identification of Components Not Within the Scope of License Renewal 2-215 2.5.2.3 Identification of Components that are Passive but Not Long-Lived... 2-219 2.5.3 Conclusion.................................................. 2-219 3 Aging Management Review Results.......................................... 3-1 3.0 Common Aging Management Programs.................................. 3-1 3.0.1 Introduction.................................................... 3-1 3.0.2 Program and Activity Attributes..................................... 3-1 3.0.3 Common Aging Management Programs and Activities................... 3-2 3.0.3.1 Borated Water Systems Stainless Steel Inspection................. 3-2 3.0.3.2 Chemistry Control Program................................... 3-5 3.0.3.3 Containment Inservice Inspection Plan - IWE.................... 3-10

-viii-3.0.3.4 Containment Leak Rate Testing Program....................... 3-17 3.0.3.5 Fire Barrier Inspections..................................... 3-22 3.0.3.6 Flow-Accelerated Corrosion Program.......................... 3-25 3.0.3.7 Fluid Leak Management Program............................. 3-28 3.0.3.8 Galvanic Susceptibility Inspection............................. 3-32 3.0.3.9 Common Heat Exchanger Activities............................ 3-35 3.0.3.10 Inservice Inspection Plan................................... 3-43 3.0.3.11 Inspection Program for Civil Engineering Structures and Components 3-53 3.0.3.12 Liquid Waste System Inspection............................. 3-58 3.0.3.13 Preventive Maintenance Activities - Condenser Circulating Water System Internal Coating Program............................ 3-61 3.0.3.14 Selective Leaching Inspection............................... 3-66 3.0.3.15 Service Water Piping Corrosion Program...................... 3-70 3.0.3.16 Sump Pump Systems Inspection............................. 3-75 3.0.3.17 Treated Water Systems Stainless Steel Inspection............... 3-78 3.0.3.18 Underwater Inspection of Nuclear Service Water Structures........ 3-81 3.0.3.19 Ventilation Area Pressure Boundary Sealants Inspection

.......... 3-85 3.0.4 Quality Assurance Program...................................... 3-87 3.0.4.1 Technical Information in the Application......................... 3-88 3.0.4.2 Staff Evaluation........................................... 3-89 3.0.4.3 Programs and Activities, FSAR Supplement..................... 3-90 3.0.4.4 Conclusions.............................................. 3-91 3.1 Aging Management of Reactor Vessel, Internals, and Reactor Coolant System... 3-92 3.1.1 Reactor Coolant Class 1 Piping, Valves, and Pump Casings............. 3-93 3.1.1.1 Technical Information in the Application......................... 3-93 3.1.1.2 Staff Evaluation........................................... 3-95 3.1.1.3 Conclusions............................................. 3-101 3.1.2 Pressurizers................................................. 3-101 3.1.2.1 Technical Information in the Application........................ 3-102 3.1.2.2 Staff Evaluation.......................................... 3-103 3.1.2.3 Conclusions............................................. 3-118 3.1.3 Reactor Vessel and Control Rod Drive Mechanism Pressure Boundary.... 3-119 3.1.3.1 Technical Information in the Application........................ 3-119 3.1.3.2 Staff Evaluation.......................................... 3-121 3.1.3.3 Conclusions............................................. 3-145 3.1.4 Reactor Vessel Internals........................................ 3-145 3.1.4.1 Technical Information in the Application........................ 3-146 3.1.4.2 Staff Evaluation.......................................... 3-147 3.1.4.3 Conclusions............................................. 3-163 3.1.5 Steam Generators............................................ 3-163 3.1.5.1 Technical Information in the Application........................ 3-164 3.1.5.2 Staff Evaluation.......................................... 3-165 3.1.5.3 Conclusions............................................. 3-175 3.1.6 Aging Management Review for Class-1 Closure Bolting................ 3-175 3.1.6.1 Aging Effects............................................ 3-176 3.1.6.2 Aging Management Programs............................... 3-176 3.1.6.3 Conclusions............................................. 3-176

-ix-3.2 Aging Management of Engineered Safety Features....................... 3-177 3.2.1 Annulus Ventilation System..................................... 3-178 3.2.1.1 Technical Information in the Application........................ 3-178 3.2.1.2 Staff Evaluation.......................................... 3-178 3.2.1.3 Conclusions............................................. 3-180 3.2.2 Containment Isolation System................................... 3-181 3.2.2.1 Technical Information in the Application........................ 3-181 3.2.2.2 Staff Evaluation.......................................... 3-183 3.2.2.3 Conclusions............................................. 3-186 3.2.3 Containment Air Return Exchange and Hydrogen Skimmer System

