ML042940290
| ML042940290 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 10/11/2004 |
| From: | Susquehanna |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| Download: ML042940290 (22) | |
Text
Oct. 11, 2004 Page 1 of 1 MANUAL HARD COPY DISTRIBUTION DOCUMENT TRANSMITTAL 2004-40690 USE INFO ION:
Name:G A *ROSE M EMPL#:028401 CA#:0363 Address: 2 Phone#: 2 4-3 TRANSMITTAL INFORMATION:
TO: 10/11/2004 LOCATION: USNRC FROM: NUCLEAR RECORDS DOCUMENT CONTROL CENTER (NUCSA-2)
THE FOLLOWING CHANGES HAVE OCCURRED TO THE HARDCOPY OR ELECTRONIC MANUAL ASSIGNED TO YOU:
TSB2 - TECHNICAL SPECIFICATIONS BASES UNIT 2 MANUAL REMOVE MANUAL TABLE OF CONTENTS DATE: 10/07/2004
'D MANUAL TABLE OF CONTENTS DATE: 10/08/2004 YATEGORY: DOCUMENTS TYPE: TSB2 ID: TEXT 3.6.4.3 REPLACE: REV:1 UPDATES FOR HARD COPY MANUALS WILL BE DISTRIBUTED WITHIN 5 DAYS IN ACCORDANCE WITH DEPARTMENT PROCEDURES. PLEASE MAKE ALL CHANGES AND ACKNOWLEDGE COMPLETE IN YOUR NIMS INBOX UPON RECEIPT OF HARD COPY. FOR ELECTRONIC MANUAL USERS, ELECTRONICALLY REVIEW THE APPROPRIATE DOCUMENTS AND ACKNOWLEDGE COMPLETE IN YOUR NIMS INBOX.
Oct. 08, 2004 Page I of 1 MANUAL HARD COPY DISTRIBUTION DOCUMENT TRANSMITTAL 2004-40302 USER INFORMATION: __
Name: CH* E M EMPL#:028401 CA#:0363 Address: .2 Phone#: 25 4 TRANSM L INFORMATION:
TO: 10/08/2004 LOCATION: USNRC FROM: NUCLEAR RECORDS DOCUMENT CONTROL CENTER (NUCSA-2)
THE FOLLOWING CHANGES HAVE OCCURRED TO THE HARDCOPY OR ELECTRONIC MANUAL ASSIGNED TO YOU:
TSB2 - TECHNICAL SPECIFICATIONS BASES UNIT 2 MANUAL PZA~,W~AoMM1 T.ABL~E OF CONTENTS DATE: -Uv/ud/zuuq'mm
'D trvt u E OF CONTENTS DATE: 10/U7/Zut CATEGORY: DOCUMENTS TYPE: TSB2
~~~. . ., vra TI--
CATEGORY: DOCUMENTS TYPE: TSB2 ID: TEXT LOES REMOVE: REV:47 ADD: REV: 48 UPDATES FOR HARD COPY MANUALS WILL BE DISTRIBUTED WITHIN 5 DAYS IN ACCORDANCE WITH DEPARTMENT PROCEDURES. PLEASE MAKE ALL CHANGES AND ACKNOWLEDGE COMPLETE IN YOUR NIMS INBOX UPON RECEIPT OF HARD COPY. FOR ELECTRONIC MANUAL USERS, ELECTRONICALLY REVIEW THE APPROPRIATE DOCUMENTS AND ACKNOWLEDGE COMPLETE IN YOUR NIMS INBOX.
SSES MANUAL
. Manual Maine: TSB2 Manual
Title:
TECHNICAL SPECIFICATIONS BASES UNIT 2 MANUAL Table Of Contents Issue Date: 10/08/2004 Procedure Name Rev Issue Date Change ID Change Number TEXT LOES 48 10/07/2004
Title:
LIST OF EFFECTIVE SECTIONS TEXT TOC 3 09/02/2004
Title:
TABLE OF CONTENTS TEXT 2.1.1 0 11/18/2002
Title:
SAFETY LIMITS (SLS) REACTOR CORE SLS TEXT 2.1.2 0 11/18/2002
Title:
SAFETY LIMITS (SLS) REACTOR COOLANT SYSTEM (RCS) PRESSURE SL TEXT 3.0 0 11/18/20024, '
Title:
LIMITING CONDITION FOR OPERATION.-(LCO).,APPLICABILITY TEXT 3.1.1 0 111/18/2002
Title:
REACTIVITY CONTROL SYSTEMS SHUTDOWN MARGIN (SDM)
TEXT 3.1.2 < 11/18/2002 2
Title:
REACTIVITY CONTROL SYSTEMS REACTIVITY ANOMALIES TEXT 3.1.3 -( ) 0 11/18/2002
Title:
REACTIVITY .CONTROL"SYSTEMS CONTROL ROD OPERABILITY TEXT 3.1.4 00 11/18/2002
Title:
REACTIVITY CONTROL SYSTEMS CONTROL'ROD SCRAM TIMES TEXT 3.1.5 0 11/18/2002
Title:
REACTIVITY CONTROL SYSTEMS CONTROL ROD SCRAM ACCUMULATORS TEXT 3.1.6 0 11/18/2002
Title:
REACTIVITY CONTROL SYSTEMS ROD PATTERN CONTROL of 8 Reor Dae 10/11/04.... . --......
