ML12033A128
| ML12033A128 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 01/16/2012 |
| From: | Gerlach R Susquehanna |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| Download: ML12033A128 (23) | |
Text
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MANUAL HARD COPY DISTRIBUTION DOCUMENT TRANSMITTAL 2012-2503 USER INFORMATION:
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4-'-
SSES MANUAL Manual Name:
TSB2 Manual
Title:
TECHNICAL SPECIFICATIONS BA ES UNIT 2 MANUAL Table Of Contents Issue Date:
01/13/2012 procedure Name Rev TEXT LOES 105
Title:
LIST OF EFFECTIVE SECTIONS Issue Date 01/13/2012 Change ID Change Number TEXT TOC
Title:
TABLE OF CONTENTS 18 09/01/2010 TEXT 2.1.1 4
05/06/2009
Title:
SAFETY LIMITS (SLS)
REACTOR CORE SLS TEXT 2.1.2 1
10/04/2007
Title:
SAFETY LIMITS (SLS)
PRESSURE SL TEXT 3.0 3
Title:
LIMITING CONDITION FOR OPERATION (1CO)
APPLICABILITY TEXT 3.1.1 1
03/24/2005
Title:
REACTIVITY CONTRO,. SYSTEMS SHUTDOWN MARGIN (SDM)
TEXT 3.1.2
Title:
REACTIVITY C9-ROL SYSTEMS TEXT 3.1.3 2
Title:
E IV*
ONTROL SYSTEMS 11/18/2002 REACTIVITY ANOMALIES 01/19/2009 CONTROL ROD OPERABILITY TEXT 3.1.4 4
01/30/2009
Title:
REACTIVITY CONTROL SYSTEMS CONTROL ROD SCRAM TIMES TEXT 3.1.5 1
Title:
REACTIVITY CONTROL SYSTEMS TEXT,3.1.6 2
Title:
REACTIVITY CONTROL SYSTEMS 07/06/2005 CONTROL ROD SCRAM ACCUMULATORS 03/24/2005 ROD [.TTERN CONTROL Pagel of 8
Report Date: 01/16/1 Page -1 of 8 Report Date: 01/16/1
SSES MANUAL Manual Name:
TSB2 Manual
Title:
TECHNICAL SPECIFICATIONS BASES UNIT 2 MANUAL TEXT 3.1.7
Title:
REACTIVITY CONTROL 3
10/04/2007 SYSTEMS STANDBY LIQUID CONTROL (SLC)
SYSTEM TEXT 3.1.8 3
05/06/2009
Title:
REACTIVITY CONTROL SYSTEMS SCRAM DISCHARGE VOLUME (SDV)
VENT AND DRAIN VALVES TEXT 3.2,1
Title:
POWER DISTRIBUTION TEXT 3.2.2
Title:
POWER DISTRIBUTION 4
05/06/2009 LIMITS AVERAGE PLANAR LINEAR HEAT GENERATION RATE (APLHGR) 3 05/06/2009 LIMITS MINIMUM CRITICAL POWER RATIO (MCPR)
TEXT 3.2.3 2
05/06/2009
Title:
POWER DISTRIBUTION LIMITS LINEAR HEAT GENERATION RATE LHGR TEXT 3.3.1.1
Title:
INSTRUMENTATION TEXT 3.3.1.2
Title:
INSTRUMENTATION 4