...... 3-186 3.2.3.1 Technical Information in the Application........................ 3-186 3.2.3.2 Staff Evaluation.......................................... 3-187 3.2.3.3 Conclusions............................................. 3-188 3.2.4 Containment Spray System..................................... 3-188 3.2.4.1 Technical Information in the Application........................ 3-188 3.2.4.2 Staff Evaluation.......................................... 3-189 3.2.4.3 Conclusions............................................. 3-197 3.2.5 Containment Valve Injection Water System......................... 3-197 3.2.5.1 Technical Information in the Application........................ 3-197 3.2.5.2 Staff Evaluation.......................................... 3-198 3.2.5.3 Conclusions............................................. 3-199 3.2.6 Refueling Water System........................................ 3-199 3.2.6.1 Technical Information in the Application........................ 3-199 3.2.6.2 Staff Evaluation.......................................... 3-200 3.2.6.3 Conclusions............................................. 3-204 3.2.7 Residual Heat Removal System.................................. 3-204 3.2.7.1 Technical Information in the Application........................ 3-204 3.2.7.2 Staff Evaluation.......................................... 3-205 3.2.7.3 Conclusions............................................. 3-207 3.2.8 Safety Injection System........................................ 3-208 3.2.8.1 Technical Information in the Application........................ 3-208 3.2.8.2 Staff Evaluation.......................................... 3-209 3.2.8.3 Conclusions............................................. 3-210 3.2.9 Containment Air Return Exchange and Hydrogen Skimmer Systems -

Supplemental Evaluation....................................... 3-211 3.2.9.1 Technical Information in the Application........................ 3-211 3.2.9.2 Staff Evaluation.......................................... 3-212 3.2.9.3 Conclusions............................................. 3-212 3.2.10 Aging Management Review for Closure Bolting in Engineered Safety Features

.................................................. 3-212 3.2.10.1 Aging Effects........................................... 3-213 3.2.10.2 Aging Management Programs.............................. 3-214 3.2.10.3 Conclusions............................................ 3-214 3.3 Auxiliary Systems................................................. 3-215 3.3.1 Auxiliary Building Ventilation System.............................. 3-216 3.3.1.1 Technical Information in the Application........................ 3-216 3.3.1.2 Staff Evaluation.......................................... 3-317 3.3.1.3 Conclusions............................................. 3-218

-x-3.3.2 Boron Recycle System......................................... 3-218 3.3.2.1 Technical Information in the Application........................ 3-218 3.3.2.2 Staff Evaluation.......................................... 3-219 3.3.2.3 Conclusions............................................. 3-220 3.3.3 Building Heating Water System.................................. 3-221 3.3.3.1 Technical Information in the Application........................ 3-221 3.3.3.2 Staff Evaluation.......................................... 3-221 3.3.3.3 Conclusions............................................. 3-222 3.3.4 Chemical and Volume Control System............................. 3-222 3.3.4.1 Technical Information in the Application........................ 3-222 3.3.4.2 Staff Evaluation.......................................... 3-223 3.3.4.3 Conclusions............................................. 3-224 3.3.5 Component Cooling System..................................... 3-224 3.3.5.1 Technical Information in the Application........................ 3-224 3.3.5.2 Staff Evaluation.......................................... 3-225 3.3.5.3 Conclusions............................................. 3-233 3.3.6 Condenser Circulating Water System.............................. 3-233 3.3.6.1 Technical Information in the Application........................ 3-233 3.3.6.2 Staff Evaluation.......................................... 3-234 3.3.6.3 Conclusions............................................. 3-239 3.3.7 Containment Ventilation System.................................. 3-239 3.3.7.1 Technical Information in the Application........................ 3-239 3.3.7.2 Staff Evaluation.......................................... 3-239 3.3.7.3 Conclusions............................................. 3-240 3.3.8 Control Area Ventilation System and Chilled Water System............. 3-240 3.3.8.1 Technical Information in the Application........................ 3-240 3.3.8.2 Staff Evaluation.......................................... 3-241 3.3.8.3 Conclusions............................................. 3-247 3.3.9 Conventional Waste Water Treatment System....................... 3-247 3.3.9.1 Technical Information in the Application........................ 3-247 3.3.9.2 Staff Evaluation.......................................... 3-248 3.3.9.3 Conclusions............................................. 3-249 3.3.10 Diesel Building Ventilation System............................... 3-249 3.3.10.1 Technical Information in the Application....................... 3-249 3.3.10.2 Staff Evaluation......................................... 3-250 3.3.10.3 Conclusions............................................ 3-250 3.3.11 Diesel Generator Air Intake and Exhaust System.................... 3-251 3.3.11.1 Technical Information in the Application....................... 3-251 3.3.11.2 Staff Evaluation......................................... 3-251 3.3.11.3 Conclusions............................................ 3-255 3.3.12 Diesel Generator Cooling Water System.......................... 3-255 3.3.12.1 Technical Information in the Application....................... 3-255 3.3.12.2 Staff Evaluation......................................... 3-256 3.3.12.3 Conclusions............................................ 3-264 3.3.13 Diesel Generator Crankcase Vacuum System...................... 3-264 3.3.13.1 Technical Information in the Application....................... 3-264 3.3.13.2 Staff Evaluation......................................... 3-265 3.3.13.3 Conclusions............................................ 3-265