Pag 1 Page I of 8 Report Date: 10/11/04
SSES MANUAL I I Manual Name: TSB2 Manual
Title:
TECHNICAL SPECIFICATIONS BASES UNIT 2 MANUAL TEXT 3.1.7 0 11/18/2002
Title:
REACTIVITY CONTROL SYSTEMS STANDBY LIQUID CONTROL (SLC) SYSTEM TEXT 3.1.8 0 11/18/2002
Title:
REACTIVITY CONTROL SYSTEMS SCRAM DISCHARGE VOLUME (SDV) VENT AND DRAIN VALVES TEXT 3.2.1 0 11/18/2002
Title:
POWER DISTRIBUTION LIMITS AVERAGE PLANAR LINEAR HEAT GENERATION RATE (APLHGR)
TEXT 3.2.2 0 11/18/2002
Title:
POWER DISTRIBUTION LIMITS MINIMUM CRITICAL POWER RATIO (MCPR)
TEXT 3.2.3 0 11/18/2002
Title:
POWER DISTRIBUTION LIMITS LINEAR HEAT GENERATION RATE (LHGR)
TEXT 3.2.4 0 11/18/2002
Title:
POWER DISTRIBUTION LIMITS AVERAGE POWER RANGE MONITOR (APRM) GAIN AND SETPOINTS-_j TEXT 3.3.1.1 0 11/18/2002
Title:
INSTRUMENTATION REACTOR PROTECTION SYSTEM (RPS) INSTRUMENTATION TEXT 3.3.1.2 0 11/18/2002
Title:
INSTRUMENTATION SOURCE RANGE MONITOR (SRM) INSTRUMENTATION TEXT 3.3.2.1 0 11/18/2002
Title:
INSTRUMENTATION CONTROL ROD BLOCK INSTRUMENTATION TEXT 3.3.2.2 0 11/18/2002
Title:
INSTRUMENTATION FEEDWATER - MAIN TURBINE HIGH WATER LEVEL TRIP INSTRUMENTATION TEXT 3.3.3.1 0 11/18/2002
Title:
INSTRUMENTATION POST ACCIDENT MONITORING (PAM) INSTRUMENTATION LDCN 3710 TEXT 3.3.3.2 0 11/18/2002
Title:
INSTRUMENTATION REMOTE SHUTDOWN SYSTEM I
Page 2 of 8 Report Date: 10/11/04
SSES' A d Manual Name: TSB2 Manual
Title:
TECHNICAL SPECIFICATIONS BASES.UNIT 2'MANUAL-TEXT 3.3.4.1 0 11/18/2002
Title:
INSTRUMENTATION END OF CYCLE RECIRCULATION PUMP TRIP (EOC-RPT) INSTRUMENTATION TEXT 3.3.4.2 0 11/18/2002 -
Title:
INSTRUMENTATION'ANTICIPATED TRANSIENT WITHOUT SCRAM RECIRCULATION PUMP TRIP (ATWS-RPT) INSTRUMENTATION TEXT 3.3.5.1 0 11/18/2002 e
Title:
INSTRUMENTATIONEMERGENCY CORE COOLING SYSTEM.(ECCS) INSTRUMENTATION TEXT 3.3.5.2 0 11/18/2002
Title:
INSTRUMENTATION REACTOR CORE ISOLATION COOLING (RCIC)J.SYSTEM INSTRUMENTATION TEXT 3.3.6.1 0 11/18/2002
Title:
INSTRUMENTATION PRIMARY CONTAINMENT:ISOLATION INSTRUMENTATION TEXT 3.3.6.2 0 11/18/2002.
Title:
INSTRUMENTATION SECONDARY CONTAINMENT ISOLATION INSTRUMENTATION TEXT 3.3.7.1 0 11/18/2002'
Title:
INSTRUMENTATION CONTROL ROOM EMERGENCY OUTSIDE AIR"SUPPLY (CREOAS) SYSTEM INSTRUMENTATION TEXT 3.3.8.1 1 09/02/2004
Title:
INSTRUMENTATION LOSSOF POWER (LOP) INSTRUMENTATION-TEXT 3.3.8.2 0 11/18/2002'
Title:
INSTRUMENTATION REACTOR PROTECTION-,SYSTEM (RPS) ELECTRIC POWER MONITORING TEXT 3.4.1 1 11/06/2003
Title:
REACTOR COOLANT SYSTEM .(RCS).RECIRCULATION LOOPS OPERATING.
