ML060870407
| ML060870407 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 03/17/2006 |
| From: | Susquehanna |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| Download: ML060870407 (25) | |
Text
Mar.
17, 2006 Page 1
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MANUAL HARD COPY DISTRIBUTION DOCUMENT TRANSMITTAL 2006-12371 USER INFORMATION:
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TSB1 -
TECHNICAL SPECIFICATION BASES UNIT 1 MANUAL REMOVE MANUAL TABLE OF CONTENTS DATE: 02/01/2006 ADD MANUAL TABLE OF CONTENTS DATE: 03/16/2006 CATEGORY:
DOCUMENTS TYPE: TSB1 ftoo I
Mar. 17, 2006 Page 2
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ID:
TEXT 3.6.4.1 REMOVE:
REV:4 ADD:
REV: 5 CATEGORY:
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REVT:
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SSES MANUAL
- Manual Name
TSB1 Manual
Title:
TECHNICAL SPECIFICATION BASES UNIT 1 MANUAL Table Of Contents Issue Date:
03/16/2006 Procedure Name Rev Issue Date Change ID Change Number TEXT LOES 69 03/16/2006
Title:
LIST OF EFFECTIVE SECTIONS TEXT TOC 7
04/18/2005
Title:
TA3LE OF CONTENTS TEXT 2.1.1 1
04/27/2004
Title:
SAFETY LIMITS (SLS)
REACTOR CORE SLS TEXT 2.1.2 0
11/15/2002
Title:
SAFETY LIMITS (SLS)
REACTOR COOLANT SYSTEM (RCS) PRESSURE SL TEXT 3.0 1
04/18/2005
Title:
LIMITING CONDITION FOR.OPERATION (LCO)
APPLICABILITY TEXT 3.1.1 0
11/15/2002
Title:
REACTIVITY CONTROL SYSTEMS SHUTDOWN MARGIN (SDM)
TEXT 3.1.2 0
11/15/2002
Title:
REACTIVITY CONTROL SYSTEMS REACTIVITY ANOMALIES TEXT 3.1.3 1
07/06/2005
Title:
REACTIVITY CONTROL SYSTEMS CONTROL ROD OPERABILITY TEXT 3.1.4 1
07/06/2005
Title:
REACTIVITY CONTROL SYSTEMS CONTROL ROD SCRAM TIMES TEXT 3.1.5 1
07/06/2005
Title:
REACTIVITY CONTROL SYSTEMS CONTROL ROD SCRAM ACCUMULATORS TEXT 3.1.6 1
02/17/2005
Title:
REACTIVITY CONTROL SYSTEMS ROD PATTERN CONTROL Page 1 of 8; Report Date: 03/16/06
SSES MANUAL Manual Name: TSB1 Manual
Title:
TECHNICAL SPECIFICATION BASES UNIT 1 MANUAL KJ TEXT 3.1.7
Title:
REACTIVITY CONTROL 1
08/30/2005 SYSTEMS STANDBY LIQUID CONTROL (SLC) SYSTEM TEXT 3.1.8 1
10/19/2005
Title:
REACTIVITY CONTROL SYSTEMS SCRAM DISCHARGE VOLUME (SDV)
VENT AND DRAIN VALVES TEXT 3.2.1 0
11/15/2002
Title:
POWER DISTRIBUTION LIMITS AVERAGE PLANAR LINEAR HEAT GENERATION RATE (APLHGR)
TEXT 3.2.2 0
11/15/2002
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 1
07/06/2005
Title:
POWER DISTRIBUTION LIMITS AVERAGE POWER RANGE MONITOR (APRM) GAIN AND SETPOINTS C TEXT 3.3.1.1 2
07/06/2005.
Title:
INSTRUMENTATION REACTOR.PROTECTION SYSTEM (RPS) INSTRUMENTATION TEXT 3.3.1.2 0
11/15/2002
Title:
INSTRUMENTATION SOURCE RANGE MONITOR (SRM) INSTRUMENTATION TEXT 3.3.1.3
Title:
OPRM INSTRUMENTATION 0
11/22/2004 TEXT 3.3.2.1 1
02/17/2005
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 2
07/06/2005
Title:
INSTRUMENTATION POST ACCIDENT MONITORING (PAM) INSTRUMENTATION V)
Page *
of 8 Report Date: 03/16/06 Page 2 of 8 Report Date: 03/16/06
SSES MANUAL Manual Name:
TSB1 Manual
Title:
- TECHNICAL SPECIFICATION BASES UNIT 1 MANUAL TEXT 3.3.3.2 1
04/18/2005
Title:
INSTRUMENTATION REMOTE SHUTDOWN SYSTEM 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 (AIWS-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 TEXT 3.3.8.2
Title:
INSTRUMENTATION TEXT 3.4.1
Title:
REA.CTOR COOLANT TEXT 3.4.2
Title:
REA.CTOR COOLANT 2
07/06/2005 EMERGENCY CORE COOLING SYSTEM (ECCS) INSTRUMENTATION 0.