-xi-3.3.14 Diesel Generator Fuel Oil System

............................... 3-266 3.3.14.1 Technical Information in the Application....................... 3-266 3.3.14.2 Staff Evaluation......................................... 3-267 3.3.14.3 Conclusions............................................ 3-267 3.3.15 Diesel Generator Lube Oil System............................... 3-268 3.3.15.1 Technical Information in the Application....................... 3-268 3.3.15.2 Staff Evaluation......................................... 3-269 3.3.15.3 Conclusions............................................ 3-271 3.3.16 Diesel Generator Room Sump Pump System....................... 3-271 3.3.16.1 Technical Information in the Application....................... 3-271 3.3.16.2 Staff Evaluation......................................... 3-272 3.3.16.3 Conclusions............................................ 3-273 3.3.17 Diesel Generator Starting Air System............................. 3-274 3.3.17.1 Technical Information in the Application....................... 3-274 3.3.17.2 Staff Evaluation......................................... 3-275 3.3.17.3 Conclusions............................................ 3-283 3.3.18 Drinking Water System........................................ 3-283 3.3.18.1Technical Information in the Application....................... 3-283 3.3.18.2 Staff Evaluation......................................... 3-284 3.3.18.3 Conclusions............................................ 3-284 3.3.19 Fire Protection System........................................ 3-285 3.3.19.1 Technical Information in the Application....................... 3-285 3.3.19.2 Staff Evaluation......................................... 3-288 3.3.19.3 Conclusions............................................ 3-303 3.3.20 Fuel Handling Building Ventilation System......................... 3-303 3.3.20.1 Technical Information in the Application....................... 3-303 3.3.20.2 Staff Evaluation......................................... 3-304 3.3.20.3 Conclusions............................................ 3-305 3.3.21 Groundwater Drainage System.................................. 3-305 3.3.21.1 Technical Information in the Application....................... 3-305 3.3.21.2 Staff Evaluation......................................... 3-306 3.3.21.3 Conclusions............................................ 3-304 3.3.22 Hydrogen Bulk Storage System................................. 3-307 3.3.22.1 Technical Information in the Application....................... 3-307 3.3.22.2 Staff Evaluation......................................... 3-308 3.3.22.3 Conclusions............................................ 3-309 3.3.23 Instrument Air System........................................ 3-309 3.3.23.1 Technical Information in the Application....................... 3-309 3.3.23.2 Staff Evaluation......................................... 3-310 3.3.23.3 Conclusions............................................ 3-311 3.3.24 Liquid Waste System......................................... 3-311 3.3.24.1 Technical Information in the Application....................... 3-311 3.3.24.2 Staff Evaluation......................................... 3-312 3.3.24.3 Conclusions............................................ 3-314 3.3.25 Miscellaneous Structures Ventilation System....................... 3-314 3.3.25.1 Technical Information in the Application....................... 3-314 3.3.25.2 Staff Evaluation......................................... 3-314 3.3.25.3 Conclusions............................................ 3-315

