ML062850519
| ML062850519 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 10/02/2006 |
| From: | Susquehanna |
| To: | Gerlach R Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| TSB1, Rev 11 | |
| Download: ML062850519 (27) | |
Text
Oct.
02, 2006 Page 1
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SSES MANUAL j Manual Name:
TSBI-inual
Title:
TECHNICAL SPECIFICATION BASES UNIT 1 MANUAL Table Of Contents Issue Date:
09/29/2006 Procedure Name Rev TEXT LOES 78
Title:
LIST OF EFFECTIVE SECTIONS Issue Date 09/29/2006 Change ID Change Number TEXT TOC
Title:
TABLE OF CONTENTS 11 09/29/2006 TEXT 2.1.1 2
Title:
SAFETY LIMITS (SLS)
REACTOR TEXT 2.1.2 0
Title:
SAFETY LIMITS (SLS)
REACTOR 04/18/2006 CORE SLS 11/15/2002 COOLANT SYSTEM (RCS) 'PRESSURE SL TEXT 3.0 1
04/18/2005
Title:
LIMITING CONDITION FOR OPERATION *(LCO)
APPLICABILITY TEXT 3.1.1
Title:
REACTIVITY TEXT 3.1.2
Title:
REACTIVITY TEXT 3.1.3
Title:
REACTIVITY TEXT 3.1.4
Title:
REACTIVITY TEXT 3.1.5
Title:
REACTIVITY TEXT 3.1.6
Title:
REACTIVITY CONTROL SYSTEMS 04718/2006 SHUTDOWN MARGIN (SDM)
.0 11/15/2002 CONTROL SYSTEMS REACTIVITY ANOMALIES 1
07/06/2005 CONTROL SYSTEMS CONTROL ROD OPERABILITY 3
CONTROL SYSTEMS 09/29/2006 CONTROL ROD SCRAM TIMES 1
07/06/2005 CONTROL SYSTEMS CONTROL ROD SCRAM ACCUMULATORS 2
CONTROL SYSTEMS 04/18/2006 ROD PATTERN CONTROL Pagel of 8
Report Date: 09/29/06 Page I of 8 Report Date: 09/29/06
SSES MANUAL Manual Name:
TSBI-Manual
Title:
TECHNICAL SPECIFICATION BASES UNIT 1 MANUAL TEXT 3.1.7 1
08/30/2005
Title:
REACTIVITY CONTROL SYSTEMS STANDBY LIQUID CONTROL (SLC)
SYSTEM TEXT 3.1.8
Title:
REACTIVITY CONTROL 1
10/19/2005 SYSTEMS SCRAM DISCHARGE VOLUME (SDV)
VENT AND DRAIN VALVES TEXT 3.2.1 1
04/18/2006
Title:
POWER DISTRIBUTION LIMITS AVERAGE PLANAR LINEAR HEAT GENERATION RATE (APLHGR)
TEXT 3.2.2 1
04/18/2006
Title:
POWER DISTRIBUTION LIMITS MINIMUM CRITICAL POWER RATIO (MCPR)
TEXT 3.2.3 0
11/15/2002
Title:
POWER DISTRIBUTION LIMITS LINEAR HEAT GENERATION RATE (LHGR)
TEXT 3.2.4 2
04/12/2006
Title:
POWER DISTRIBUTION LIMITS AVERAGE POWER RANGE MONITOR (APRM)
GAIN AND SETPOINTS K>
TEXT 3.3.1.1
Title:
INSTRUMENTATION 3
04/12/2006 REACTOR PROTECTION SYSTEM (RPS)
INSTRUMENTATION TEXT 3.3.1.2 1
04/12/2006
Title:
INSTRUMENTATION SOURCE RANGE MONITOR (SRM)
INSTRUMENTATION TEXT 3.3.2.1 2
04/12/2006
Title:
INSTRUMENTATION CONTROL ROD BLOCK INSTRUMENTATION TEXT 3.3.2.2 0
11/15/2002
Title:
INSTRUMENTATION FEEDWATER -
MAIN TURBINE HIGH WATER LEVEL TRIP INSTRUMENTATION TEXT 3.3.3.1 5
06/13/2006
Title:
INSTRUMENTATION POST ACCIDENT MONITORING (PAM)
INSTRUMENTATION TEXT 3.3.3.2
Title:
INSTRUMENTATION Page 2 of 8
1 04/18/2005 REMOTE SHUTDOWN SYSTEM Report Date: 09/29/06
SSES MANUAL Manual Name:
TSBI-Manual
Title:
TECHNICAL SPECIFICATION BASES UNIT 1 MANUAL TEXT 3.3.4.1 0
11/15/2002
Title:
INSTRUMENTATION END OF CYCLE RECIRCULATION PUMP TRIP (EOC-RPT)
INSTRUMENTATION TEXT 3.3.4.2 0
11/15/2002
Title:
INSTRUMENTATION ANTICIPATED TRANSIENT WITHOUT SCRAM RECIRCULATION PUMP TRIP (ATWS-RPT)
INSTRUMENTATION TEXT 3.3.5.1 2
07/06/2005
Title:
INSTRUMENTATION EMERGENCY CORE COOLING SYSTEM (ECCS)
INSTRUMENTATION TEXT 3.3.5.2
.0.