11/15/2002 REACTOR CORE ISOLATION COOLING (RCIC) SYSTEM INSTRUMENTATION 1
11/09/2004 PRIMARY CONTAINMENT ISOLATION INSTRUMENTATION 1
1/09/2004.
SECONDARY CONTAINMENT ISOLATION INSTRUMENTATION 0
11/15/2002 CONTROL ROOM EMERGENCY OUTSIDE AIR SUPPLY (CREOAS) SYSTEM 1
09/02/2004 LOSS OF POWER (LOP) INSTRUMENTATION 0
11/15/2002 REACTOR PROTECTION SYSTEM (RPS) ELECTRIC POWER MONITORING 2
11/22/2004 SYSTEM (RCS) RECIRCULATION LOOPS OPERATING 0
11/15/2002 SYSTEM (RCS)
JET PUMPS Page3 of 8
Report Date: 03/16/06 Page 3 of 8 Report Date: 03/16/06
SSES MANUAL Manual Name: TSB1 y
Manual
Title:
TECHNICAL SPECIFICATION BASES UNIT 1 MANUAL TEXT 3.4.3
Title:
REACTOR TEXT 3.4.4
Title:
REACTOR TEXT 3.4.5
Title:
REACTOR TEXT 3.4.6
Title:
REACTOR TEXT 3.4.7
Title:
REACTOR 1
01/16/2006 COOLANT SYSTEM (RCS) SAFETY/RELIEF VALVES (S/RVS) 0 11/15/2002 COOLANT SYSTEM (RCS) RCS OPERATIONAL LEAKAGE 1
01/16/2006 COOLANT SYSTEM (RCS) RCS PRESSURE ISOLATION VALVE (PIV) LEAKAGE 1
04/18/2005 COOLANT SYSTEM (RCS) RCS LEAKAGE DETECTION INSTRUMENTATION 1
04/18/2005 COOLANT SYSTEM (RCS) RCS SPECIFIC ACTIVITY TEXT 3.4.8 1
04/18/2005
Title:
REACTOR COOLANT SYSTEM~ (RCS)
RESIDUAL HEAT REMOVAL (RHR) SHUTDOWN COOLING SYSTEM ij HOT SHUTDOWN TEXT 3.4.9
Title:
REACTOR COOLANT COLD SHUTDOWN TEXT 3.4.10
Title:
11/15/2002.
SYSTEM (RCS) RESIDUAL HEAT REMOVAL (RHR) SHUTDOWN COOLING SYSTEM 0
11/15/2002 SYSTEM (RCS)
RCS PRESSURE AND TEMPERATURE (P/T) LIMITS TEXT 3.4.11 0
11/15/2002
Title:
REACTOR COOLANT SYSTEM (RCS) REACTOR STEAM DOME PRESSURE TEXT 3.5.1 2
01/16/2006
Title:
EMERGENCY CORE COOLING SYSTEMS (ECCS) AND REACTOR CORE ISOLATION COOLING SYSTEM ECCS -
OPERATING TEXT 3.5.2 0
11/15/2002
Title:
EMERGENCY CORE COOLING SYSTEMS (ECCS) AND REACTOR CORE ISOLATION COOLING SYSTEM ECCS -
SHUTDOWN TEXT 3.5.3 1
04/18/2005
Title:
EMERGENCY CORE COOLING SYSTEMS (ECCS)
AND REACTOR CORE ISOLATION COOLING SYSTEM RCIC SYSTEM (RCIC)
(RCIC)
(RCIC)
Page4 of 8
Report Date: 03/16/06 Page 4 of 8 Report Date: 03/16/06
SSES MANUAL s
Manual Name:
TSB1 Manual
Title:
TECHNICAL SPECIFICATION BASES UNIT 1 MANUAL TEXT 3.6.1.1 0
11/15/2002
Title:
CONTAINMENT SYSTEMS PRIMARY CONTAINMENT TEXT 3.6.1.2 0
11/15/2002
Title:
CONrTAINMENT SYSTEMS PRIMARY CONTAINMENT AIR LOCK TEXT 3.6.1.3
Title:
CONTAINMENT 3
12/08/2005 SYSTEMS PRIMARY CONTAINMENT ISOLATION VALVES (PCIVS)
TEXT 3.6.1.4
Title:
CONTAINMENT TEXT 3.6.1.5
Title:
CONTAINMENT TEXT 3.6.1.6 Qji
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 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 1
04/18/2005 SYSTEMS PRIMARY CONTAINMENT HYDROGEN RECOMBINERS 1
04/18/2005 SYSTEMS DRYWELL AIR FLOW SYSTEM PageS of 8