-xii-3.3.26 Nitrogen System............................................. 3-315 3.3.26.1 Technical Information in the Application....................... 3-315 3.3.26.2 Staff Evaluation......................................... 3-315 3.3.26.3 Conclusions............................................ 3-316 3.3.27 Nuclear Sampling System

..................................... 3-316 3.3.27.1 Technical Information in the Application....................... 3-316 3.3.27.2 Staff Evaluation......................................... 3-317 3.3.27.3 Conclusions............................................ 3-318 3.3.28 Nuclear Service Water System.................................. 3-318 3.3.28.1 Technical Information in the Application....................... 3-318 3.3.28.2 Staff Evaluation......................................... 3-319 3.3.28.3 Conclusions............................................ 3-323 3.3.29 Nuclear Service Water Pump Structure Ventilation System............ 3-324 3.3.29.1 Technical Information in the Application....................... 3-324 3.3.29.2 Staff Evaluation......................................... 3-324 3.3.29.3 Conclusions............................................ 3-325 3.3.30 Nuclear Solid Waste Disposal System............................ 3-325 3.3.30.1 Technical Information in the Application....................... 3-325 3.3.30.2 Staff Evaluation......................................... 3-326 3.3.30.3 Conclusions............................................ 3-327 3.3.31 Reactor Coolant Pump Motor Oil Collection Sub-System.............. 3-327 3.3.31.1 Technical Information in the Application....................... 3-327 3.3.31.2 Staff Evaluation......................................... 3-328 3.3.31.3 Conclusions............................................ 3-329 3.3.32 Reactor Coolant System (Non-Class 1 Components)................. 3-330 3.3.32.1 Technical Information in the Application....................... 3-330 3.3.32.2 Staff Evaluation......................................... 3-330 3.3.32.3 Conclusions............................................ 3-332 3.3.33 Recirculated Cooling Water System.............................. 3-332 3.3.33.1 Technical Information in the Application....................... 3-332 3.3.33.2 Staff Evaluation......................................... 3-333 3.3.33.3 Conclusions............................................ 3-334 3.3.34 Spent Fuel Cooling System.................................... 3-334 3.3.34.1 Technical Information in the Application....................... 3-334 3.3.34.2 Staff Evaluation......................................... 3-335 3.3.34.3 Conclusions............................................ 3-336 3.3.35 Standby Shutdown Diesel...................................... 3-336 3.3.35.1 Technical Information in the Application....................... 3-336 3.3.35.2 Staff Evaluation......................................... 3-337 3.3.35.3 Conclusions............................................ 3-342 3.3.36 Turbine Building Sump Pump System

............................ 3-343 3.3.36.1 Technical Information in the Application....................... 3-343 3.3.36.2 Staff Evaluation......................................... 3-343 3.3.36.3 Conclusions............................................ 3-344 3.3.37 Turbine Building Ventilation System.............................. 3-345 3.3.37.1 Technical Information in the Application....................... 3-345 3.3.37.2 Staff Evaluation......................................... 3-345 3.3.37.3 Conclusions............................................ 3-346 3.3.38 Waste Gas System........................................... 3-346 3.3.38.1 Technical Information in the Application....................... 3-346

-xiii-3.3.38.2 Staff Evaluation......................................... 3-347 3.3.38.3 Conclusions............................................ 3-352 3.3.39 Auxiliary Systems - General.................................... 3-352 3.3.39.1 Thermal Fatigue......................................... 3-352 3.3.39.2 Scoping Issues Related to Aging Management Programs for Auxiliary Systems.............................................. 3-352 3.3.39.3 Ventilation Systems Flexible Connectors...................... 3-353 3.3.39.4 Aging Management Review for Closure Bolting in Auxiliary Systems. 3-354 3.4 Steam and Power Conversion Systems