11/15/2002
Title:
INSTRUMENTATION REACTOR CORE ISOLATION COOLING (RCIC)
SYSTEM INSTRUMENTATION TEXT 3.3.6.1
Title:
INSTRUMENTATION TEXT 3.3.6.2
Title:
INSTRUMENTATION TEXT 3.3.7.1
Title:
INSTRUMENTATION INSTRUMENTATION 1
11/09/2004 PRIMARY CONTAINMENT'ISOLATION INSTRUMENTATION 1
11/09/2004 SECONDARY CONTAINMENT ISOLATION INSTRUMENTATION 0
11/15/2002 CONTROL ROOM EMERGENCY OUTSIDE AIR SUPPLY (CREOAS)
SYSTEM TEXT 3.3.8.1 1
09/02/2004
Title:
INSTRUMENTATION LOSS OF POWER (LOP)
INSTRUMENTATION TEXT 3.3.8.2
Title:
INSTRUMENTATION 0
11/15/2002 REACTOR PROTECTION SYSTEM (RPS)
ELECTRICPOWER MONITORING TEXT 3.4.1 3
04/12/2006
Title:
RECIRCULATION LOOPS OPERATING TEXT 3.4.2
Title:
-TEXT 3.4.3
Title:
11/15/2002 SYSTEM (RCS)
JET PUMPS 1
01/16/2006 SYSTEM (RCS)
SAFETY/RELIEF VALVES (S/RVS)
Page3 of 8 Report Date: 09/29/06 Page 3 of 8
Report Date: 09/29/06
SSES MANUAL 4-Manual Name:
TSBI-Manual
Title:
TECHNICAL SPECIFICATION BASES UNIT 1 MANUAL TEXT 3.4.4
Title:
REACTOR-COOLANT 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 0
11/15/2002 SYSTEM (RCS)
01/16/2006 SYSTEM (RCS)
RCS PRESSURE ISOLATION VALVE (PIV) LEAKAGE 1
04/18/2005 SYSTEM (RCS)
RCS LEAKAGE DETECTION INSTRUMENTATION 1
04/18/2005 SYSTEM (RCS)
RCS SPECIFIC ACTIVITY 1
04/18/2005 SYSTEM (RCS)
SHUTDOWN COOLING SYSTEM 0
11/15/2002 SYSTEM (RCS)
SHUTDOWN COOLING SYSTEM 2
05/10/2006 SYSTEM (RCS)
RCS PRESSURE AND TEMPERATURE (P/T) LIMITS.
0 11/15/2002 SYSTEM (RCS)
REACTOR STEAM DOME PRESSURE 2
01/16/2006
Title:
EMERGENCY CORE COOLING SYSTEMS (ECCS)
AND REACTOR CORE ISOLATION SYSTEM ECCS -
OPERATING TEXT 3.5.2 0
11/15/2002
Title:
EMERGENCY CORE COOLING SYSTEMS (ECCS)
AND REACTOR CORE ISOLATION SYSTEM ECCS SHUTDOWN TEXT 3.5.3 1
04/18/2005
Title:
EMERGENCY CORE COOLING SYSTEMS (ECCS)
AND REACTOR CORE ISOLATION SYSTEM RCIC SYSTEM COOLING (RCIC)
COOLING (RCIC)
COOLING (RCIC)
TEXT 3.6.1.1 0
11/15/2002
Title:
CONTAINMENT SYSTEMS PRIMARY CONTAINMENT Page 4 of 8 Report Date: 09/29/06 Page 4 of 8 Report Date: 09/29/06
SSES MANUAL Manual Name:
TSBI-Manual
Title:
TECHNICAL SPECIFICATION BASES UNIT 1 MANUAL TEXT 3.6.1.2
Title:
CONTAINMENT 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 0
11/15/2002 SYSTEMS PRIMARY CONTAINMENT AIR LOCK 3
12/08/2005 SYSTEMS PRIMARY CONTAINMENT ISOLATION VALVES (PCIVS) 0 11/15/2002 SYSTEMS CONTAINMENT PRESSURE 1
10/05/2005 SYSTEMS DRYWELL AIR TEMPERATURE 0
11/15/2002 SYSTEMS SUPPRESSION CHAMBER-TO-DRYWELL VACUUM BREAKERS 0
11/15/2002 SYSTEMS SUPPRESSION POOL AVERAGE TEMPERATURE 0
11/15/2002 SYSTEMS SUPPRESSION POOL WATER LEVEL 1
01/16/2006 SYSTEMS RESIDUAL HEAT'REMOVAL (RHR)
SUPPRESSION POOL COOLING 0
11/15/2002 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
11/15/2002 SYSTEMS PRIMARY CONTAINMENT OXYGEN CONCENTRATION PageS of 8
Report Date: 09/29/06 Page 5 of 8
Report Date: 09/29/06
SSES MANUAL Manual Name:
TSBI-Manual
Title:
TECHNICAL SPECIFICATION BASES UNIT 1 MANUAL TEXT 3.6.4.1 6
08/08/2006
Title:
CONTAINMENT SYSTEMS SECONDARY CONTAINMENT TEXT 3.6.4.2 2
01/03/2005
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
'ii TEXT 3.7.1
Title:
PLANT SYSTEMS ULTIMATE HEAT 0
11/15/2002 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 1
11/09/2004 SYSTEMS EMERGENCY SERVICE WATER (ESW)
SYSTEM 0
11/15/2002 SYSTEMS CONTROL ROOM EMERGENCY OUTSIDE AIR SUPPLY (CREOAS)
SYSTEM 0
11/15/2002 SYSTEMS CONTROL ROOM FLOOR COOLING SYSTEM 0
11/15/2002 SYSTEMS MAIN CONDENSER OFFGAS 1
01/17/2005 SYSTEMS MAIN TURBINE BYPASS SYSTEM 0
11/15/2002 SYSTEMS SPENT FUEL STORAGE POOL WATER LEVEL 4
04/18/2006 K)
Title:
ELECTRICAL POWER SYSTEMS AC SOURCES -
OPERATING TEXT 3.8.2 0
11/15/2002
Title:
ELECTRICAL POWER SYSTEMS AC SOURCES -
SHUTDOWN Page 6 of 8
Report Date: 09/29/06
SSES MANUAL Manual Name:
TSBI-Manual
Title:
TECHNICAL SPECIFICATION BASES UNIT 1 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 C TEXT 3.9.2
Title:
REFUELING C TEXT 3.9.3
Title:
REFUELING C TEXT 3.9.4
Title:
REFUELING C TEXT 3.9.5
Title:
REFUELING C TEXT 3.9.6
Title:
REFUELING C POWER SYST POWER SYST POWER SYST POWER SYST POWER SYST POWER SYST
)PERATIONS
)PERATIONS
)PERATIONS
)PERATIONS
)PERATIONS
)PERATIONS 0
11/15/2002
'EMS DIESEL FUEL OIL, LUBE OIL, AND STARTING AIR 1
06/13/2006
'EMS DC SOURCES -
OPERATING 0
11/15/2002
'EMS DC SOURCES -
SHUTDOWN 0
11/15/2002
'ENS BATTERY CELL PARAMETERS 1
10/05/2005
'EMS DISTRIBUTION SYSTEMS -
OPERATING 0
11/15/2002
'EMS DISTRIBUTION SYSTEMS -
SHUTDOWN 0
11/15/2002 REFUELING EQUIPMENT INTERLOCKS 0
11/15/2002 REFUEL POSITION ONE-ROD-OUT INTERLOCK 0
11/15/2002 CONTROL ROD POSITION 0
11/15/2002 CONTROL ROD POSITION INDICATION 0
11/15/2002 CONTROL ROD OPERABILITY REFUELING.