Report Date: 03/16/06 Page 5 of 8 Report Date: 03/16/06
SSES MANUAL Manual Name: TSB1 Manual
Title:
TECHNICAL SPECIFICATION BASES UNIT 1 MANUAL TEXT 3.6.3.3
Title:
CONTAINMENT TEXT 3.6.4.1
Title:
CONTAINMENT TEXT 3.6.4.2
Title:
CONTAINMENT TEXT 3.6.4.3
Title:
CONTAINMENT TEXT 3.7.1 0
11/15/2002 SYSTEMS PRIMARY CONTAINMENT OXYGEN CONCENTRATION 5
03/16/2006 SYSTEMS SECONDARY CONTAINMENT 2
01/03/2005 SYSTEMS SECONDARY CONTAINMENT ISOLATION VALVES (SCIVS) 3 10/24/2005 SYSTEMS STANDBY GAS TREATMENT (SGT)
SYSTEM 0
11/15/2602
Title:
PLANT SYSTEMS RESIDUAL HEAT REMOVAL SERVICE WATER (RHRSW)
SYSTEM AND THE ULTIMATE HEAT SINK (UHS)
TEXT 3.7.2
Title:
PLANT 1
11/09/2004 SYSTEMS EMERGENCY SERVICE WATER (ESW)
SYSTEM TEXT 3.7.3 0
11/15/2002.
Title:
PLANT SYSTEMS CONTROL ROOM EMERGENCY OUTSIDE AIR SUPPLY (CREOAS) SYSTEM TEXT 3.7.4 0
11/15/2002
Title:
PLANT SYSTEMS CONTROL ROOM FLOOR COOLING SYSTEM TEXT 3.7.5 0
11/15/2002
Title:
PLANT SYSTEMS MAIN CONDENSER OFFGAS TEXT 3.7.6 1
01/17/2005
Title:
PLANT SYSTEMS MAIN TURBINE BYPASS SYSTEM TEXT 3.7.7
Title:
PLANT TEXT 3.8.1 0
11/15/2002 SYSTEMS SPENT FUEL STORAGE POOL WATER LEVEL 3
10/05/2005
Title:
ELECTRICAL POWER SYSTEMS AC SOURCES -
OPERATING Page 6 of 8
Report Date: 03/16/06 Page 6 of 8 Report Date: 03/16/06
SSES MANUAL d, Manual Name:
TSB1 Manual
Title:
- TECHNICAL SPECIFICATION BASES UNIT 1 MANUAL TEXT 3.8.2
Title:
ELECTRICAL 0
11/15/2002 POWER SYSTEMS AC SOURCES -
SHUTDOWN 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 to
Title:
ELECTRICAL 0
11/15/2002 POWER SYSTEMS DIESEL FUEL OIL, LUBE OIL, AND STARTING AIR 0
11/15/2002 POWER SYSTEMS DC SOURCES -
OPERATING 0
11/15/2002 POWER SYSTEMS DC SOURCES -
SHUTDOWN 0
11/15/2002 POWER SYSTEMS BATTERY CELL PARAMETERS 1
10/05/2005 POWER SYSTEMS DISTRIBUTION SYSTEMS -
OPERATING TEXT 3.8.8
Title:
ELECTRICAL 0
11/15/2002.
POWER SYSTEMS DISTRIBUTION SYSTEMS -
SHUTDOWN 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 OPERATIONS OPERATIONS OPERATIONS OPERATIONS OPERATIONS 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 Page 7 of 8
Report Date: 03/16/06 Page 7 of 8 Report Date: 0 3/16/06
SSES MANUAL Manual Name: TSB1 Manual
Title:
TECHNICAL SPECIFICATION BASES UNIT 1 MANUAL TEXT 3.9.6 0
11/15/2002
Title:
REFUELING OPERATIONS REACTOR PRESSURE VESSEL (RPV)
TEXT 3.9.7 0
11/15/2002
Title:
REFUELING OPERATIONS RESIDUAL HEAT REMOVAL (RHR) -
TEXT 3.9.8 0
11/15/2002
Title:
REFUELING-OPERATIONS RESIDUAL HEAT REMOVAL (RHR) -
WATER LEVEL HIGH WATER LEVEL 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 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 Y-N 0
11/15/2002.