................................ 3-356 3.4.1 Auxiliary Feedwater System..................................... 3-356 3.4.1.1 Technical Information in the Application........................ 3-356 3.4.1.2 Staff Evaluation.......................................... 3-357 3.4.1.3 Conclusions............................................. 3-359 3.4.2 Auxiliary Steam System........................................ 3-359 3.4.2.1 Technical Information in the Application........................ 3-359 3.4.2.2 Staff Evaluation.......................................... 3-360 3.4.2.3 Conclusions............................................. 3-361 3.4.3 Condensate System........................................... 3-361 3.4.3.1 Technical Information in the Application........................ 3-362 3.4.3.2 Staff Evaluation.......................................... 3-362 3.4.3.3 Conclusions............................................. 3-363 3.4.4 Condensate Storage System.................................... 3-363 3.4.4.1 Technical Information in the Application........................ 3-363 3.4.4.2 Staff Evaluation.......................................... 3-364 3.4.4.3 Conclusions............................................. 3-365 3.4.5 Feedwater System............................................ 3-365 3.4.5.1 Technical Information in the Application........................ 3-365 3.4.5.2 Staff Evaluation.......................................... 3-367 3.4.5.3 Conclusions............................................. 3-367 3.4.6 Feedwater Pump Turbine Exhaust System.......................... 3-368 3.4.6.1 Technical Information in the Application........................ 3-368 3.4.6.2 Staff Evaluation.......................................... 3-369 3.4.6.3 Conclusions............................................. 3-370 3.4.7 Main Steam System........................................... 3-370 3.4.7.1 Technical Information in the Application........................ 3-370 3.4.7.2 Staff Evaluation.......................................... 3-371 3.4.7.3 Conclusions............................................. 3-372 3.4.8 Main Steam Supply to Auxiliary Equipment System................... 3-372 3.4.8.1 Technical Information in the Application........................ 3-372 3.4.8.2 Staff Evaluation.......................................... 3-374 3.4.8.3 Conclusions............................................. 3-374 3.4.9 Main Steam Vent to Atmosphere System........................... 3-375 3.4.9.1 Technical Information in the Application........................ 3-375 3.4.9.2 Staff Evaluation.......................................... 3-376 3.4.9.3 Conclusions............................................. 3-377 3.4.10 Aging Management Review for Closure Bolting in Steam and Power 377 Conversion Systems.......................................... 3-377 3.4.10.1 Aging Effects........................................... 3-377 3.4.10.2 Aging Management Programs.............................. 3-378 3.4.10.3 Conclusions............................................ 3-378

-xiv-3.5 Aging Management of Containments, Structures, and Component Supports.... 3-380 3.5.1 Reactor Building.............................................. 3-380 3.5.1.1 Technical Information in the Application........................ 3-380 3.5.1.2 Staff Evaluation.......................................... 3-383 3.5.1.3 Conclusions............................................. 3-400 3.5.2 Other Structures.............................................. 3-401 3.5.2.1 Technical Information in the Application........................ 3-401 3.5.2.2 Staff Evaluation.......................................... 3-403 3.5.2.3 Conclusions............................................. 3-414 3.5.3 Component Supports.......................................... 3-414 3.5.3.1 Technical Information in the Application........................ 3-414 3.5.3.2 Staff Evaluation.......................................... 3-415 3.5.3.3 Conclusions............................................. 3-423 3.5.4 Aging Management Review for High-Strength Structural Bolting......... 3-423 3.5.4.1 Aging Effects............................................ 3-423 3.5.4.2 Aging Management Programs............................... 3-423 3.5.4.3 Conclusions............................................. 3-423 3.6 Aging Management of Electrical and Instrumentation and Controls Components. 3-424 3.6.1 Aging Effects Caused by Heat and Radiation........................ 3-424 3.6.1.1 Technical Information in the Application........................ 3-424 3.6.1.2 Staff Evaluation.......................................... 3-426 3.6.1.3 Conclusions............................................. 3-436 3.6.2 Aging Effects Caused by Moisture and Voltage Stress for Inaccessible Medium-Voltage Cables....................................... 3-437 3.6.2.1 Technical Information in the Application........................ 3-437 3.6.2.2 Staff Evaluation.......................................... 3-437 3.6.2.3 Conclusions............................................. 3-444 3.6.3 Aging Effects Caused by Boric Acid Ingress into Connector Pins......... 3-444 3.6.3.1 Technical Information in the Application........................ 3-444 3.6.3.2 Staff Evaluation.......................................... 3-445 3.6.3.3 Conclusions............................................. 3-445 3.6.4 Aging Management of Electrical Components Required for SBO......... 3-445 3.6.4.1 AMR Results for Isolated-Phase Bus and Nonsegregated-Phase Bus. 3-445 3.6.4.2 Staff Evaluation of AMR Results for Isolated-Phase Bus and Nonsegregated-Phase Bus................................. 3-447 3.6.4.3 Conclusion.............................................. 3-449 3.6.4.4 Aging Management Review Results for Transmission Conductors, Switchyard Bus, and High-Voltage Insulators.................... 3-449 3.6.4.5 Staff Evaluation of Aging Management Review Results for Transmission Conductor, Switchyard Bus, and High-Voltage Insulators 3-451 3.6.4.6 Conclusions............................................. 3-453 4 Time-Limited Aging Analyses............................................... 4-1 4.1 Identification of Time-Limited Aging Analyses.............................. 4-1 4.1.1 Technical Information in the Application.............................. 4-1 4.1.2 Staff Evaluation................................................ 4-2 4.1.3 Conclusions................................................... 4-2 4.2 Reactor Vessel Neutron Embrittlement................................... 4-2 4.2.1 Upper Shelf Energy............................................. 4-3 4.2.1.1 Technical Information in the Application.......................... 4-3 4.2.1.2 Staff Evaluation............................................ 4-3