05/06/2009 REACTOR PROTECTION SYSTEM (RPS)
INSTRUMENTATION 2
01/19/2009 SOURCE RANGE MONITOR (SRM)
INSTRUMENTATION TEXT 3.3.2.1 2
04/09/2007
Title:
INSTRUMENTATION CONTROL ROD BLOCK INSTRUMENTATION TEXT 3.3.2.2 1
05/06/2009
Title:
INSTRUMENTATION FEEDWATER -
MAIN TURBINE HIGH WATER LEVEL TRIP INSTRUMENTATION TEXT 3.3.3.1 7
10/27/2008
Title:
INSTRUMENTATION POST ACCIDENT MONITORING (PAM)
INSTRUMENTATION TEXT 3.3.3.2 1
04/18/2005
Title:
INSTRUMENTATION REMOTE SHUTDOWN SYSTEM TEXT 3.3.4.1 1
05/06/2009
Title:
INSTRUMENTATION END OF CYCLE RECIRCULATION PUMP TRIP (EOC-RPT)
INSTRUMENTATION Page a of 8
Report Date: 01/16/12
SSES MANUAL Manual Name:
TSB2 Manual
Title:
TECHNICAL SPECIFICATIONS BASES UNIT 2 MANUAL 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
Title:
INSTRUMENTATION TEXT 3.3.5.2
Title:
INSTRUMENTATION TEXT 3.3.6.1
Title:
INSTRUMENTATION TEXT 3.3.6.2
Title:
INSTRUMENTATION TEXT 3.3.7.1
Title:
INSTRUMENTATION INSTRUMENTATION TEXT 3.3.8.1
Title:
INSTRUMENTATION 4
08/20/2009 EMERGENCY CORE COOLING SYSTEM (ECCS)
INSTRUMENTATION 0
11/18/2002 REACTOR CORE ISOLATION COOLING (RCIC)
SYSTEM INSTRUMENTATION 4
05/06/2009 PRIMARY CONTAINMENT ISOLATION INSTRUMENTATION 4
09/01/2010 SECONDARY CONTAINMENT ISOLATION INSTRUMENTATION 2
107 7/2008 CONTROL ROOM EMERGENCY OUTSIDE AIR SUPPLY (CREOAS)
SYSTEM 3
12/17/2007 LOSS OF 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
Title:
REACTOR COOLANT TEXT 3.4.2
Title:
REACTOR COOLANT TEXT 3.4.3
Title:
07/20/2010 SYSTEM (RCS)
RECIRCULATION LOOPS OPERATING 2
07/20/2010 SYSTEM (RCS) JET PUMPS 3
01/13/2012 SYSTEM (RCS)
SAFETY/RELIEF VALVES (S/RVS)
TEXT 3.4.4 0
1l/18/2002
Title:
RCS OPERATIONAL LEAKAGE Page~
of 8 Report Date: 01/16/12 Page 3 of 8
Report Date: 01/16/12
SSES MANUAL Manual Name:
TSB2 Manual
Title:
TECHNICAL SPECIFICATIONS BASES UNIT 2 MANUAL TEXT 3.4.5
Title:
REACTOR COOLANT TEXT 3.4.6
Title:
REACTOR COOLANT TEXT 3.4.7
Title:
REACTOR COOLANT TEXT 3.4.8
Title:
REACTOR COOLANT HOT SHUTDOWN TEXT 3.4.9
Title:
REACTOR COOLANT COLD SHUTDOWN TEXT 3.4.10
Title:
REACTOR COOLANT TEXT 3.4.11
Title:
REACTOR COOLANT TEXT 3.5.1 3
03/10/2010 SYSTEM (RCS)