0 11/15/2002 REACTOR PRESSURE VESSEL (RPV)
WATER LEVEL Page7 of 8 Report Date: 09/29/06 Page 7 of 8 Report Date: 09/29/06
SSES MANUAL Manual Name:
TS=-
Manual
Title:
TECHNICAL SPECIFICATION BASES UNIT 1 MANUAL TEXT 3.9.7 0
11/15/2002
Title:
REFUELING OPERATIONS RESIDUAL HEAT REMOVAL (RHR)
HIGH WATER LEVEL TEXT 3.9.8 0
11/15/2002
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 0
11/15/2002 INSERVICE LEAK AND HYDROSTATIC TESTING OPERATION
.0.
11/15/2002 REACTOR MODE SWITCH INTERLOCK TESTING 0
11/15/2002 SINGLE CONTROL ROD WITHDRAWAL HOT SHUTDOWN 0
11/15/2002 SINGLE CONTROL ROD WITHDRAWAL -
COLD SHUTDOWN 0
11/15/2002 OPERATIONS SINGLE CONTROL ROD DRIVE (CRD)
REMOVAL -
REFUELING-0 11/15/2002 OPERATIONS MULTIPLE CONTROL ROD WITHDRAWAL -
REFUELING 1
04/18/2006 OPERATIONS CONTROL ROD TESTING -
OPERATING 1
04/12/2006 SHUTDOWN MARGIN (SDM)
TEST -
REFUELING OPERATIONS Page 8 Page 8 of 8
Report Date: 09/29/06 of 8 Report Date: 09/29/06
SUSQUEHANNA STEAM ELECTRIC STATION LIST OF EFFECTIVE SECTIONS (TECHNICAL SPECIFICATIONS BASES)
Section Title TOC table of Contents B 2.0 SAFETY LIMITS BASES
- Page B 2.0-1 Page TS / B 2.0-2 Page TS / B 2.0-3 Pages TS / B 2.0-4 and TS / B 2.0-5 Page TS / B 2.0-6 Pages B 2.0-7 through B 2.0-9 Revision 11 B 3.0 B 3.1 Ib LCO AND SR APPLICABILITY BASES Pages B 3.0-1 through B 3.0-4 Pages TS / B 3.0-5 through TS / B 3.0-7 Pages TS / B 3.0-8 through TS / B 3.0-9 Pages TS / B 3.0-10 through TS / B 3.0-12' 1 Pages TS/ B 3.0-13 through TS / B 3.0-15 Pages TS / B 3.0-16 and TS / B 3.0-17.
REACTIVITY CONTROL BASES Pages B 3.1-1 through B 3.1-4 Page TS / B 3.1-5 K.. II Pages TS / B 3.1-6 and TS /,B 3.1-7 Pages B 3.1-8 through B 3.1L13=
Page TS / B 3.1-,4 1 Pages B 3.1-15,through B 3.1-21 Page TS / B 3.1.22 Page TS hB3.1A23 Page TSI/.B,3!.1-24 Page TS 1B 3.1 *25 Page TS / B 3.1'-26 Page'TS/B 3.1-27 PageTS/B3.1-28 Page TS/B3.1-29 Pages B 3.1730 through B 3.1-33'
';Pages TS / B 3.3-34 through TS IB 3ý3-36
- .Pages TS I B 3.1-37 and TS / B 3.1-38
- Pages B 3.1-39 through B 3.1-44 Page TSI B 3.1545
- Pages B 311-46 and B 3.1-47
,Pages TS i B 3.1-48 and TS I B 3.149
':Page B-3.1 -50 Page TS 6B3.1-51
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1 I
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SUSQUEHANNA - UNIT I TSIBLOES-1 Revision 78 TS / B LOES-1 Revision 78
SUSQUEHANNA STEAM ELECTRIC STATION LIST OF EFFECTIVE SECTIONS (TECHNICAL SPECIFICATIONS BASES)
Section Title Revision B 3.2 POWER DISTRIBUTION LIMITS BASES Page TS / B 3.2-1 1
Pages TS / B 3.2-2 through TS / B 3.2-6 2
- Page B 3.2-7 0
Pages TS / B 3.2-8 and TS / B 3.2-9 2
Page TS / B 3.2.10 1
Page TS / B 3.2-11 2
Page B 3.2-12 0
Page TS / B 3.2-13 2
Pages B 3.2-14 and B 3.2-15 0
Page TS / B 3.2-16 2
Page B 3.2-17 0
Page TS / B 3.2-18 1
Page TS / B 3.2-19 4
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 3.3-7a 0
Pages TS / B 3.3-8 through TS / B 3.3-12 3
Pages TS / B 3.3-12a through TS / B 3.3-12c 0
Page TS / B 3.3-13 1
Page TS / B 3.3-14 3
Pages TS / B 3.3-15 and TS / B 3.3-16 1
Pages TS / B 3.3-17 and TS / B 3.3-18 3.