SINGLE CONTROL ROD WITHDRAWAL -
COLD SHUTDOWN 0
11/15/2002 SINGLE CONTROL ROD DRIVE (CRD)
REMOVAL -
REFUELING O
11/15/2002 MULTIPLE CONTROL ROD WITHDRAWAL -
REFUELING 0
11/15/2002 CONTROL ROD TESTING -
OPERATING 0
11/15/2002 SHUTDOWN MARGIN (SDM)
TEST -
REFUELING Page8 of 8 Report Date: 03/16/06 Page 8 of 8 Report Date: 03/16/06
SUSQUEHANNA STEAM ELECTRIC STATION LIST OF EFFECTIVE SECTIONS (TECHNICAL SPECIFICATIONS BASES)
K.
Section Title Revision TOC Table of Contents 7
B 2.0 SAFETY LIMITS BASES Page B 2.0-1 0
Page TS / B 2.0-2' 2
Page TS/B2.0-3 3
Pages TS/ B 2.0-4 and TS / B 2.0-5 2
PageTS/B2.0-6 1
Pages B 2.0-7 through B 2.0-9 0
B 3.0 LCO AND SR APPLICABILITY BASES Pages B 3.0-1 through B 3.0-4 0
Pages TS / B 3.0-5 through TS / B 3.0-7 1
Pages TS / B 3.0-8 through TS / B 3.0-9
,2 Pages TS / B 3.0-10 through TS / e 3.0-12 1
Pages TS / B 3.0-13 through TS / e. 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 3.1-5 0
Pages TS / B 3.1-6 and TS / B 3.1-7 1
Pages B 3.1-8 through B 3.1-13'-;
t0 PageTS/B3.1-14 Pages B 3.1-15 through B 3.1-22 0
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Pages B 3.1-24 thrwugh B 3.1-27
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Pages TS / B 3.3-34 through TS / B 3.3-36 1
PageTS/B3.1-37
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<Pages B 3.1-39 through B 3.1-44 0
PageTS/B3.1-45 1
Pages B 3.1-46 and B 3.1-47 Pages TS / B 3.1-48 and TS/ B 3.149 1
Page B 3.1-50 0
PageTS/B3.1-51 1
B 3.2 POWER DISTRIBUTION LIMITS BASES I
Page TS/ B 3.2-1 21 Page TS B 3.2-2 2
I Page TS B 3.2-3 1
PageTS/B3.2-4 2
Pages TS / B 3.2-5 and TS B 3.2-6 1
SUSQUEHANNA - UNIT 1 TS / B LOES-1 Revision 69
SUSQ UEHANNA STEAM ELECTRIC STATION LIST OF EFFECTIVE SECTIONS (TECHNICAL SPECIFICATIONS BASES) k-mv Sectiohl D
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IIi Titil 1%,W'
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I Page B 3.2-7 Pages TS / B 3.2-8,through TS / B 3.2-10 Page TS / B 3.2-11 Page B 3.2-12 Page TS / B 3.2-13 Pages B 3.2114 and B 3.2-15 Page TS / B 3.2-16 Pages B 3.2-17 and B 3.2-18 Page TS / B3.2-19 INSTRUMENTATION Pages TS / B 3.3-1 through TS / B 3.3-4 Page TS /B 3.3-5 Page TS / B 3.3-6*J Pages TS / B 3.3-7 through TS / B 3.3-11 Page TS / B13.3-12 Page TS / B 3.3-13 Page TS / B,3.3-14 Pages TS / B 3.3-15 and TS / B 3.3-16 Pages TS / B 3.3-17 and TS / B 3.3-18 Pages TS / B 3.3-19 through TS / B 3.3-27 Pages TS / B 3.3-28 through TS / B 3.3-31 Pages TS / B 3 3-32 and TS / B 3.3-33 Pages TS / B 3.3-34 through TS / B 3.3-43 IPages TS / B 3.3-43a through TS / B 3.3-43i Pages TS / B 3.3-44 through TS / B 3.3-50 Pages TS / B 3.3-51 through TS / B 3.3-53 Page TS / B 3.3-54' Pages B 3.3.55 through B 3.3-63 Pages TS / B 3.3-64 and TS / B 3.3-65
'Page TS / B13.3-66 Page TS / B 3.3-67, Page TS/B:3.3-68 Pages TS / B 3.3-69 and TS / B 3.3-70 Page TS / Bs3.3-711 Pages TS / 3.3-72 through TS /3.3-75 Page TS/ B 1B3.3-75a Pages TS / B 3.3-75b and TS / B 3.3-75c Pages B 3.3176 through 3.3-77 PageTS/B3.3-78' Pages B 3.3!79 through B 3.3-89 Page TS / B,3.3-90',