RCS PRESSURE ISOLATION VALVE (PIV) LEAKAGE 3
01/25/2011 SYSTEM (RCS)
RCS LEAKAGE DETECTION INSTRUMENTATION 2
10/04/2007 SYSTEM (RCS)
RCS SPECIFIC ACTIVITY 1
04/18/2005 SYSTEM (RCS)
SHUTDOWN COOLING SYSTEM SYSTEM 0
11/18/2002 (RCS)
SHUTDOWN COOL:
3 05/06/2009 (RCS)
RCS PRESSURE AND TEMPERATURE (P/T) LIMITS ING SYSTEM0 SYSTEM 0
11/18/2002 SYSTEM (RCS)
REACTOR STEAM DOME PRESSURE 3
01/16/2006
Title:
EMERGENCY CORE COOLING SYSTEMS (ECCS)
AND REACTOR SYSTEM ECCS -
OPERATING TEXT 3.5.2 0
11/18/2002
Title:
EMERGENCY CORE COOLING SYSTEMS (ECCS)
AND REACTOR SYSTEM ECCS -
SHUTDOWN TEXT 3.5.3 2
07/09/2010
Title:
EMERGENCY CORE COOLING SYSTEMS (ECCS)
AND REACTOR SYSTEM RCIC SYSTEM CORE ISOLATION COOLING (RCIC)
CORE ISOLATION COOLING (RCIC)
CORE ISOLATION COOLING (RCIC)
TEXT 3.6.1.1
Title:
11/09/2011 TEXT 3.6.1.2 1
05/06/2009
Title:
CONTAINMENT SYSTEMS PRIMARY CONTAINMENT AIR LOCK Page4 of 8 Report Date: 01/16/12 Page 4 of
.8 Report Date: 01/16/12
SSES MANUEAL Manual Name:
TSB2 Manual
Title:
TECHNICAL SPECIFICATIONS BASES UNIT 2 MANUAL TEXT 3.6.1.3
Title:
CONTAINMENT TEXT 3.6.1.4
Title:
CONTAINMENT TEXT 3.6.1.5
Title:
CONTAINMENT TEXT 3.6.1.6
Title:
CONTAINMENT TEXT 3.6.2.1
Title:
CONTAINMENT TEXT 3.6.2.2
Title:
CONTAINMENT TEXT 3.6.2.3
Title:
CONTAINMENT TEXT 3.6.2.4
Title:
CONTAINMENT TEXT 3.6.3.1
Title:
CONTAINMENT TEXT 3.6.3.2
Title:
CONTAINMENT TEXT 3.6.3.3
Title:
CONTAINMENT TEXT 3.6.4.1
Title:
CONTAINMENT 11 04/14/2010 SYSTEMS PRIMARY CONTAINMENT ISOLATION VALVES (PCIVS) 1 05/06/2009 SYSTEMS CONTAINMENT PRESSURE 1
10/05/2005 SYSTEMS DRYWELL AIR TEMPERATURE 0
11/18/2002 SYSTEMS SUPPRESSION CHAMBER-TO-DRYWELL VACUUM BREAKERS 2
12/17/2007 SYSTEMS SUPPRESSION POOL AVERAGE TEMPERATURE 0
11/18/2002 SYSTEMS SUPPRESSION POOL WATER LEVEL 1
01/16/2006 SYSTEMS RESIDUAL HEAT REMOVAL (RHR)
SUPPRESSION POOL COOLING 0
11/18/2002 SYSTEMS RESIDUAL HEAT REMOVAL (RHR)
SUPPRESSION POOL SPRAY 2
06/13/2006 SYSTEMS PRIMARY CONTAINMENT HYDROGEN RECOMBINERS 1
04/18/2005 SYSTEMS DRYWELL AIR FLOW SYSTEM 0
11/18/2002 SYSTEMS PRIMARY CONTAINMENT OXYGEN CONCENTRATION 7
1.0604/2007 SYSTEMS SECONDARY CONTAINMENT Page 5..