Page TS / B 3.3-19 1
Pages TS /lB 3.3-20 through TS / B 3.3-22 2
Page TS / B 3.3-22a 0
Pages TS / B 3.3-23 and TS / B 3.3-24 2
Pages TS / B 3.3-24a and TS / B 3.3-24b 0
Pages TS / B 3.3-25 and TS / B 3.3-26 2
Page TS / B 3.3-27 1
Pages TS / B 3.3-28 through TS / B 3.3-30 3
Page TS / B 3.3-30a 0
Page TS / B 3.3-31 3
Page TS / B 3.3-32 5
Pages TS / B 3.3-32a and TS / B 3.3-32b 0
Page TS / B 3.3-33 5
Page TS / B 3.3-33a 0
Page TS / B 3.3-34 1
Pages TS / B 3.3-35 and TS / B 3.3-36 2
Pages TS / B 3.3-37 through TS / B 3.3-43 1
Page TS / B 3.3-44 3
SUSQUEHANNA - UNIT I TSlBLOES-2 Revision 78 SUSQUEHANNA - UNIT I TS I B LOES-2 Revision 78
SUSQUEHANNA STEAM ELECTRIC STATION LIST OF EFFECTIVE SECTIONS (TECHNICAL SPECIFICATIONS BASES)
Section Title Revision Pages TS / B 3.3-45 through TS I B 3.3-49 2
Page TS / B 3.3-50, 3
PageTS/B 3.3-51 2
Pages TS / B 3.3-52 and TS /B 3.3-53 1
Page TS / B 3.3-54 3
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
Page TS / B 3.3-68 4
Page TS / B 3.3-69, 5
Pages TS / B 3.3-70, and 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 3.3-75:1 2
Page TS / B 3.3-75a 5
Page TS / B 3.3-75b 6
Page TS / B 3.3-75c L 4
Pages B 3.3-76 through 3.3-77 0
Page TS B3.3-78!'
Pages B 3.3-79 through B 3.3-89 0
Page'TS / B 3.3-90H 1
Page B 3.3-91 0
Pages TS / B 3.3-92 through TS /B 3.3-100 1
Pages B 3.3-101 through B 3.3-103 0
Page TS / B 3.3-104' 1
Pages B 3.3-105 and B 3.3-106
.0 Page TS / B 3.3-107'1 PageB3.3-108 0
Page TS / B 3.3-109 1
Pages B 3.3-110 and B 3.3-111 0
Page's TS / B 3.3-112land TS / B 3.3-112a 1
Pages TS / B 3.3-i1 3throdugh TS I B 3.3-115 1
Page'TS/B3.3-116 2
PagetS / B3.3-117 Pages B 3.3-118 thiough B 3.3-122 0
Pages TS / B 3.3-1 23 Iand TS I B 3.3-124 1
PageTS / B 3.3-124:
0 Page B3.3-125 1 [ 1 ý 1
0 Page* TS / B 3.3-126 and TS/B 3.3-127 1
Page's B 3.3-128 thr6'gh B 3.3-130 0
Page'TS/B3.3-131 M,
1 Pages B 3.3-132 t6rough B 3.3-137 0
Os
,,r SUSQUEHANNA
- UNIT I TSIBLOES-3 Revision 78 SUSQUEHANNA7'UNIT 1 TS I B LOES-3 Revision 78
SUSQUEHANNA STEAM ELECTRIC STATION LIST OF EFFECTIVE SECTIONS (TECHNICAL SPECIFICATIONS BASES)
Section Title Revision 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 / B 3.3-177 1
Pages TS / B 3.3-178 and TS / B 3.3-179 2
Pages TS / B 3.3-179a and TS / B 3.3-179b 2
Page TS / B 3.3-179c 0
- Page TS / B 3.3-180 1
Page TS / B 3.3-181 2
Pages TS / B 3.3-182 through TS I B 3.3-186 1
Pages TS / B 3.3-187 and TS / B 3.3-188 2
Pages TS / B 3.3-189 through TS / B 3.3-191 1
Pages B 3.3-192 through B 3.3-204 0
Page TS / B 3.3-205 1
Pages B 3.3-206 through B 3.3-219
.0 B 3.4 REACTOR COOLANT SYSTEM BASES Pages B 3.4-1 and B 3.4-2 0
Pages TS / B 3.4-3 and Page TS / B 3.4-4 4
Pages TS / B 3.4-5 through TS / B 3.4-9 2
Pages B 3.4-10 through B 3.4-14 0
Page TS / B 3.4-15 1
Pages TS / B 3.4-16 through TS / B 3.4-18 2
Pages B 3.4-19 through B 3.4-27 0
Pages TS / B 3.4-28 and TS / B 3.4-29 1
Pages B 3.4-30 and B 3.4-31
.0 Page TS / B 3.4-32 1
Pages B 3.4-33 through B 3.4-36 0
Page TS / B 3.4-37 1
Pages B 3.4-38 through B 3.4-40 0
Page TS / 8 3.4-41 1
Pages B 3.4-42 through B 3.4-48 0
Page TS / B 3.4-49 3
Page TS / B 3.4-50 1
Page TS / B 3.4-51 3
Page TS / B 3.4-52 2
Page TS / B 3.4-53 1
Pages TS / B 3.4-54 and TS I B 3.4-55 2
Page TS / B 3.4-56 1
Page TS / B 3.4-57 3
Pages TS / B 3.4-58 through TS / B 3.4-60 1
SUSQUEHANNA
- UNIT I TSIB LOES-4 Revision 78 SUSQUEHANNA - UNIT 1 TS / B LOES-4 Revision 78
SUSQUEHANNA STEAM ELECTRIC STATION LIST OF EFFECTIVE SECTIONS (TECHNICAL SPECIFICATIONS BASES)
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SUSQUEHANNA STEAM ELECTRIC STATION LIST OF EFFECTIVE SECTIONS (TECHNICAL SPECIFICATIONS BASES)
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SUSQUEHANNA - UNIT I TS/BLOES-6 Revision 78 SUSQUEHANNA -UNIT1I TS / B LOES-6 Revision 78
SUSQUEHANNA STEAM ELECTRIC STATION LIST OF EFFECTIVE SECTIONS (TECHNICAL SPECIFICATIONS BASES)
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TSB1 text LOES 9/21/06 SUSQUEHANNA - UNIT I TSIB LOES-7 Revision 78 SUSQUEHANNA - UNIT 1
ý: TS /-B LOES-7 Revision 78
TABLE OF CONTENTS (TECHNICAL SPECIFICATIONS BASES)
B2.0 SAFETY LIM ITS (SLs).................................................................................