TEXT 3.4.2 0 11/18/2002
Title:
REACTOR COOLANT SYSTEM (RCS) JET PUMPS '
TEXT 3.4.3 0 11/18/2002 I
Title:
REACTOR COOLANT SYSTEM (RCS) SAFETY/RELIEF VALVES (S/RVS)'
P a g e 3 ~~~~~ o f 8_eo t D t : 1 / 1 0 Page 3 of 8 Report Date: 10/11/04
SSES MANUAL Manual Name: TSB2 Manual
Title:
TECHNICAL SPECIFICATIONS BASES UNIT 2 MANUAL TEXT 3.4.4 0 11/18/2002
Title:
REACTOR COOLANT SYSTEM (RCS) RCS OPERATIONAL LEAKAGE TEXT 3.4.5 0 11/18/2002
Title:
REACTOR COOLANT SYSTEM (RCS) RCS PRESSURE ISOLATION VALVE (PIV) LEAKAGE TEXT 3.4.6 0 11/18/2002
Title:
REACTOR COOLANT SYSTEM (RCS) RCS LEAKAGE DETECTION INSTRUMENTATION TEXT 3.4.7 0 11/18/2002
Title:
REACTOR COOLANT SYSTEM (RCS) RCS SPECIFIC ACTIVITY TEXT 3.4.8 0 11/18/2002
Title:
REACTOR COOLANT SYSTEMl (RCS) RESIDUAL HEAT REMOVAL (RHR) SHUTDOWN COOLING SYSTEM
- HOT SHUTDOWN TEXT 3.4.9 . 0 11/18/2002
Title:
REACTOR COOLANT SYSTEM (RCS) RESIDUAL HEAT REMOVAL (RHR) SHUTDOWN COOLING SYSTEM.-,
- COLD SHUTDOWN TEXT 3.4.10 0 11/18/2002
Title:
REACTOR COOLANT SYSTEM (RCS) RCS PRESSURE AND TEMPERATURE (P/T) LIMITS TEXT 3.4.11 0 11/18/2002
Title:
REACTOR COOLANT SYSTEM (RCS) REACTOR STEAM DOME PRESSURE TEXT 3.5.1 0 11/18/2002
Title:
EMERGENCY-CORE COOLING SYSTEMS (ECCS) AND REACTOR CORE ISOLATION COOLING (RCIC)
SYSTEM ECCS - OPERATING TEXT 3.5.2 0 11/18/2002
Title:
EMERGENCY CORE COOLING SYSTEMS (ECCS) AND REACTOR CORE ISOLATION COOLING (RCIC)
SYSTEM ECCS - SHUTDOWN TEXT 3.5.3 0 11/18/2002
Title:
EMERGENCY CORE COOLING SYSTEMS (ECCS) AND REACTOR CORE ISOLATION COOLING (RCIC)
SYSTEM RCIC SYSTEM TEXT 3.6.1.1 0 11/18/2002
Title:
CONTAINMENT SYSTEMS PRIMARY CONTAINMENT Report Date: 10/11/04 Page Page 44 of of 88 Report Date: 10/11/04
.@ ' ;, 5 ,. I.t 1t SSES lMANUAL I -. .
Manual
( Name: TSB2 Manual
Title:
TECHNICAL SPECIFICATIONS BASES UNIT 2 MANUAL :
TEXT 3.6.1.2 0 11/18/2002
Title:
CONTAINMENT SYSTEMS PRIMARY CONTAINMENT AIR LOCK TEXT 3.6.1.3 0 11/18/2002
Title:
CONTAINMENT SYSTEMS PRIMARY CONTAINMENT ISOLATION VALVES (PCIVS)
TEXT 3.6.1.4 0 11/18/2002
Title:
CONTAINMENT SYSTEMS CONTAINMENT.PRESSURE TEXT 3.6.1.5 0 11/18/2002.
Title:
CONTAINMENT SYSTEMS DRYWELL AIR'TEMPERATURE ' - ....
TEXT 3.6.1.6 0 11/18/2002
Title:
CONTAINMENT SYSTEMS SUPPRESSION CHAMBER-TO-DRYWELL VACUUM BREAKERS TEXT 3.6.2.1 0 11/18/2002'.
Title:
CONTAINMENT SYSTEMS SUPPRESSION POOL-AVERAGE TEMPERATURE, TEXT 3.6.2.2 0 11/18/2002
Title:
CONTAINMENT SYSTEMS.SUPPRESSION POOL WATER LEVEL TEXT 3.6.2.3 0 11/18/2002
Title:
CONTAINMENT SYSTEMS RESIDUAL HEAT REMOVAL (RHR) SUPPRESSION POOL COOLING TEXT 3.6.2.4 0 11/18/2002: ..
Title:
CONTAINMENT SYSTEMS RESIDUAL HEAT REMOVAL (RHR)'SUPPRESSION POOL'SPRAY-TEXT 3.6.3.1 0 11/18/2002
Title:
CONTAINMENT SYSTEMS PRIMARY CONTAINMENT HYDROGEN RECOMBINERS TEXT 3.6.3.2 0 11/18/2002
Title:
CONTAINMENT SYSTEMS DRYWELL AIR PLOW SYSTEM '
TEXT 3.6.3.3 0 11/18/2002!