-xv-4.2.2 Pressurized Thermal Shock....................................... 4-5 4.2.2.1 Technical Information in the Application.......................... 4-6 4.2.2.2 Staff Evaluation............................................ 4-6 4.2.3 Pressure-Temperature Limits...................................... 4-8 4.2.3.1 Technical Information in the Application.......................... 4-8 4.2.3.2 Staff Evaluation............................................ 4-9 4.2.4 FSAR Supplement.............................................. 4-9 4.2.5 Conclusions................................................... 4-9 4.3 Metal Fatigue

..................................................... 4-10 4.3.1 Technical Information in the Application............................. 4-10 4.3.2 Staff Evaluation............................................... 4-11 4.3.3 FSAR Supplement............................................. 4-20 4.3.4 Conclusions.................................................. 4-21 4.4 Environmental Qualification of Electric Equipment......................... 4-21 4.4.1 Technical Information in the Application............................. 4-21 4.4.2 Staff Evaluation............................................... 4-25 4.4.3 FSAR Supplement............................................. 4-27 4.4.4 Conclusions.................................................. 4-27 4.5 Concrete Containment Tendon Prestress................................ 4-27 4.5.1 Technical Information in the Application............................. 4-27 4.5.2 Staff Evaluation............................................... 4-28 4.5.3 Conclusions.................................................. 4-28 4.6 Containment Liner Plate, Metal Containments, and Penetration Fatigue Analysis.. 4-28 4.6.1 Technical Information in the Application............................. 4-28 4.6.2 Staff Evaluation............................................... 4-29 4.6.3 FSAR Supplement............................................. 4-30 4.6.4 Conclusions.................................................. 4-30 4.7 Other Plant-Specific Time-Limited Aging Analyses......................... 4-31 4.7.1 Reactor Coolant Pump Flywheel Fatigue............................ 4-31 4.7.1.1 Technical Information in the Application......................... 4-31 4.7.1.2 Staff Evaluation........................................... 4-31 4.7.1.3 FSAR Supplement......................................... 4-31 4.7.1.4 Conclusions.............................................. 4-31 4.7.2 Leak-Before-Break Analyses..................................... 4-32 4.7.2.1 Technical Information in the Application......................... 4-32 4.7.2.2 Staff Evaluation........................................... 4-33 4.7.2.3 FSAR Supplement......................................... 4-34 4.7.2.4 Conclusions.............................................. 4-34 4.7.3 Depletion of Nuclear Service Water Pond Volume due to Runoff.......... 4-35 4.7.3.1 Technical Information in the Application......................... 4-35 4.7.3.2 Staff Evaluation........................................... 4-36 4.7.3.3 FSAR Supplement......................................... 4-37 4.7.3.4 Conclusions.............................................. 4-37 5 Review by the Advisory Committee on Reactor Safeguards

....................... 5-1 6 Conclusions............................................................ 6-1 APPENDIX A, Chronology.................................................. A-1

-xvi-APPENDIX B, References.................................................. B-1 APPENDIX C, Principal Contributors

.......................................... C-1 APPENDIX D, Table of Applicant Commitments.................................. D-1

-xvii-ABBREVIATIONS ACI American Concrete Institute ACRS Advisory Committee on Reactor Safeguards ACSR aluminum conductor steel reinforced AFW auxiliary feedwater (system)

AMP aging management program AMR aging management review ANSI American National Standards Institute AS auxiliary steam (system)