B2.0-1 B2.1.1 Reactor Core SLs...........................................................................
B2.0-1 B2.1.2 Reactor Coolant System (RCS) Pressure SL.................................
B2.0-7 B3.0 LIMITING CONDITION FOR OPERATION (LCO) APPLICABILITY.............. B3.0-1 B3.0 SOJRVEILLANCE REQUIREMENT (SR) APPLICABILITY...................... TS/B3.0-10 B3.1 REACTIVITY CONTROL SYSTEMS......................
B3.1-1 B3.1.1 Shutdown Margin (SDM)................................................................
B3.1-1 B3.1.2 Reactivity Anomalies..............................
B3.1-8 B3.1.3 Control Rod OPERABILITY............................................................
B3.1-13 B3.1.4 Control Rod.Scram Times........................
TS/B3.1-22 B3.1.5 Control Rod Scram Accumulators............................................
TS/B3.1-29 B3.1.6 Rod Pattern Control..................................................................
TS/B3.1-34 B3.1.7 Standby Liquid Control (SLC) System............................................
B3.1-39 B3.1.8 Scram Discharge Volume (SDV) Vent and Drain Valves................ B3.1-47 B3.2 POWER DISTRIBUTION LIMITS..........................
..... TS/B3.2-1 B3.2.1 Average Planar Linear Heat Generation Rate (APLHGR)......
TS/B3.2-1 B3.2.2 Minimum Critical Power Ratio (MCPR).....................................
TS/B3.2-5 B3.2.3 Linear Heat Generation Rate (LHGR).......................................
TS/B3.2-10 B3.2.4 Average Power Range Monitor (APRM) Gain and Setpoints........................................................
B3.2-14 B3.3 INSTRUMENTATION...................................................................
- .. TS/B3.3-1 83.3.1.1 Reactor Protection System (RPS) Instrumentation................... TS/B3.3-1 B3.3.1.2 Source Range Monitor (SRM) Instrumentation.........................
TS/B3.3-35 B3.3.2.1 Control Rod Block Instrumentation
.................. TS/B3.3-44 B3.3.2.2 Feedwater -Main Turbine High Water Level Trip Instrum entation.........................................................................
B3.3-55 B3.3.3.1 Post Accident Monitoring (PAM) Instrumentation..................... TS/B3.3-64 B3.3.3.2 Remote Shutdown System..............................
B3.3-76 B3.3.4.1 End of Cycle' Recirculation Pump Trip (EOC-RPT)
Instrumentation...............................
B3.3-81 B3.3.4.2 Anticipated Transient Without Scram Recirculation Pump Trip (ATWS-RPT) Instrumentation............................. TS/B3.3-92 B3.3.5.1 Emergency CoreCooling System (ECCS)
Instrumentation.....................................
........................... B3.3-101 B3.3.5.2 Reactor Core Isolation Cooling (RCIC) System Instrumentation...............................
B3.3-135 B3.3.6.1 Primary Containment Isolation Instrumentation.............................
B3.3-147 B3.3.6.2 Secondary Containment Isolation Instrumentation.................. TS/B3.3-180 B3.3.7.1 Control Room 'Emergency Outside Air Supply (CREOAS)
System Instrumentation..;.........................................................
B3.3-192 (continued)
SUSQUEHANNA - UNIT I TS / B TOG - I Revision 11
TABLE OF CONTENTS (TECHNICAL SPECIFICATIONS BASES)
B3.3 B3.3.8.1 B3.3.8.2 B3.41 B3.4.1 B3.4.2 B3.4.3 B3.4.4 B3.4.5 B3.4.6 B3.4.7 B3.4.8 B3.4.9 B3.4.1 0 B3.4.11 B3.5 B3.5.1 B3.5.2 B3.5.3 B3.6 B3.6.1..1 B3.6.1.2 B3.6.1.3 B3.6.1.4 B3.6.1.5 B3.6.1.6 B3.6.2.1 B3.6.2.2 B3.6.2.3 B3.6.2.4 B3.6.3.1 B3.6.3.2 B3.6.3.3 83.6.4.1 B3.6.4.2 B3.6.4.3 INSTRUMENTATION (continued)
Loss of Power (LOP) Instrumentation.................
TS/B3.3-205 Reactor Protection System (RPS) Electric Power Monitoring 3.3-213 REACTOR COOLANT SYSTEM (RCS)...............................................
B3.4-1 Recirculation Loops Operating.......................................................
B3.4-1 Jet Pum ps......................................................................................
B3.4-10 Safety/Relief Valves (S/RVs)....................................................
TS/B3.4-15 RCS Operational LEAKAGE 3.4-19 RCS Pressure Isolation Valve (PIV) Leakage.................................
B3.4-24 RCS Leakage Detection Instrumentation.................
8 3.4-30 RCS Specific Activity..............................
B3.4-35 Residual Heat Removal (RHR) Shutdown Cooling System - Hot Shutdown...........................................................