Title:
CONTAINMENT SYSTEMS PRIMARY CONTAINMENT OXYGEN CONCENTRATION Pag 5 of 8 e o D t : 1 / 1 0 Page 5 of S. Report Date: 10/11/04
SSES 4AgNUAL Manual Name: TSB2 Manual
Title:
TECHNICAL SPECIFICATIONS BASES UNIT 2 MANUAL
_- /
TEXT 3.6.4.1 0 11/18/2002
Title:
CONTAINMENT SYSTEMS SECONDARY CONTAINMENT TEXT 3.6.4.2 0 11/18/2002
Title:
CONTAINMENT SYSTEMS SECONDARY CONTAINMENT ISOLATION VALVES (SCIVS)
TEXT 3.6.4.3 1 10/08/2004
Title:
CONTAINMENT SYSTEMS STANDBY GAS TREATMENT (SGT) SYSTEM TEXT 3.7.1 0 11/18/2002
Title:
PLANT SYSTEMS RESIDUAL HEAT REMOVAL SERVICE WATER (RHRSW) SYSTEM AND THE ULTIMATE HEAT SINK (UHS)
TEXT 3.7.2 0 11/18/2002
Title:
PLANT SYSTEMS EMERGENCY SERVICE WATER (ESW) SYSTEM TEXT 3.7.3 0 11/18/2002
Title:
PLANT SYSTEMS CONTROL ROOM EMERGENCY OUTSIDE AIR SUPPLY (CREOAS) SYSTEM TEXT 3.7.4 0 11/18/2002
Title:
PLANT SYSTEMS CONTROL ROOM FLOOR COOLING SYSTEM TEXT 3.7.5 0 11/18/2002
Title:
PLANT SYSTEMS MAIN CONDENSER OFFGAS TEXT 3.7.6 0 11/18/2002
Title:
PLANT SYSTEMS MAIN TURBINE BYPASS SYSTEM TEXT 3.7.7 0 11/18/2002
Title:
PLANT SYSTEMS SPENT FUEL STORAGE POOL WATER LEVEL TEXT 3.8.1 1 10/17/2003
Title:
ELECTRICAL POWER SYSTEMS AC SOURCES - OPERATING TEXT 3.8.2 0 11/18/2002
Title:
ELECTRICAL POWER SYSTEMS AC SOURCES - SHUTDOWN Report Date: 10/11/04 Page6 Page 6 of of 88 Report Date: 10/11/04
SSES M1ANUAL Manual Name:
X TSB2 Manual
Title:
TECHNICAL SPECIFICATIONS BASES UNIT 2 MANUAL TEXT 3.8.3 0 11/18/2002
Title:
ELECTRICAL POWER SYSTEMS DIESEL FUEL OIL, LUBE OIL, AND STARTING AIR TEXT 3.8.4 0 11/18/2002
Title:
ELECTRICAL.POWIER. SYSTEMS'DC SOURCES - OPERATING TEXT 3.8.5 0 11/18/2002.
Title:
ELECTRICAL POWER SYSTEMS DC SOURCES - SHUTDOWN TEXT 3.8.6 0 11/18/2002
Title:
ELECTRICAL POWER SYSTEMS BATTERY CELL PARAMETERS TEXT 3.8.7 0 11/18/2002;'
Title:
ELECTRICAL POWER SYSTEMS DISTRIBUTION-SYSTEMS - OPERATING TEXT 3.8.8 0 11/18/2002'
Title:
ELECTRICAL POWER SYSTEMS DISTRIBUTION SYSTEMS - SHUTDOWN TEXT 3.9.1 0 11/18/2002 'I
Title:
REFUELING OPERATIONS REFUELING EQUIPMENT INTERLOCKS TEXT 3.9.2 0 11/18/2002
Title:
REFUELING OPERATIONS REFUEL POSITION ONE-ROD-OUT INTERLOCK TEXT 3.9.3 0 11/18/2002.:
Title:
REFUELING OPERATIONS CONTROL ROD'POSITION -
TEXT 3.9.4 0 11/18/2002
Title:
REFUELING OPERATIONS CONTROL ROD POSITION INDICATION TEXT 3.9.5 0 11/18/2002
Title:
REFUELING OPERATIONS CONTROL ROD OPERABILITY - REFUELING TEXT 3.9.7 0 11/18/2002
'Title: REFUELING OPERATIONS RESIDUAL HEAT REMOVAL (RHR) - HIGH-WATER LEVEL Report Date: 10/11/04 Page77 Page of.8 of ,8 Report Date: 10/11/04
SSES MANUAL Manual Name: TSB2 Manual
Title:
TECHNICAL SPECIFICATIONS BASES UNIT 2 MANUAL TEXT 3.9.8 0 11/18/2002 I
Title:
REFUELING OPERATIONS RESIDUAL HEAT REMOVAL (RHR) - LOW WATER LEVEL TEXT 3.10.1 0 11/18/2002
Title:
SPECIAL OPERATIONS INSERVICE LEAK AND HYDROSTATIC TESTING OPERATION TEXT 3.10.2 o 11/18/2002
Title:
SPECIAL OPERATIONS REACTOR MODE SWITCH INTERLOCK TESTING TEXT 3.10.3 0 11/18/2002
Title:
SPECIAL OPERATIONS SINGLE CONTROL ROD WITHDRAWAL - HOT SHUTDOWN TEXT 3.10.4 0 11/18/2002
Title:
SPECIAL OPERATIONS SINGLE CONTROL ROD WITHDRAWAL - COLD SHUTDOWN TEXT 3.10.5 0 11/18/2002
Title:
SPECIAL OPERATIONS SINGLE CONTROL ROD DRIVE (CRD) REMOVAL - REFUELING . /
TEXT 3.10.6 0 11/18/2002
Title:
SPECIAL OPERATIONS MULTIPLE CONTROL ROD WITHDRAWAL - REFUELING TEXT 3.10.7 0 11/18/2002
Title:
SPECIAL OPERATIONS CONTROL ROD-TESTING - OPERATING TEXT 3.10.8 0 11/18/2002
Title:
SPECIAL OPERATIONS SHUTDOWN MARGIN (SDM) TEST - REFUELING
_ae _f8Rpr at:1/10 Page 8 of 8 Report Date: 10/11/04
SUSQUEHANNA STEAM ELECTRIC STATION UST OF EFFECTIVE SECTIONS (TECHNICAL SPECIFICATIONS BASES)