ASME American Society of Mechanical Engineers ASTM American Society for Testing and Materials BMI bottom-mounted instrumentation BTP Branch Technical Position BWI Babcock and Wilcox International CASS cast austenitic stainless steel CCW condenser circulating water (system)

CFR Code of Federal Regulations CIV containment isolation valve CLB current licensing basis CRDM control rod drive mechanism CSS containment spray system CUF cumulative usage factor CVCS chemical and volume control system DBA design basis accident DBD design basis document ECCS emergency core cooling systems ECT eddy current test EFPY effective full-power years ELL Electrical Licensing Library EOC end of cycle EOLE end of life extended EPDM ethylene propylene dienyl monomer EPL vital batteries system EPQ diesel generator batteries system EPRI Electric Power Research Institute EQ environmental qualification EQD standby shutdown facility diesel batteries system ETM standby shutdown facility batteries system FAC flow-accelerated corrosion FD (system) flow diagram FI filtration FP fire protection FSAR final safety analysis report GALL Generic Aging Lessons Learned (Report)

GDC general design criterion or general design criteria GEIS generic environmental impact statement gpm gallons per minute GSI generic safety issue

-xviii-HAZ heat-affected zone HELB high-energy line break HVAC heating, ventilation, and air conditioning HT heat transfer I&C instrumentation and controls IASCC irradiation-assisted stress corrosion cracking ID inner diameter IGSCC intergranular stress corrosion cracking IPA integrated plant assessment IR insulation resistance ISG interim staff guidance ISI inservice inspection ITS Improved Technical Specifications LBB leak-before-break (analysis)

LEFM linear elastic fracture mechanics LER Licensee Event Report LOCA loss-of-coolant accident LRA license renewal application LWR light-water reactor MeV million electron volts MIC microbiologically induced corrosion Mpa mega pascals MRP Materials Reliability Project MW megawatts NC reactor coolant NDT nil ductility temperature, non-destructive testing NEI Nuclear Energy Institute NEPA National Environmental Policy Act NFPA National Fire Protection Association NPAR nuclear plant aging research NRC Nuclear Regulatory Commission NSAC Nuclear Safety Analysis Center NSD Nuclear System Directive NSSS nuclear steam supply system NSW nuclear service water (system)

NW containment valve injection water (system)

ODSCC outside diameter stress corrosion cracking OSHA Occupational Safety and Health Administration P-T pressure-temperature P&ID piping and instrumentation diagram PB pressure boundary PCB power circuit breaker PIP Problem Investigation Process PORV power-operated relief valve ppb parts per billion ppm parts per million psig pounds per square inch gauge PTS pressurized thermal shock PWHT post-weld heat treated PWR pressurized water reactor

-xix-PWSCC primary water stress corrosion cracking RAI request for additional information RCCA rod cluster control assembly RCP reactor coolant pump RCS reactor coolant system RF interior fire water (system)

RG regulatory guide RHR residual heat removal (system)

RPV reactor pressure vessel RTD resistance temperature detector RSG replacement steam generator RT reference temperature RV reactor vessel RVI reactor vessel internals RVID Reactor Vessel Integrity Database RWST refueling water storage tank SBO station blackout (event)

SCC stress corrosion cracking SCs structures and components SER safety evaluation report SFP spent fuel pool SG steam generator SIS safety injection system SLC Selected Licensee Commitments SNSW standby nuclear service water SNSWP standby nuclear service water pond SR surveillance requirement SRP Standard Review Plan SCC stress corrosion cracking SCV steel containment vessel SE safety evaluation SER safety evaluation report SOC Statement of Considerations SSs systems and structures SSCs systems, structures, and components SSE safe-shutdown earthquake SSF standby shutdown facility SSS standby shutdown system TFMP Thermal Fatigue Management Program TGSCC transgranular stress corrosion cracking TH throttle TLAA time-limited aging analysis TR testing requirement TS technical specification(s)

TSSR technical specification surveillance requirement UFSAR updated final safety analysis report UHI upper head injection UT ultrasonic testing VA auxiliary building ventilation (system)

VC control area ventilation (system)

-xx-VCP Vessel Closure Penetration (Nozzle Inspection Program)

VD diesel building ventilation (system)

VE annulus ventilation (system)

VF fuel handling building ventilation (system)

VHP vessel head penetration VK miscellaneous structures ventilation (system)

VT visual examination W

Westinghouse WCAP Westinghouse topical report WOG Westinghouse Owners Group YC control area chilled water (system)