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'Section Title Page TS / B 3.3-104 Pages B 3.3-105 and B 3.3-106 Page TS / B 3.3-107 Page B 3.3-108 Page TS / B 3.3-109 Pages B 3.3-110 and B 3.3-111 Pages TS / B 3.3-112 and TS / B 3.3-112a Pages TS / B 3.3-113 and TS / B 3.3-114 Page TS / B 3.3-115 Page TS / B 3.3-116 Page TS / B 3.3-117 Pages B 3.3-118 through B 3.3-122 Pages TS / B 3.3-123 and TS / B 3.3-124 Page TS / B 3.3-124a Page B 3.3-125 Page TS / B 3.3-126 Page TS / B 3.3-127 Pages B 3.3-128 through B 3.3-130 Page TS / B 3.3-131 Pages B 3.3-132 through B 3.3-137 Page TS / B 3.3-138 Pagles B 3.3-139 through B 3.3-149 Page TS'/ B 3.3-150 through TS / B 3.3-162 Page TS / B 3.3-163 Pages TS / B 3.3-164 through TS / B 3.3-177 Pages TS / B 3.3-178 and TS / B 3.3-179 Page TS / B 3.3-179a Page TS / B 3.3-179b Page TS / B 3.3-179c Page TS / B 3.3-180 PageTS/B3.3-181 Pages TS / B 3.3-1 82 through TS / B 3.3-186 Pages TS / B 3.3-187 and TS / B 3.3-188 Pages TS / B 3.3-189 through TS / B 3.3-191 Pages B 3.3-192 through B 3.3-204 Page TS / B 3.3-205' Pages B 3.3-206 through B 3.3-219 REACTOR COOLANT SYSTEM BASES Pages B 3.4-1 and B 3.4-2 Page TS / B 3.4-3'and Page TS I B 3.4-4 Pages TS I B 3.4-5 through TS / B 3.4-9 Pages B 3.4-10 through B 3.4-14 Page TS / B 3.4-15 Pages TS I B 3.4-16 through TS / B 3.4-18 Revision 1
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R-SUSQIJEHANNA STEAM ELECTRIC STATION LIST OF EFFECTIVE SECTIONS (TECHNICAL SPECIFICATIONS BASES)
Section Title Revision Pages B 3.4-19 through B 3.4-27 0
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B 3.6 CONTAINMENTISYSTEMS BASES Page iTS / B 3.6-1 2
PageITS / B 3.6-1a 3
Pages TS / B 13.642 through TS / B 3.6-5 2
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Pages TS / B 3.6 6a and TS / B 3.6-6b 2
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SUSQUEHANNA - UNIT 1 TS I B LOES-4 Revision 69
SUSQUEHANNA STEAM ELECTRIC STATION LIST OF EFFECTIVE SECTIONS (TECHNICAL SPECIFICATIONS BASES) wp)
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SUSQlJEHANNA STEAM ELECTRIC STATION LIST OF EFFECTIVE SECTIONS (TECHNICAL SPECIFICATIONS BASES)
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SUSQLJEHANNA-UNIT I TS/BLOES-6 Revision 69 SUSQ UEHANNA - UNIT I TS I B LOES6 Revision 69
SUSQUEHANNA STEAM ELECTRIC STATION LIST OF EFFECTIVE SECTIONS (TECHNICAL SPECIFICATIONS BASES)
Section Title Revision B 3.9 B 3.10 TSB1 text LOES 3/11/06 REFUELING OPERATIONS BASES Pages TS / B 3.9-1 and TS / B 3.9-1a Pages TS / B 3.9-2 through TS / B 3.9-4 Pages B 3.9-5 through B 3.9-30 I
0 SPECIAL OPERATIONS BASES Page TS / B 3.10-1 Pages B 3.10-2 through B 3.10-31 Page TS/B3.10-32;;
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SUSQUEHANNA - UNIT 1 E
R TS / B LOES-7 Revision 69
PPL. Rev. 5 Secondary Containment B 3.6.4.1 kJ~
B 3.6 AI.