B3.4-39 Residual Heat Removal (RHR) Shutdown Cooling System - Cold Shutdown.........................
b3.4-44 RCS Pressure and Temperature (P/T) Limits.........................
TS/B3.4-49 Reactor Steam Dome Pressure................................................
TS/B3.4-58 EMERGENCY CORE COOLING SYSTEMS (ECCS) AND REACTOR CORE ISOLATION COOLING (RCIC) SYSTEM...............
B3.5-1 ECCS - Operating.........................................................................
B3.5-1 ECCS - Shutdown.........................................................................
B3.5-19 RCIC System........................................................................
"..TS/B3.5-25 CONTAINMENT SYSTEMS...........................................................
TS/B3.6-1 Primary Containment........................................
TS/83.6-1 Primary Containment Air Lock..........................
B3.6-7 Primary Containment Isolation Valves (PCIVs)......................... TS/B3.6-15 Containment Pressure....................................................................
B3.6-41 Drywell Air Temperature..........................................................
TS/B3.6-44 Suppression Chamber-to-Drywell Vacuum Breakers.......
TS/B3.6-47 Suppression Pool Average Temperature..................... I.......
B3.6-53 Suppression Pool Water Level........................
B3.6-59 Residual Heat Removal (RHR) Suppression Pool Cooling............................................................ *.............
83.6-62 Residual Heat Removal (RHR) Suppression Pool Spray.....
B3.6-66 Not Used......................... ;....................................................
TS/B3.6-70 Drywell Air Flow System........................................
B3.6-76 Primary Containment Oxygen Concentration.................
B3.6-81 Secondary Containment.........
K..........................................
TS/B3.6-84 Secondary Containment Isolation Valves (SC0Vs).........
TS/B3.6-91 Standby Gas Treatment (SGT) System.
TS/B3.6-1o 1
(continued)
SUSQUEHANNA-UNIT I TS/BTOC-2 Revision 11 SUSQUEHANNA - UNIT 1 TS/BTOC-2 Revision 11
TABLE OF CONTENTS (TECHNICAL SPECIFICATIONS BASES)
B3.7 B3.7.1 B3.7.2 B3.7.3 B3.7.4 B3.7.5 B3.7.6 B3.7.7 B3.8 B3.8.1 B3.8.2 B3.8.3 B3.8.4 B3.8.5 B3.8.6 B3.8.7 B3.8.8 B3.9 B3.9.1 B3.9.2 B3.9.3 B3.9.4 B3.9.5 B3.9.6" B3.9.7 B3.9.8 PLANT SYSTEMS.........................................................................
TS/B3.7-1 Residual Heat Removal Service Water (RHRSW) System and the Ultimate Heat Sink (UHS)......................................
TS/B3.7-1 Emergency Service Water (ESW) System................................
TS/B3.7-7 Control Room Emergency Outside Air Supply (CREOAS) System.............................................................
TSIB3.7-12 Control Room Floor Cooling System........................................
TS/B3.7-19 Main Condenser Offgas.................................................................
B3.7-24 Main Turbine Bypass System...................................................
TS/83.7-27 Spent Fuel Storage Pool Water Level B3.7-31 ELECTRICAL POWER SYSTEM...................................................
TS/13.8-1
!'AC Sources - Operating TSIB3.8-1
- AC Sources - Shutdown................................................................
B3.8-38 Diesel Fuel Oil, Lube Oil, and Starting Air......................................
B3.8-45 DC Sources - Operating..........................................................
TS/B3.8-54 DC Sources -Shutdown B3.8-66 Battery Cell Parameters.................................................................
B3.8-71 Distribution Systems - Operating...................................................
B3.8-78 Distribution !Systems -. Shutdown...................................................
B3.8-86 REFUELING OPERATIONS..........................................................
TS/B3.9-1 Refueling Equipment Interlocks................................................
TS/B3.9-1 Refuel Position One-Rod-Out Interlock.................................. B3.9-5 Control Rod Position 3.9-9 Control Rod Position Indication......................................................
B3.9-12 Control Rod OPERABILITY-Refueling.........................................
B3.9-16 Reactor Pressure Vessel (RPV) Water Level.................................
B3.9-19
'Residual Heat Removal (RHR) - High Water Level....................... B3.9-22 IResidual Heat Removal (RHR) - Low Water Level......................... B3.9-26 B3.10 B3.10.1 B3.10.2 B3.10.3 B3.10.4 B3.10.5 B3.10.6 B3.10.7 B3.10.8 SPECIAL OPERATIONS.................................
TS/B3.10-1 Inservice Leak and Hydrostatic Testing Operation................... TS/B3.10-1 Reactor Mode'Switch Interlock Testing..........................................
B3.10-6 Single Control Rod Withdirawal - Hot Shutdown.............................
B3.10-11 Single Control Rod Withdrawal - Cold Shutdown...........................
B3.10-16 Single Control Rod Drive (CRD) Removal - Refueling................... B3.10-21 Multiple Control Rod Withdrawal - Refueling..................................
B3.10-26 Control Rod Testing "Operating...................................................
B3.10-29 SHUTDOWN MARGIN (SDM) Test-Refueling.............................
B3.10-33 TSB1 Text TOC 9/20/2006 SUSQUEHANNA UNIT I TS/BTOC-3 Revision 11 SUSQUEHANNA - UNIT 1 TS/BTOC-3 Revision 11
PPL Rev. 3 Control Rod Scram Times B 3.1.4 B3.1 B 3.1.4 BASES REACTIVITY CONTROL SYSTEMS Control Rod Scram Times BACKGROUND The scram function of the Control Rod Drive (CRD) System controls reactivity 'changes during abnormal operational transients to ensure that specified acceptable fuel design limits are not exceeded (Ref. 1). The control rods are scrammed by positive means using hydraulic pressure exerted on the CRD piston.