Section Title Revision TOC Table of Contents 3 B 2.0 SAFETY LIMITS BASES PageTSIB.2.0-1 ' 1 Pages TS / B 2.0-2 and TS I B 2.0-3 2 PageTS/B2.0-4 . 3 PageTS/B2.0-5 ; '
Pages B 2.0-6 through B 2.0-8 0 B 3.0 LCO AND SR APPLICABILITY BASES Pages B 3.0-1 through'B 3.0-7 i '0 Pages TS / B 3.0-8 and TS / B 3.0-9 1 1A
Pages B 3.0-10 through.B 3.0-12 0 Pages TS / B 3.0-13 through TS I B 3.0-15 \ -
B 3.1 REACTIVITY CONTROL BASES Pages B 3.1-1 through B 3.1-5 0 Pages TS / B 3.1-6 and TS / B 3.-1-7.,
Pages B 3.1-8 through B 3.1-27ir ' ' 0 Page TS / B 3.1 Pages B 3.1-29 through B2-36. .'0 Page TS I B 3.1-37 <JN.>, '
Pages B 3.1-38 through B 31-51 0 B 3.2 POWER DISTRIBULTIONULIMITS BASES Pages TS 1,B-3N2-fithrough TS / B 3.2-4 1 Pages TS [ B 3;2-5 and TS I B 3.2-6 2 Page TS/IB"32-7 Pages T,S /B 3.2- and TS I B 3.2-9 . 2 Rages48Br3.2-10 through TS / B 3.2-19 1 B 3.3 INSTRUMENTATION Pages TS / B 3.3-1 through TS / B 3.3-10 1 PageTS/B3.3-11 2 Pages TS I B 3.3-12 through TS I B 3.3-27 1 Pages TS / B 3.3-28 through TS / B 3.3-30 ... 2 Page TS / B 3.3-31 1 Pages TS / B 3.3-32 and TS / B 3.3-33 2 Pages TS / B 3.3-34 through TS / B 3.3-54
- 1 Pages B 3.3-55 through B 3.3-63 0 Pages TS / B 3.3-64 and TS / B 3.3-65 2 Page TS / B 3.3-66 4 Page TS / B 3.3-67 3 SUSQUEHANNA - UNIT 2 TS i B LOES-1 Revision 4EI
SUSQUEHANNA STEAM ELECTRIC STATION UST OF EFFECTIVE SECTIONS (TECHNICAL SPECIFICATIONS BASES)
Section 'Title Revision Page TS / B 3.3-68 4 Pages TS / B 3.3-69 and TS / B 3.3-70 3 Pages TS / B 3.3-71 through TS / B 3.3-75 2 Page TS / B 3.3-75a 4 Pages TS / B 3.3-75b through TS / B 3.3-75c 3 Pages B 3.3-76 through B 3.3-91 0 Pages TS / B 3.3-92 through TS / B 3.3-103 1 Page TS / B 3.3-104 2 Pages TS / B 3.3-105 and TS / 83.3-106 1 Page TS / B 3.3-107 2 Page TS / B 3.3-108 1 Page TS / B 3.3-109 2 Pages TS I B 3.3-110 through TS / B 3.3-115 1 Pages TS / B 3.3-116 through TS / B 3.3-118 2 Pages TS / B 3.3-119 through TS / B 3.3-120 1 Pages TS / B 3.3-121 and TS / B 3.3-122 2 Page TS / B 3.3-123 1 Page TS / B3.3-124 2 Page TS / B 3.3-124a 0 Pages TS / B.3.3-125 and TS / B 3.3-126 1 Page TS / B 3.3-127 2 Pages TS / B 3.3-128 through TS IB 3.3-131 1 Page TS / B 3.3-132 2 Pages TS / B 3.3-133 and TS / B 3.3-134 .1 Pages B 3.3-135 through B 3.3-137 0 Page TS / B 3.3-138 - 1 Pages B 3.3-139 through B 3.3-149 0 Pages TS/ B 3.3-150 through TS / B 3.3-162 1 Page TS / B 3.3-163 2 Pages TS / B 3.3-164 through TS I B 3.3-177 1 Pages TS I B 3.3-178 and TS I B 3.3-179 2 Page TS / B 3.3-179a 1 Pages TS / B 3.3-180 through TS I B 3.3-191 1 Pages B 3.3-192 through B 3.3-205 0 Page TS / B 3.3-206 1 Pages B 3.3-207 through B 3.3-220 .. 0 B 3.4 REACTOR COOLANT SYSTEM BASES Pages TS / B 3.4-1 and TS / B 3.4-2 . 1 Pages TS / B 3.4-3 through TS / B 3.4-6 2 Page TS / B 3.4-7 1 Pages TS / B 3.4-8 and TS /B3.4-9 2 Pages B 3.4-10 through B 3.4-14 0 SUSQUEHANNA - UNIT 2 ' TS / B LOES-2 Revision 48
SUSQUEHANNA STEAM ELECTRIC STATION LIST OF EFFECTIVESECTIONS (TECHNICAL SPECIFICATIONS BASES)
Section Title Revision Page TS / B 3.4-15 1 Pages TS / B 3.4-16 and TS I B 3.4-17 2 Page TS / B 3.4-18 1 Pages B 3.4-19 through B 3.4-28 0 Page TS / B 3.4-29 1 Pages B 3.3-30 through B 3.3-48 0 Page TS / B 3.4-49 2 Page TS I B 3.4-50 1 Page TS / B 3.4-51 2 Pages TS / B 3.4-52 and TS / B 3.4-53 1 Pages TS / B 3.4-54 and TS I B 3.4-55 2 Pages TS / B 3.4-56 through TS / B 3.4-60 1 B 3.5 ECCS AND RCIC BASES Pages TS / B 3.5-1 and TS I B 3.5-2 1 Page TS / B 3.5-3 2 Pages TS / B 3.5-4 through TS I B 3.5-10 1 PageTS I B 3.5-11 2 Pages TS / B 3.5-12 through TS I B 3.5-14 1 Pages TS / B.3.5-15 through TS / B.3.5-17 2 PageTS/B3.18 1 Pages B 3.5-19 through B 3.5-24 0 Page TS / B 3.5-25 1 Pages B' 3.5-26 through B 3.5-31 0 B 3.6 CONTAINMENT SYSTEMS BASES Page TS / B 3.6-1 2 Page TS / B 3.6-1 a 3 Pages TS I B 3.6-2 through TS / B 3.6-5 2 Page TS / B 3.6-6 3 Pages TS / B 3.6-6a and TS / B 3.6-6b 2 Page TS / B 3.6-6c 0 Pages B 3.6-7 through B 3.6-14 0 Page TS / B 3.6-15 3 Pages TS / B 3.6-1 5a and TS / B 3.6-1 5b 0 Page TS / B 3.6-16 .. 