CONTAINMENT SYSTEMS B 3.6.4.1-Secondary Containment BASES BACKGROUND I
The secondary containment structure completely encloses the primary containment structure such that a dual-containment design is utilized to limit the spread of radioactivity to the environment to within limits. The function of the secondary containment is to contain, dilute, and hold up fission products that may leak from primary containment into secondary containment following a Design Basis Accident (DBA)L In conjunction with operation of the Standby Gas Treatment (SGT) System and closured of certain valves whose lines penetrate the secondary containment, the secondary containment is designed to reduce the activity level of the fission products prior to release to the environment and to isolate and contain fission products that are released during certain operations that take place inside primary containment, when primary containment is not required to be OPERABLE, or that take place outside primary containment (Ref. 1).
The secondary containment is a structure that completely encloses the primary containment and reactor coolant pressure boundary components.
This structure forms a control volume that serves to hold up and dilute the fission products. It is possible for the pressure in the control volume to rise relative to the environmental pressure (e.g., due to pump and riotor heat load additions).
The secondary containment boundary consists of the reactor building structure and associated removable walls and panels, hatches, docirs, dampers, sealed penetrations and valves. The secondary containment is divided into Zone I, Zone II and Zone III, each of which must be OPERABLE depending on plant status and the alignment of the secondary containment boundary. Specifically, the Unit 1 secondary containment boundary can be modified to exclude Zone II. Similarly, the Unit 2 secondary containment boundary can be modified to exclude Zone I. Secondary containment may consist of only Zone IlIl when in MODE 4 or 5 during CORE ALTERATIONS, or during handling of irradiated fuel within the Zone IlIl secondary containment boundary.
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SU QUEHANNA - UNIT 1 TS / B 3.6-84 Revision 3
PPL Rev. 5 Secondary Containment B 3.6.4.1 BAS3ES BACKGROUND To prevent ground level exfiltration while allowing the secondary (continued) containment to be designed as a conventional structure, the secondary containment requires support systems to maintain the control volume pressure at less than the external pressure. Requirements for the safety related systems are specified separately in LCO 3.6.4.2, "Secondary Containment Isolation Valves (SCIVs)," and LCO 3.6.4.3, "Standby Gas Treatment (SGT) System." When one or more zones are excluded from secondary containment, the specific requirements for support systems will also change (e.g., required secondary containment isolation valves).
APPLICABLE' There are two principal accidents for which credit is taken for secondary SAFETY containment OPERABILITY. These are a loss of coolant accident lLOCA)
ANALYSES (Ref. 2) and a fuel handling accident inside secondary containment:
(Ref. 3). The secondary containment performs no active function in response to either of these limiting events; however, its leak tightness is required to ensure that the release of radioactive materials from the primary containment is restricted to those leakage paths and associated leakage rates assumed in the accident analysis and that fission products entrapped within the secondary containment structure will be treated by the SGT System prior to discharge to the environment.
Secondary containment satisfies Criterion 3 of the NRC Policy Statement (Ref. 4);
LCO An OPERABLE secondary containment provides a control volume into which fission products that bypass or leak from primary containment, or are released from the reactor coolant pressure boundary components located in secondary containment, can be diluted and processed prior to release to the environment. For the secondary containment to be considered OPERABLE, it must have adequate leak tightness to ensure that the required vacuum can be established !and maintained. The leak tightness of secondary containment must also ensure that the release of radioactive materials to the environment is restricted to those leakage paths and associated leakage rates assumed in the accident analysis. For example, secondary containment bypass leakage must be restricted to the leakage rate required by LCO 3.6.1.3. The secondary containment boundary required to be OPERABLE is depenident on the operating status of both units, as well as the configuration of walls, doors, hatches, SCIVs, and available flow paths to the SGT System.!
(cc'ntinued)
SUSQUEHANNA-UNIT 1 TS / B 3.6-85 Revision 2
PPL. Rev. 5 Secondary Containment B 3.6.4.1 BASES (continued)
APPLICABILITY In MODES 1, 2, and 3, a LOCA could lead to a fission product release to primary containment that leaks to secondary containment. Therefore, secondary containment OPERABILITY is required during the same operating conditions that require primary containment OPERABILITY.