When a scram signal is initiated, control air is vented from the scram valves, allowing them to open by spring action. Opening the exhaust valve reduces the pressure above the main drive piston to atmospheric pressure, and opening the inlet valve applies the accumulator or reactor pressure to the bottom of the piston. Since the notches in the index tube are tapered on the lower edge, the collet fingers are forced open by cam action, allwirng the index tube to move upward without restriction because of the high differential pressure across the piston. As the drive moves upward and the accumulator pressure reduces below the reactor pressure, p ball check valve opens, letting the reactor pressure complete the scram action: If the reactor pressure is low, such as during startup, the accumulator will fully insert the control rod in the required time without assistance from reactor pressure.
APPLICABLE SAFETY ANALYSES APPLICABLE SAFETY ANALYSES The analytical methods and assumptions used in evaluating the control rod scram function are presented in References 2, 3, and 4. The Design Basis Accident (DBA) and transient analyses assume that all of the control rods scram at a specified insertion rate. The resulting negative scram reactivity forms the basis for the determination of plant thermal limits (e.g.,
the MCPR?. Other distributions of scram times (e.g., several control rods scramming slower than the average time with several control rods scramming faster than the average time) can also provide sufficient scram reactivity. Surveillance of each individual control rod's scram time ensures the scram reactivity assumed in the DBA and transient analyses can be met.
(continued)
SUSQUEHANNA - UNIT 1 TS / B 3.1-22 Revision 0
PPL Rev. 3 Control Rod Scram Times B 3.1.4 BASES APPLICABLE SAFETY-ANALYSES (continued)
The scram function of the CRD System protects the MCPR Safety Limit (SL) (see Bases for SL 2.1.1, "Reactor Core SLs," and LCO 3.2.2, "MINIMUM CRITICAL POWER RATIO (MCPR)") and the 1% cladding plastic strain fuel design limit (see Bases for LCO 3.2.3, 'LINEAR HEAT GENERATION RATE (LHGR)" and LCO 3.2.4, "AveragePower Range Monitor (APRM) Gain and Setpoints"), which ensure that no fuel damage will occur if these limits are not exceeded. Above 800 psig, the scram function is designed to insert negative reactivity at a rate fast enough to prevent the actual MCPR from becoming less than the MCPR SL, during the analyzed limiting power transient. Below 800 psig, the scram function is assumed to perform during the control rod drop accident and, therefore, also provides protection against violating fuel damage limits during reactivity insertion accidents (Ref. 5) (see Bases for LCO 3.1.6, "Rod Pattern Control"). For the reactor vessel overpressure protection analysis, the scram function, along with the safety/relief valves, ensure that the peak vessel pressure is maintained within the applicable ASME Code limits.
Control rod scram times satisfy Criterion 3 of the NRC Policy Statement (Ref. 6).
LCO The scram times specified in Table 3.1.4-1 (in the accompanying LCO) are required to ensure that the scram reactivity assumed in the DBA.and transient analysis is met (Ref. 7). To account for single failures and "slow" scramming control rods, the scram times specified in Table 3.1.4-1 are faster than those assumed in the design basis analysis. The scram times have a margin that allows up to approximately 7% of the control rods (e.g.,
185 x 7%,& 13) to have scram times exceeding the specified limits (i.e.,
"slow" control rods) including a single stuck control rod (as allowed by LCO 3.1.3, "Control Rod OPERABILITY") and an addition;al control rod failing to scram per the single failure criterion. The scram titmes are specified as a function of reactor steam dome pressure to account for the pressure dependence of the scram times. The scram times are specified relative to measurements based on reed switch positions, ýwhich provide the control rod position indication. The reed switch closes ("pickup") when the index tube passes a specific location and then opens ("dropout") as the index tube travels upward. Verification of the specified scram times in Table 3.1.4-1 is (continued)
SUSQUEHANNA - UNIT 1 TS / B 3.1-23 Revision 1
PPL Rev. 3 Control Rod Scram Times B 3.1.4 BASES LCO (continued) accomplished through measurement of the "dropout" times. To ensure that local scram reactivity rates are maintained within acceptable limits, no more than one "slow" control rod may occupy a face or diagonally adjacent location to any other "slow" or stuck control rod.
Table 3.1.4-1 is modified by two Notes which state that control rods with scram times not within the limits of the table are considered "slow" and that control rods with scram times > 7 seconds are considered inoperable as required by SR 3.1.3.4.
This LCO applies only to OPERABLE control rods since inoperable control rods will be inserted and disarmed (LCO 3.1.3). Slow scramming control rods may be conservatively declared inoperable and not accounted for as "slow" control rods.
APPLICABILITY In MODES 1 and 2, a scram is assumed to function during transients and accidents analyzed for these plant conditions. These events are assumed to occur during startup and power operation; therefore, the scram function of the control rods is required during these MODES. In MODES 3 and 4, the control rods are not able to be withdrawn (except as* permitted by LCO 3.10.3 and LCO 3.10.4) since the reactor mode switch is in shutdown and a control rod block is applied. This provides adequate requirements for control rod scram capability during these conditions. Scram requirements in MODE 5 are contained in LCO 3.9.5, "Control Rod OPERABILITY-Refueling."
ACTIONS A.1 When the requirements of this LCO are not met, the rate of negative reactivity insertion during a scram may not be within the assumptions of the safety analyses. Therefore, 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 />. The allowed Completion Time of 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> is reasonable, based on operating experience, to reach MODE 3 from full power conditions in an orderly manner and without challenging plant systems.
(continued)
SUSQUEHANNA - UNIT 1 TS / B 3.1-24 Revision 0
PPL Rev. 3 Control Rod Scram Times B 3.1.4 BASES (continued)
SURVEILLANCE REQUIREMENTS The four SRs of this LCO are modified by a Note stating that during a single control rod scram time surveillance, the CRD pumps shall be isolated from the associated scram accumulator. With the CRD pump isolated, (i.e., charging valve closed) the influence of the CRD pump head does not affect the single control rod scram times. During a full core scram, the CRD pump head would be seen by all control rods and would have a negligible effect on the scrarni insertion times.