of 8
Report Date:
01/16/12 Page5 of
_8 Report Date: 01/16/12
SSES MANUAL Manual Name:
TSB2 Manual
Title:
TECHNICAL SPECIFICATIONS BASES UNIT 2 MANUAL TEXT 3.6.4.2 3
03/10/2010
Title:
CONTAINMENT SYSTEMS SECONDARY CONTAINMENT ISOLATION VALVES (SCIVS)
TEXT 3.6.4.3 4
09/21/2006
Title:
CONTAINMENT SYSTEMS STANDBY GAS TREATMENT (SGT)
SYSTEM TEXT 3.7.1
Title:
PLANT SYSTEMS ULTIMATE HEAT 4
04/05/2010 RESIDUAL HEAT REMOVAL SERVICE WATER (RHRSW)
SYSTEM AND THE SINK (UHS)
TEXT 3.7.2
Title:
PLANT TEXT 3.7.3
Title:
PLANT TEXT 3.7.4
Title:
PLANT TEXT 3.7.5
Title:
PLANT TEXT 3.7.6
Title:
PLANT TEXT 3.7.7
Title:
PLANT TEXT 3.8.1 2
05/02/2008 SYSTEMS EMERGENCY SERVICE WATER (ESW)
SYSTEM 1
01/08/2010 SYSTEMS CONTROL ROOM EMERGENCY OUTSIDE AIR SUPPLY (CREOAS)
SYSTEM 0
11/i8/2002 SYSTEMS CONTROL ROOM FLOOR COOLING SYSTEM 1
10/04/2007 SYSTEMS MAIN CONDENSER OFFGAS 3
01/25/2011 SYSTEMS MAIN TURBINE BYPASS SYSTEM 1
10/04/2007 SYSTEMS SPENT FUEL STORAGE POOL WATER LEVEL 8
05/06/2009
Title:
ELECTRICAL POWER SYSTEMS AC SOURCES -
OPERATING TEXT 3.7.8 0
05/06/2009
Title:
MAINE TURBINE PRESSURE REGULATION SYSTEM TEXT 3.8.2 0
i1/18/2002
Title:
ELECTRICAL POWER SYSTEMS AC SOURCES -
SHUTDOWN Page.~
of 8
Report Date: 01/16/12 Page 6 of 8
Report Date: 01/16/12
SSES MANUAL Manual Name:
TSB2 Manual
Title:
TECHNICAL SPECIFICATIONS BASES UNIT 2 MANUAL TEXT 3.8.3
Title:
ELECTRICAL TEXT 3.8.4
Title:
ELECTRICAL TEXT 3.8.5
Title:
ELECTRICAL TEXT 3.8.6
Title:
ELECTRICAL TEXT 3.8.7
Title:
ELECTRICAL TEXT 3.8.8
Title:
ELECTRICAL TEXT 3.9.1
Title:
REFUELING TEXT 3.9.2
Title:
REFUELING TEXT 3.9.3
Title:
REFUELING TEXT 3.9.4
Title:
REFUELING TEXT 3.9.5
Title:
REFUELING TEXT 3.9.6
Title:
REFUELING POWER SYST POWER SYST POWER SYST POWER SYST POWER SYST POWER SYST OPERATIONS OPERATIONS
)PERATIONS OPERATIONS
)PERATIONS
)PERATIONS 2
04/14/2010 EMS DIESEL FUEL OIL LUBE OIL AND STARTING AIR 3
01/19/2009 EMS DC SOURCES -
OPERATING 1
12/14/2006 EMS DC SOURCES -
SHUTDOWN 1
12/14/2006 EMS BATTERY CELL PARAMETERS 3
03/31/2006 EMS DISTRIBUTION SYSTEMS -
OPERATING 0
11/18/2002
'EMS DISTRIBUTION SYSTEMS -
SHUTDOWN 0
11/18/2002 REFUELING EQUIPMENT INTERLOCKS 1
09/01/2010 REFUEL POSITION ONE-ROD-OUT INTERLOCK 0
11/18/2002 CONTROL ROD POSITION 0
11/18/2002 CONTROL ROD POSITION INDICATION 0
11/18/2002 CONTROL ROD OPERABILITY -
REFUELING 1
10/04/2007 REACTOR PRESSURE VESSEL (RPV) WATER LEVEL Page2 of 8 Report Date: 01/16/12 Page 7 of 8
Report Date: 01/16/12
SSES MANUAL Manual Name:
TSB2 Manual
Title:
TECHNICAL SPECIFICATIONS BASES UNIT 2 MANUAL TEXT 3.9.7 0
11/18/2002
Title:
REFUELING OPERATIONS RESIDUAL HEAT REMOVAL (RHR)
HIGH WATER LEVEL TEXT 3.9.8 0
11/18/2002
Title:
REFUELING OPERATIONS RESIDUAL HEAT REMOVAL (RHR)
LOW WATER LEVEL TEXT 3.10.1
Title:
SPECIAL TEXT 3.10.2
Title:
SPECIAL TEXT 3.10.3
Title:
SPECIAL TEXT 3.10.4
Title:
SPECIAL TEXT 3.10.5
Title:
SPECIAL TEXT 3.10.6
Title:
SPECIAL TEXT 3.10.7
Title:
SPECIAL TEXT 3.10.8
Title:
SPECIAL OPERATIONS OPERATIONS OPERATIONS OPERATIONS OPERATIONS OPERATIONS OPERATIONS 1
01/23/2008 INSERVICE LEAK AND HYDROSTATIC TESTING OPERATION 0
11/18/2002 REACTOR MODE SWITCH INTERLOCK TESTING 0
11/18/2002 SINGLE CONTROL ROD WITHDRAWAL -
HOT SHUTDOWN 0
11/18/2002 SINGLE CONTROL ROD WITHDRAWAL -
COLD SHUTDOWN 0
11/18/2002 SINGLE CONTROL ROD DRIVE (CRD)
REMOVAL REFUELING 0
11/18/2002 MULTIPLE CONTROL ROD WITHDRAWAL.-
REFUELING 1
03/24/2005 CONTROL ROD TESTING -
OPERATING 2
04/09/2007 OPERATIONS SHUTDOWN MARGIN (SDM)
TEST -
REFUELING Page8 of 8 Report Date: 01/16/12 Page 8 of
.8 Report Date: 01/16/12
SUSQUEHANNA STEAM ELECTRIC STATION LIST OF EFFECTIVE SECTIONS (TECHNICAL SPECIFICATIONS BASES)
Section Title Revision TOC Table of Contents 18 B 2.0 SAFETY LIMITS BASES Page TS / B 2.0-1 1
Pages TS / B 2.0-2 and TS / B 2.0-3 4
Page TS / B 2.0-4 6
Pages TS / B 2.0-5 through TS / B 2.0-8 1
B 3.0 LCO AND SR APPLICABILITY BASES Page TS / B 3.0-1 1
Pages TS / B 3.0-2 through TS / B 3.0-4 0
Pages TS / B 3.0-5 through TS / B 3.0-7 1
Page TS / B 3.0-8 3
Pages TS / B 3.0-9 through Page TS / B 3.0-11 2
Page TS / B 3.0-1 la 0
Page TS / B 3.0-12 1
Pages TS / B 3.0-13 through TS / B 3.0-15 2
Pages TS / B 3.0-16 and TS / B 3.0-17 0
B 3.1 REACTIVITY CONTROL BASES Pages B 3.1-1 through B 3.1-4 0
Page TS / B 3.1-5 1
Pages TS / B 3.1-6 and TS / B 3.1-7 2
Pages B 3.1-8 through B 3.1-13 0
Page TS / B 3.1-14 1
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Page TS / B 3.1-16 1
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Pages TS / B 3.1-20 and TS / B 3.1-21 1
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Page TS / B 3.1-23 1
Page TS / B 3.1-24 0
Pages TS / B 3.1-25 through TS / B 3.1-27 1
Page TS / B 3.1-28 2
Page TS / 3.1-29 1
Pages B 3.1-30 through B 3.1-33 0
Pages TS / B 3.1.34 through TS / B 3.1-36 1
Pages TS / B 3.1-37 and TS / B 3.1-38 2
Pages TS / B 3.1-39 and TS / B 3.1-40 2
Page TS / B 3.1-40a 0
Page TS / B 3.1-41 1
Page TS / B 3.1-42 2
SUSQUEHANNA
- UNIT 2 TS / B LOES-1 Revision 105 SUSQUEHANNA - UNIT 2 TS / B LOES-1 Revision 105
SUSQUEHANNA STEAM ELECTRIC STATION LIST OF EFFECTIVE SECTIONS (TECHNICAL SPECIFICATIONS BASES)
Section Title Revision Pages TS / B 3.1-43 1
Page TS / B 3.1-44 0
Page TS / B 3.1-45 3
Page TS / B 3.1-46 0
Page TS / B 3.1-47 1
Pages TS / B 3.1-48 and TS / B 3.1-49 1
Page B 3.1-50 0
Page TS / B 3.1-51 3
B 3.2 POWER DISTRIBUTION LIMITS BASES Pages TS / B 3.2-1 and TS / B 3.2-2 2
Page TS / B 3.2-3 4
Page TS / B 3.2-4 1
Page TS / B 3.2-5 3
Page TS / B 3.2-6 4
Page TS / B 3.2-7 3
Pages TS / B 3.2-8 and TS / B 3.2-9 4
Pages TS / B 3.2-10 through TS / B 3.2-12 2
Page TS / B 3.2-13 1
B 3.3 INSTRUMENTATION Pages TS / B 3.3-1 through TS / B 3.3-4 1
Page TS / B 3.3-5 2
Page TS / B 3.3-6 1
Page TS / B 3.3-7 3
Page TS / B 3.3-8 4
Pages TS / B 3.3-9 through TS / B 3.3-13 3