1 Page TS / B 3.6-17 2 Page TS / B 3.6-17a 0 PagesTS/B3.6-18andTSIB3.6-19 1 Page TS / B 3.6-20 2 Page TS / B 3.6-21 3 Pages TS/B3.6-21a and TS B 3.6-21b 0 Pages TS / B 3.6-22 and TS / B 3.6-23 2 SUSQUEHANNA - UNIT 2 TS / B LOES-3 Revision 48
SUSQUEHANNA STEAM ELECTRIC STATION LIST OF EFFECTIVE SECTIONS (TECHNICAL SPECIFICATIONS BASES)
Section Title Revision Pages TS I B 3.6-24 through TS / B 3.6-26 1 Page TS I B 3.6-27 3 Page TS / B 3.6-28 6 Page TS / B 3.6-29 3 Page TS / B 3.6-29a 0 Page TS / B 3.6-30 2 Page TS / B 3.6-31 3 Pages TS I B 3.6-32 through TS I B 3.6-34 1 Pages TS / B 3.6-35 through TS I B 3.6-37 2 Page TS / B 3.6-38 1 Page TS / B 3.6-39 4 Pages. B 3.6-40 through B 3.6-42 0 Pages TS / B 3.6-43 through TS / B 3.6-50 1 Page TS / B 3.6-51 2 Pages B 3.6-52 through B 3.6-62 0 Page TS / B 3.6-63 1 Pages B 3.6-64 through B 3.6-82 0 Page TS / B 3.6-83 2 Pages TS / B 3.6-84 through TS / B 3.6-87 1 Page TS / B 3.6-87a 1 Page TS / B 3.6-88 2 Pages TS / B 3.6-89 through TS / B 3.6-99 1 Page B 3.6-100 0 Pages TS I B 3.6-1 01 through TS / B 3.6-106 1 B 3.7 PLANT SYSTEMS BASES Pages TS / B 3.7-1 through TS / B 3.7-6 2 Page TS / B 3.7-6a 2 Pages TS / B 3.7-6b and TS / B 3.7-6c . 0 Pages TS / B 3.7-7 and TS / B 3.7-8 1 Pages B 3.7-9 through B 3.7-11 0 Pages TS / B 3.7-12 and TS / B 3.7-13 1 Pages TS I B 3.7-14 through TS / B 3.7-18 2 Page TS / B 3.7-18a 0 Pages TS / B 3.7-19 through TS / B 3.7-26 i Pages B 3.7-24 through B 3.7-26 0 Pages TS / 3.7-27. through TS / B 3.7-29 1 Pages B 3.7-30 through B 3.7-33 0 B 3.8 ELECTRICAL POWER SYSTEMS BASES Pages B 3.8-1 through B 3.8-4 0 Page TS / B 3.8-5 1 Pages B 3.8-6 through B 3.8-8 0 Revision 48 TSIB LOES-4 SUSQUEHANNA - UNIT UNIT 22 TS /B LOES-4 Revision 48
SUSQUEHANNA STEAM ELECTRIC STATION LIST OF EFFECTVE SECTIONS (TECHNICAL SPECIFICATIONS BASES)
Section Title Revision Pages TS / B 3.8-9 through TS / B 3.8-11 1 Pages B 3.8-12 through B 3.8-18 0 Page TS / B 3.8-19 1 Pages B 3.8-20 through B 3.8-22 0 Page TS / B 3.8-23 1 Page B 3.8-24 0 Pages TS / B 3.8-25 and TS / B 3.8-26 1 Pages B 3.8-27 through B 3.8-37 0 Page TS / B 3.8-38 1 Pages TS / B 3.8-39 through TS / B 3.8-55 0 Pages TS / B 3.8-56 through TS / B 3.8-64 1 Page TS / B 3.8-65 2 Page TS I B 3.8-66 2 Pages TS / B 3.8-67 through TS / B 3.8-68 1 Page TS / B 3.8-69 2 Pages B 3.8-70 through B 3.8-99 0 B 3.9 REFUELING OPERATIONS BASES, Pages TS / B 3.9-1 and TS / B 3.9-2 1 Page TS / B 3.9-2a 1 Pages TS / B 3.9-3 and TS / B 3.9-4 1 Pages B 3.9-5 through B 3.9-30 0 B 3.10 SPECIAL OPERATIONS BASES Page TS / B 3.10-1 1 Pages B 3.10-2 through B 3.10-32 0 Page TS / B 3.10-33 1 Pages B 3.10-34 through B 3.10-38 0 Page TS lB 3.10-39 . 1 TSB2 text LOES 917/04 SUSQUEHANNA - UNIT 2 TS / B LOES-5 Revision 48
PPL Rev. 1 SGT System B 3.6.4.3 B 3.6 CONTAINMENT SYSTEMS B 3.6.4.3 Standby Gas Treatment (SGT) System BASES BACKGR( )UND The SGT System is required by 10 CFR 50, Appendix A, GDC 41, "Containment Atmosphere Cleanup" (Ref. 1). The safety function of the SGT System is to ensure that radioactive materials that leak from the primary containment into the secondary containment following a Design Basis Accident (DBA) are filtered and adsorbedfniorto exhausting to the environment.