In MODES 4 and 5, the probability and consequences of the LOCA are reduced due to the pressure and temperature limitations in these MODES.
Therefore, maintaining secondary containment OPERABLE is not required in MODE 4 or 5 to ensure a control volume, except for other situations for which significant releases of radioactive material can bhe 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 If secondary containment is inoperable, it must be restored to OPERABLE status within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. 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 the problem that is commensurate with the importance of maintaining secondary containment during MODES 1, 2, and 3. This time period also ensures that the probability of an accident (requiring secondary containment OPERABILITY) occurring during periods where secondary containment is inoperable is minimal.
A temporary (one-time) Completion Time is connected to the Completion Time Requirements above (4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />) with an "OR" connector. The Temporary Completion Time is 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> and applies to the replacement of the Reactor Building Recirculating Fan Damper Motors. The Temporary Comnpletion Time of 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> may only be used once, and expires on December 31, 2005.
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SUSQUEHANNA - UNIT I TS / B 3.6-86 Revision 3
PPL. Rev. 5 Secondary Containment B 3.6.4.1 BASES ACTIONS (c:)ntinued) 1 I
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B.1 and B.2 If secondary containment 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 oil 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, and C.3 Movement of irradiated fuel assemblies in the secondary containment, CORE ALTERATIONS, and OPDRVs can be postulated to cause fission product release to the secondary containment. In such cases, the secondary containment is the only barrier to release of fission products to the environment. CORE ALTERATIONS and movement of irradiated fuel assemblies must be immediately suspended if the secondary containment is inoperable.
Suspension of these activities shall not preclude completing an action that involves moving a component to a safe position. Also, action must be immediately initiated to suspend OPDRVs to minimize the probability of a vessel draindown and subsequent potential for fission product release.
Actions must continue until OPDRVs are suspended.
Required Action C.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 a sufficient reason to require a reactor shutdown.
SU RVEILLANCE SRI 3.6.4.1.1 REQUIREMENTS lThis SR ensures that the secondary containment boundary is suff iciently leak tight to preclude exfiltration.
(continued)
SU LSQUEHANNA - UNIT 1 TS / B 3.6-87 Revision 1
PPL Rev. 5 Secondary Containment
- B 3.6.4.1 BASES SURVEILLANCE
~1 lORUrK^U-re SR 3.6.4.1.1 (continued)
MMMILU
~vr The 24.hour Frequency of this SR was developed based on operating experience related to secondary containment vacuum variations duiing the applicable MODES and the low probability of a DBA occurring between surveillances.
Furthermore, the 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> Frequency is considered adequate in viev/ of other indications available in the control room, including alarms, to alert the operator to an abnormal secondary containment vacuum condition.
SR 3.6.4.1.2 and SR 3.6.4.1.3 Verifying that secondary containment equipment hatches, removable walls and one access door in each access opening required to be closed are closed ensures that the infiltration of outside air of such a magnitude as to prevent maintaining the desired negative pressure does not occur.
Verifying that all such openings are closed also provides adequate assurance that exfiltration from the secondary containment will not occur.
In this application, the term "sealed" has no connotation of leak tightness.
An access opening typically contains one inner and one outer door.
Maintaining secondary containment OPERABILITY requires verifying one door in each access opening to secondary containment zones is closed.
in some cases (e.g., railroad bay), secondary containment access openings are shared such that a secondary containment barrier may have multiple inner or multiple outer doors. The intent is to maintain the secondary containment barrier intact, which is achieved by maintaining the inner or outer portion of the barrier closed at all times. However, all secondary containment access doors are normally kept closed, except when the access opening is being used for entry and exit or when maintenance is being performed on an access opening.
IWhen the railroad bay door (No. 101) is closed; all Zone I and ill hatches, removable walls, dampers, and one door in each access opening
' connected to the railroad access bay are closed; or, only Zone I removable walls and/or doors are open to the railroad access shaft; or, only Zone IlIl hatches and/or dampers are open to the railroad access shaft. 'When the railroad bay door (No. 101)' is open; all Zone I and IlIl hatches, removable walls, dampers, and one door in each access opening connected to the railroad access bay are closed. The truck bay hatch is closed and the truck bay door (No. 102) is closed unless Zone II is isolated from Zones I and Ill.