Page TS / B 3.3-14 4
Pages TS / B 3.3-15 and TS / B 3.3-16 2
Pages TS / B 3.3-17 through TS / B 3.3-21 3
Pages TS / B 3.3-22 through TS / B 3.3-27 2
Page TS / B 3.3-28 3
Page TS / B 3.3-29 4
Pages TS / B 3.3-30 and TS / B 3.3-31 3
Pages TS / B 3.3-32 and TS / B 3.3-33 4
Page TS / B 3.3-34 2
Page TS / B 3.3-34a 1
Pages TS / B 3.3-34b through TS / B 3.3-34d 0
Page TS / B 3.3-34e 1
Pages TS / B 3.3-34f through TS / B 3.3-34i 0
Pages TS / B 3.3-35 and TS / B 3.3-36 2
Pages TS / B 3.3-37 and TS / B 3.3-38 1
SUSQUEHANNA
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SUSQUEHANNA STEAM ELECTRIC STATION LIST OF EFFECTIVE SECTIONS (TECHNICAL SPECIFICATIONS BASES)
Section Title Revision Page TS / B 3.3-39 2
Pages TS / B 3.3-40 through TS / B 3.3-43 2
Pages TS / B 3.3-44 through TS / B 3.3-54 3
Pages TS / B 3.3-54a through TS / B 3.3-54e 0
Page TS / B 3.3-55 1
Page B 3.3-56 0
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Pages B 3.3-60 through B 3.3-63 0
Pages TS / B 3.3-64 and TS / B 3.3-65 2
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Page TS / B 3.3-68 4
Page TS / B 3.3.69 5
Page TS / B 3.3-70 4
Page TS / B 3.3-71 3
Pages TS,/ B 3.3-72 and TS / B 3.3-73 2
Page TS / B 3.3-74 3
Page TS / B 3.3-75 2
Pages TS / B 3.3-75a and TS / B 3.3-75 b 6
Page TS / B 3.3-75c 5
Pages B 3.3-76 and TS / B 3.3-77 0
Page TS / B 3.3-78 1
Pages B 3.3-79 through B 3.3-81 0
Page TS / B 3.3-82 1
Page B 3.3-83 0
Pages TS / B 3.3-84 and TS / B 3.3-85 1
Page 3.3-86 0
Page TS / B 3.3-87 1
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Page TS / B 3.3-89 1
Pages B 3.3-90 and B 3.3-91 0
Pages TS / B 3.3-92 through TS / B 3.3-103 1
Page TS / B 3.3-104 3
Pages TS / B 3.3-105 and TS / B 3.3-106 1
Page TS / B 3.3-107 2
Page TS / B 3.3-108 1
Page TS / B 3.3-109 2
Pages TS / B 3.3-110 through TS / B 3.3-112 1
Page TS / B 3.3-113 2
Page TS / B 3.3-114 1
Page TS / B 3.3-115 2
Page TS / B 3.3-116 3
Pages TS / B 3.3-117 and TS / B 3.3-118 2
SUSQUEHANNA
- UNIT 2 TS/B LOES-3 Revision 105 SUSQUEHANNA - UNIT 2 TS / B LOES-3 Revision 105
SUSQUEHANNA STEAM ELECTRIC STATION LIST OF EFFECTIVE SECTIONS (TECHNICAL SPECIFICATIONS BASES)
Section Title Revision 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 / B 3.3-124 2
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Page TS / B 3.3-125 1
Page TS / B 3.3-126 2
Page TS / B 3.3-127 3
Page TS / B 3.3-128 2
Pages TS / B 3.3-129 through TS / B 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 and TS / B 3.3-151 1
Pages TS / B 3.3-152 through TS / B 3.3-154 2
Page TS / B 3.3-155 1
Pages TS / B 3.3-156 through TS / 8 3.3-158 2
Pages TS / B 3.3-159 through TS / B 3.3-161 1
Page TS / B 3.3-162 1
Page TS / B 3.3-163 2
Page TS / B 3.3-164 1
Pages TS / B 3.3-165 and TS / B 3.3-166 2
Pages TS / B 3.3-167 and TS / B 3.3-168 1
Pages TS / B 3.3-169 and TS /B 3.3-170 2
Pages TS / B 3.3-171 through TS / B 3.3-177 1