The SGT System consists of two redundantsubsystems, each with its own set of dampers, filter train, a recirculation fan, and associated dampers and controls. X Each filter train consists of (cdmponents listed in order of the direction of the air flow):
- a. A demister,
- b. An electnc heater;
- c. A prefilt
- g. A centrifugal fan.
The sizing of the SGT System equipment and components is based on handling an incoming air mixture at a maximum of 125oF. The internal pressure of the secondary containment is maintained at a negative pressure of 0.25 inches water gauge when the system is in operation.
Maintenance of a negative pressure precludes direct od'tleakage.
The demister is provided to remove entrained water in the air, while the electric heater reduces the relative humidity of the airstream to less than 70% (Ref. 2). The prefilter removes large particulate matter, while the HEPA filter (continued)
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PPL Rev. 1 SGT System B 3.6.4.3 BASES BACKGROUND removes fine particulate matter and protects the charcoal from fouling. The (continued) charcoal adsorber removes gaseous elemental iodine and organic iodides, and the final HEPA filter collects any carbon fines exhausted from the charcoal adsorber.
The SGT System automatically starts and operates in response to actuation signals indicative of conditions or an accident that could require operation of the system. Following initiation in each division, the associated filter train fan starts. Upon verification that both subsystems are operating, the redundant subsystem may be shut down.
The SGT System also contains a cooling function to remove heat generated by fission product decay on the HEPA filters and charcoal adsorbers during shutdown of an SGT subsystem. The cooling function consists of two separate and independent filter cooling modes per SGT subsystem. The two cooling modes are:
- 1) Outside air damper and the filter cooling bypass damper open, allowing outside air to flow through the shutdown SGT subsystem's filter train and exit via the opposite SGT subsytem's exhaust fan.
- 2) Outside air damper opens and the SGT exhaust fan of the shutdown SGT subsystem starts. This configurations draws outside air through the shutdown SGT subsystem's filter train and exits via the associated SGT subsystem's exhaust fan.
APPLICABLE The design basis for the SGT System is to mitigate the consequences of a.
SAFETY loss of coolant accident and fuel handling accidents (Ref. 2). For all events ANALYSES analyzed, the SGT System is shown to be automatically initiated to reduce, via filtration and adsorption, the radioactive material released to the environment.
The SGT System satisfies Criterion 3 of the NRC Policy Statement (Ref. 3).
LCO Following a DBA, a minimum of one SGT subsystem is required to maintain the secondary containment at a negative pressure with respect to the environment and to process gaseous releases. Meeting the LCO requirements for two OPERABLE subsystems ensures operation of at least (continued)
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PPL Rev. 1 SGT System B 3.6.4.3 BASES LCO one SGT subsystem in the event of a single active failure. A SGT (continued) subsystem is considered OPERABLE when it has an OPERABLE set of dampers, filter train, recirculation fan and associated dampers, and associated controls. This includes the components required for at least one of the two SGTS filter cooling modes. I APPLICABILITY In MODES 1, 2, and 3, a DBA could lead to a fission product release to primary containment that leaks to secondary containment. Therefore, SGT System OPERABILITY is required during these MODES.
In MODES 4 and 5, the probability and consequences of these events are reduced due to the pressure and temperature limitations in these MODES.
Therefore, maintaining the SGT System in OPERABLE status is not required in MODE 4 or 5, except for other situations under which significant releases of radioactive material can be postulated, such as during operations with a potential for draining the reactor vessel (OPDRVs), during CORE ALTERATIONS, or during movement of irradiated fuel assemblies in the secondary containment.
ACTIONS A.1 With one SGT subsystem inoperable, the inoperable subsystem must be restored to OPERABLE status in 7 days. In this Condition, the remaining OPERABLE SGT subsystem is adequate to perform the required radioactivity release control function. However, the overall system reliability is reduced because a single failure in the OPERABLE subsystem could result in the radioactivity release control function not being adequately performed. The 7 day Completion Time is based on consideration of such factors as the availability of the OPERABLE redundant SGT System and the low probability of a DBA occurring during this period.
B.1 and B.2 If the SGT subsystem cannot be restored to OPERABLE status within the required Completion Time in MODE 1, 2, or 3, the plant must be brought to a MODE in which the LCO does not apply. To achieve this status, the plant must be brought to at least MODE 3 within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and to MODE 4 within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />. The allowed Completion Times are reasonable, based on (continued)
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PPL Rev. 1 SGT System B 3.6.4.3 BASES ACTIONS B.1 and B.2 (continued) operating experience, to reach the required plant conditions from full power conditions in an orderly manner and without challenging plant systems.