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,QUEHANNA - UNIT 11 I
A; TS / B 3.6-88 Revision 2
PPI Rev. 5 Secondary Containment E: 3.6.4.1 BASES SURVEILLANCE SR 3.6.4.1.2 and SR 3.6.4.1.3 (continued)
REQUIREMENTS When an access opening between required secondary containmert zones is being used for exit and entry, then at least one door (where two doors are provided) must remain closed. The access openings between secondary containment zones which are not provided with two doors are administratively controlled to maintain secondary containment integrity during exit and entry. This Surveillance is modified by a Note that allows access openings with a single door (i.e., no airlock) within the secondary containment boundary (i.e., between required secondary containment zones) to be opened for entry and exit. Opening of an access doo:^ for entry and exit allows sufficient administrative control by individual personnel making the entries and exits to assure the secondary containment function is not degraded. When one of the zones is not a zone required for secondary containment OPERABILITY, the Note allowance would not apply.
The 31 day Frequency for these SRs has been shown to be adequate, based on operating experience, and is considered adequate in view of the other indications of door and hatch status that are available to the operator.
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SUSQUEHANNA - UNIT 1
. I TS / B 3.6-88a RE!ViSion 2
PPL Rev. 5 Secondary Containment B 3.6.4.1 BAE;ES SUR VEIL REQUIRE (ccntinui LA NCE SR 3.6.4.1.4 and SR 3.6.4.1.5 WMENTS ed)
The SGT System exhausts the secondary containment atmosphere to the environment through appropriate treatment equipment. To ensure that all fission products are treated, SR 3.6.4.1.4 verifies that the SGT System will rapidly establish and maintain a pressure in the secondary containment that is less than the pressure external to the secondary containment:
boundary. This is confirmed by demonstrating that one SGT subsystem will draw clown the secondary containment to 2 0.25 inches of vacuum water gauge in less than or equal to the maximum time allowed. This cannot be accomplished if the secondary containment boundary is not intact. SR 3.6.4.1.5 demonstrates that one SGT subsystem can maintain
- 0.25 inches of vacuum water gauge for at least 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> at less than or equal to the maximum flow rate permitted for the secondary containment configuration that is operable. The 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> test period allows secondary containment to be in thermal equilibrium at steady state conditions. As noted, both SR 3.6.4.1.4 and SR 3.6.4.1.5 acceptance limits are dependent upon the secondary containment configuration when testing is being performed. The acceptance criteria for the SRs based on secondary containment configuration is defined as follows
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Ippli SECONDARY MAXIMUM DRAWDOWN TIME(SEC)
MAXIMUM FLOW RATE (3FM)
CONTAINMENT (SR 3.6.4.1.4 (SR 3.6.4.1.5 TEST CONFIGURATION ACCEPTANCE CRITERIA)
ACCEPTANCE CRITERIA)
Zcnes I. II and III.
< 125 Seconds
- 4000 CFM (Zones 1,11, and III)
(From Zones 1,11, and I11)
Zcnes landII.
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- 117 Seconds 2885CFM (Zones I and III)
(From Zones I and I1I)
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I IKIT d1 TS / B 3.6-89 Revision 3 owu,LI L1 11iI'4I1P'1
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PPL. Rev. 5 Secondary Containment B 3.6.4.1 BASES SURVEILLANCE SR 3.6.4.1.4 and SR 3.6.4.1.5 (continued)
REQUIREMENTS Only one of the above listed configurations needs to be tested to confirm secondary containment OPERABILITY.
A Note also modifies the Frequency for each SR. This Note identifies that each configuration is to be tested every 60 months. Testing each configuration every 60 months assures that the most limiting configuration is tested every 60 months. The 60 month Frequency is acceptable because operating experience has shown that these components usually pass the Surveillance and all active components are tested more frequently. Therefore, these tests are used to ensure secondary containment boundary integrity.
Since these SRs are secondary containment tests, they need not be performed with each SGT subsystem. The SGT subsystems are tested on a STAGGERED TEST BASIS, however, to ensure that in addition to the requirements of LCO 3.6.4.3, either SGT subsystem will perform SR 3.6.4.1.4 and SR 3.6.4.1.5. Operating experience has shown these components usually pass the Surveillance when performed at the
- 24 month Frequency. Therefore, the Frequency was concluded to be acceptable from a reliability standpoint.
REFERENCES
- 1. FSAR, Section 6.2.3.
- 2. FSAR, Section 15.6.
- 3. FSAR, Section 15.7.4.
- 4. Final Policy Statement on Technical Specifications Improvemerts, July 22,: 1993 (58 FR 39132).
SUSQUEHANNA-UNIT 1 TS / B 3.6-90 Revision 2