SR 3.1.4.1 The scram reactivity used in DBA and transient analyses is based on an assumed control rod scram time. Measurement of the scram times with reactor steam dome pressure _> 800 psig demonstrates acceptable scram times for the transients analyzed in References 3 and 4.
Maximum scram insertion times occur at a reactor steam dome pressure of approximately 800 psig because of the competing effects of reactor steam dome pressure and stored accumulator energy. Therefore, demonstration of adequate scram times at reactor steam dome pressure > 800 psig ensures that the measured scram times will be within the specified limits at higher pressures.
Limits are specified as a function of reactor pressure to account for the sensitivity of the scram insertion times with pressure and to allow a range of pressures over which scram time testing can be performed. To ensure that scram time testing is performed within a reasonable time following a shutdown > 120 days or longer, control rods are required to be tested before exceeding 40% RTP following the shutdown. This Frequency is acceptable considering the additional surveillances performed for control rod OPERABILITY, the frequent verification of adequate accumulator pressure, and the required testing of control rods affected by fuel movement within the associated core cell and by work on control rods or the CRD System.
(continued)
II I
SUSQUEHANNA - UNIT 1 TS / B 3.1-25 Revision 1
PPL Rev. 3 Control Rod Scram Times B 3.1.4 BASES SURVEILLANCE REQUIREMENTS (continued)
SR 3.1.4.2 Additional testing of a sample of control rods is required to verify the continued performance of the scram function during the cycle. A representative sample contains at least 10% of the control rods. The sample remains representative if no more than 20% of the control rods in the sample te.sted are determined to be "slow." With more than 20% of the sample declared to be "slow" per the criteria in Table 3.1.4-1, additional control rods are tested until this 20% criterion (e.g., 20% of the entire sample 'size) is satisfied, or until the total number of "slow' control rods (through'6ut the core, from all surveillances) exceeds the LCO limit.
For planned testing, the control rods selected for the sample should be different for each test. Data from inadvertent scrams should be used whenever possible to avoid unnecessary testing at power, even if the control rods with data may have been previously tested in a sample. The 120 day Frequency is based on operating experience that has shown control rod scram times do not significantly change over an operating cycle. This Frequency is also reasonable based on the additional Surveillances done on the CRDs at more frequent intervals in accordance with LCO 3.1.3 and LCO 3.1.5, !'Control Rod Scram Accumulators."
SR 3.1.4.3 When work that could affect the scram insertion time is performed on a control rod or'the CRD System, testing must be done to demonstrate that each affelcted control rod retains adequate scram performance over the range of', pplcable reactor pressures from zero to the maximum permissible pressure. The scram testing must be performed once before declaring the control rod OPERABLE. The required scram time testing must demonstrate the affected control rod is still within acceptable limits. The limits for reactor pressures < 800 psig are established based on a high probability of meeting the acceptance criteria at reactor pressures >_ 800 psig. Limits for_> 800 psig are found in Table 3.1.4-11. If testing demonstrates the affected control rod does not meet these limits, but is within the 7-second limit of Table 3.1.4-1, Note 2, the cointrol rod can be declared OPERABLE and "slow."
(o i
e (continued)
SUSQUEHANNA - UNIT 1 TS / B 3.1-26 Revision 0
PPL Rev. 3 Control Rod Scram Times B 3.1.4 BASES REQUIREMENTS SR 3.1.4.3 (continued)
SURVEILLANCE Specific examples of work that could affect the scram times are (but are not limited to) the following: removal of any CRD for maintenance or modification; replacement of a control rod; and maintenance or modification of a scram solenoid pilot valve, scram valve, accumulator, isolation valve or check valve in the piping required for scram.
The Frequency of once prior to declaring the affected control rod OPERABLE is acceptable because of the capability to test the control rod over a range of operating conditions and the more frequent surveillances on other aspects of control rod OPERABILITY.
SR 3.1.4.4 When work that could affect the scram insertion time is performed on a control rod or CRD System, or when fuel movement within the affected core cell occurs, testing must be done to demonstrate each affected control rod is still within the limits of Table 3.1.4-1 with the reactor steam dome pressure >_ 800 psig. Where work has been performed at high reactor pressure, the requirements of SR 3.1.4.3 and SR 3.1.4.4 can be satisfied with one test. For a control rod affected by work performed while shut down, however, a zero pressure and high pressure test may be required. This testing ensures that, prior to withdrawing the control rod for continued operation, the control rod scram performance is acceptable for operating reactor pressure conditions. Alternatively, a control rod scram test during hydrostatic pressure testing could also satisfy both criteria.
When fuel movement within the reactor pressure vessel occurs, only those control rods associated with the core cells affected by the fuel movement are required to be scram time tested. During a routine refueling outage, it is expected that all control rods will be affected.
The Frequency of once prior to exceeding 40% RTP is acceptable because of the capability to test the control rod over a range of operating conditions and the more frequent surveillances on other aspects of control rod OPERABILITY.
REFERENCES
- 1.
10 CFR 50, Appendix A, GDC 10.
- 2.
FSAR, Section 4.3.2.:
- 3.
FSAR, Section 4.6.
(continued)
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PPL Rev. 3 Control Rod Scram Times B 3.1.4 BASES REFERENCES (continued)
- 4.
FSAR, Section 15.0.
- 5.
FSAR, Section 15.4.9.
I
- 6.
Final Policy Statement on Technical Specifications Improvements, July 22, 1993 (58 FR 39132).
- 7.
Letter from R.F. Janecek (BWROG) to R.W. Starostecki (NRC),
"BWR Owners Group Revised Reactivity Control System Technical Specifications," BWROG-8754, September 17,1987.
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