C.1, C.2.1. C.2.2. and C.2.3 During movement of irradiated fuel assemblies, in the secondary containment, during CORE ALTERATIONS, or during OPDRVs, when Required. Action A.I cannot be completed within the required Completion Time, the OPERABLE SGT filter train should immediately be placed in operation. This action ensures that the remaining filter.train is OPERABLE, that no failures that could prevent automatic actuation have occurred, and that any other failure would be readily detected.
An alternative to Required Action C.A is to immediately suspend activities that represent a potential for releasing radioactive material to the secondary containment, thus placing the plant in a condition that minimizes risk. If applicable, CORE ALTERATIONS and movement of irradiated fuel assemblies must immediately be suspended. Suspension of these activities must not preclude completion of movement of a component to a safe position. Also, if applicable, actions must immediately be initiated to suspend OPDRVs in order to minimize the probability of a vessel draindown and subsequent potential for fission
- product release. Actions must continue until OPDRVs'are suspended.
The Required Actions of Condition C have been modified by a Note stating that LCO 3.0.3 is not applicable. If moving irradiated fuel assemblies while in MODE 4 or 5, LCO 3.0.3 would not specify any action.
If moving irradiated fuel assemblies while in MODE 1, 2, or 3, the fuel movement is independent of reactor operations. Therefore, in either case, inability to suspend movement of irradiated fuel, assemblies would not be a sufficient reason to require a reactor shutdown.
D.1
. ~..
If both SGT subsystems are inoperable in MODE 1, 2, or 3, the SGT system may not be capable of supporting the required radioactivity release control function. The 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> Completion Time provides a period of time to correct (continued)
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PPL Rev. 1 SGT System B 3.6.4.3 BASES ACTIONS D.1 (continued) the problem that is commensurate with the importance of maintaining the SGT System contribution to secondary containment during MODES 1, 2, and 3. This time period also ensures that the probability of an accident (requiring SGT OPERABILITY) occurring during periods where SGT is inoperable is minimal.
E.1 and E.2 If at least one SGT subsystem cannot be restored to OPERABLE status within the required Completion Time, the plant must be brought to a MODE in which the LCO does not apply. . To achieve this status, the plant must be brought to at least MODE 3 within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and to MODE 4 within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />. The allowed Completion Times are reasonable, based on operating experience, to reach the required plant conditions from full power conditions in an orderly manner and without challenging plant systems.
F.1. F.2. and F.3 When two SGT subsystems are inoperable, if applicable, CORE ALTERATIONS and movement of irradiated fuel assemblies in secondary containment must immediately be suspended. Suspension of these activities shall not preclude completion of movement of a component to a safe position. Also, if applicable, actions must immediately be initiated to suspend OPDRVs in order to minimize the probability of a vessel draindown and subsequent potential for fission product release. Actions must continue until OPDRVs are suspended.
Required Action F.1 has been modified by a Note stating that LCO 3.0.3 is not applicable. If moving irradiated fuel assemblies while in MODE 4 or 5, LCO 3.0.3 would not specify any action. If moving irradiated fuel assemblies while in MODE 1, 2, or 3, the fuel movement is independent of reactor operations. Therefore, in either case, inability to suspend movement of irradiated fuel assemblies would not be a6sufficient reason to require a reactor shutdown.
(continued)
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I PPL Rev. I SGT System B 3.6.4.3 BASES (continued)
SURVEILLANCE SR 3.6.4.3.1 REQUIREMENTS Operating each SGT filter train for> 10 continuous hours ensures that both filter train are OPERABLE and that all associated controls are functioning properly. It also ensures that blockage, fan or motor failure, or excessive vibration can be detected for corrective action. Operation with the heaters on (automatic heater cycling to maintain temperature) for 2 10 continuous hours every 31 days eliminates moisture on the adsorbers and HEPA filters. The 31 day Frequency is consistent with the requirements of Reference 4.
SR 3.6.4.3.2 This SR verifies that the required SGT filter testing is performed in accordance with the Ventilation Filter Testing Program (VFTP). The VFTP includes testing HEPA filter performance, charcoal adsorber efficiency, minimum system flow rate, and the physical properties of the activated charcoal (general use and following specific operations). Specific test frequencies and additional information are discussed in detail in the VFTP.
SR 3.6.4.3.3 This SR verifies that each SGT subsystem starts on receipt of an actual or simulated initiation signal. While this Surveillance can'be performed with the reactor at power, operating experience has shown that these components usually pass the Surveillance when performed at the 24 month Frequency. The LOGIC SYSTEM FUNCTIONAL TEST in
-SR 3.3.6.2.5 overlaps this SR to providebcomplete testing of the safety function. Therefore, the Frequency was found to be acceptable from a reliability standpoint.
SR 3.6.4.3.4 This SR verifies that both cooling modes for each SGT subsystem are available. Although both cooling modes are tested, only one cooling mode for each SGT subsystem is required for an SGT subsystem to be considered OPERABLE. While this Surveillance can be performed with the reactor at power, operating experience has shown that these components usually pass the Surveillance when performed at the 24 month Frequency, which is based on the refueling cycle. Therefore, the Frequency was found to be acceptable from a reliability standpoint.
(continued)
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PPL Rev. 1 SGT System B 3.6.4.3 K-1)
BASES (continuec 1)
REFERENCES 1. 10 CFR 50, AppendixA, GDC 41.
- 2. FSAR, Section 6.5.1 I
- 3. Final Policy Statement on Technical Specifications Improvements, July 22, 1993 (58 FR 39132).
- 4. Regulatory Guide 1.52, Rev. 2.
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