Page TS / B 3.3-178 2
Page TS / B 3.3-179 3
Page TS / B 3.3-179a 2
Page TS / B 3.3-180 1
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Pages TS / B 3.3-187 and TS / 83.3-188 2
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Page TS / B 3.3-193 1
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Page TS / B 3.3-196 2
SUSQUEHANNA
- UNIT 2 TS/B LOES-4 Revision 105 SUSQUEHANNA - UNIT 2 TS / B LOES-4 Revision 105
SUSQUEHANNA STEAM ELECTRIC STATION LIST OF EFFECTIVE SECTIONS (TECHNICAL SPECIFICATIONS BASES)
Section Title Revision Pages TS / B 3.3-197 through TS / B 3.3-205 0
Page TS / B 3.3-206 1
Pages B 3.3-207 through B 3.3-209 0
Page TS / B 3.3-210 1
Page TS / B 3.3-211 2
Pages TS / B 3.3-212 and TS / B 3.3-213 1
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TSB2 Text LOES.doc 1/10/2012 SUSQUEHANNA - UNIT 2 TS / B LOES-9 Revision 105
PPL Rev. 3 S/RVs B 3.4.3 B 3.4 REACTOR COOLANT SYSTEM (RCS)
B 3.4.3 Safety/Relief Valves (S/RVs)
BASES BACKGROUND The ASME Boiler and Pressure Vessel Code requires the reactor pressure vessel be protected from overpressure during upset conditions by self-actuated safety valves. As part of the nuclear pressure relief system, the size and number of S/RVs are selected such that peak pressure in the nuclear system will not exceed the ASME Code limits for the reactor coolant pressure boundary (RCPB).
The S/RVs are located on the main steam lines between the reactor vessel and the first isolation valve within the drywell. There are a total of 16 S/RVs of which any 14 are required to be OPERABLE. The S/RVs can actuate by either of two modes: the safety mode or the relief mode. In the safety mode (or spring mode of operation), the valve opens when steam pressure at the valve inlet overcomes the spring force holding the valve closed. This satisfies the Code requirement.
Each S/RV discharges steam through a discharge line to a point below the minimum water level in the suppression pool. Six S/RVs also serve as the Automatic Depressurization System (ADS) valves. The ADS requirements are specified in LCO 3.5.1, "ECCS-Operating."
APPLICABLE SAFETY ANALYSES The overpressure protection system must accommodate the most severe pressurization transient. Evaluations have determined that the most severe transient is the closure of all main steam isolation valves (MSIVs),
followed by reactor scram on high neutron flux (i.e., failure of the direct scram associated with MSIV position) (Ref. 1). For the purpose of the analyses, 14 of the 16 S/RVs are assumed to operate in the safety mode.
The analysis results demonstrate that the design S/RV capacity is capable of maintaining reactor pressure below the ASME Code limit of 110% of vessel design pressure (110% x 1250 psig = 1375 psig). This LCO helps to ensure that the acceptance limit of 1375 psig is met during the Design Basis Event.
(continued)
SUSQUEHANNA - UNIT 2 TS /B 3.4-15 Revision 2
PPL Rev. 3 S/RVs B 3.4.3 BASES APPLICABLE From an overpressure standpoint, the design basis events are bounded SAFETY by the MSIV closure with flux scram event described above. Reference 2 ANALYSES discusses additional events that are expected to actuate the S/RVs.
(continued)
S/RVs satisfy Criterion 3 of the NRC Policy Statement (Ref. 4).
LCO The safety function of 14 of the 16 S/RVs are required to be OPERABLE to satisfy the assumptions of the safety analysis (Refs. 1 and 2). The requirements of this LCO are applicable only to the capability of the S/RVs to mechanically open to relieve excess pressure when the lift setpoint is exceeded (safety function).
The S/RV setpoints are established to ensure that the ASME Code limit on peak reactor pressure is satisfied. The ASME Code specifications require the lowest safety valve setpoint to be at or below vessel design pressure (1250 psig) and the highest safety valve to be set so that the total accumulated pressure does not exceed 110% of the design pressure for overpressurization conditions. The transient evaluations in the FSAR are based on these setpoints, but also include the additional uncertainty of + 3%, - 5 % of the nominal setpoint to provide an added degree of conservatism.
Operation with fewer valves OPERABLE than specified, or with setpoints outside the ASME limits, could result in a more severe reactor response to a transient than predicted, possibly resulting in the ASME Code limit on reactor pressure being exceeded.
APPLICABILITY In MODES 1, 2, and 3, all required S/RVs must be OPERABLE, since considerable energy may be in the reactor core and the limiting design basis transients are assumed to occur in these MODES. The S/RVs may be required to provide pressure relief to discharge energy from the core until such time that the Residual Heat Removal (RHR) System is capable of dissipating the core heat.
In MODE 4 reactor pressure is low enough that the overpressure limit is unlikely to be approached by assumed (continued)
SUSQUEHANNA - UNIT 2 TS / B 3.4-16 Revision 4
PPL Rev. 3 S/RVs B 3.4.3 BASES APPLICABILITY operational transients or accidents. In MODE 5, the reactor vessel head is (continued) unbolted or removed and the reactor is at atmospheric pressure. The S/RV function is not needed during these conditions.
ACTIONS A.1 and A.2 With less than the minimum number of required S/RVs OPERABLE, a transient may result in the violation of the ASME Code limit on reactor pressure. If the safety function of one or more required S/RVs is inoperable, 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 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 required plant conditions from full power conditions in an orderly manner and without challenging plant systems.
SURVEILLANCE SR 3.4.3.1 REQUIREMENT The Surveillance requires that the required S/RVs will open at the pressures assumed in the safety analysis of Reference 1. The demonstration of the S/RV safe lift settings must be performed during shutdown, since this is a bench test, to be done in accordance with the Inservice Testing Program. The lift setting pressure shall correspond to ambient conditions of the valves at nominal operating temperatures and pressures. The S/RV setpoint is + 3%, - 5% of the nominal setpoint for OPERABILITY. Requirements for accelerated testing are established in accordance with the Inservice Test Program. Any of the 16 S/RVs, identified in this Surveillance Requirement, with their associated setpoints, can be designated as the 14 required S/RVs. This maintains the assumptions in the overpressure analysis.
A Note is provided to allow up to two of the required 14 S/RVs to be physically replaced with S/RVs with lower setpoints until the next refueling outage. This provides operational flexibility which maintains the assumptions in the over-pressure analysis.
(continued)
SUSQUEHANNA - UNIT 2 TS / B 3.4-17 Revision 4
PPL Rev. 3 S/RVs B 3.4.3 BASES SURVEILLANCE SURVEQIR NENS SR 3.4.3.1 (continued)
REQUIREMENTS The Frequency of this Surveillance is established in accordance with the Inservice Testing Program.
REFERENCES
- 1. FSAR, Section 5.2.2.1.4.
- 2. FSAR, Section 15.
- 3. ASME Operation and Maintenance Code.
- 4. Final Policy Statement on Technical Specifications Improvements, July 22, 1993 (58 FR 39132).
SUSQUEHANNA - UNIT 2 TS / B 3.4-18 Revision 2