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 of 2 MANUAL HARD COPY DISTRIBUTION DOCUMENT TRANSMITTAL 2006-12371 USER INFORMATION:
GERLACH*ROS3E M EMPL#:028401 CA#: 0363 Address: NUCSA2 Phone#: 254-3194 TRANSMITTAL INFORMATION:
TO: GERLACH*ROSE M 03/17/2006 LOCATION: USNRC FROM: NUCLEAR RECORDS DOCUMENT CONTROL CENTER (NUCSA-2)
THE FOLLOWING CHANGES HAVE OCCURRED TO THE HARDCOPY OR ELECTRONIC MANUAL ASSIGNED TO YOU. HARDCOPY USERS MUST ENSURE THE DOCUMENTS PROVIDED MATCH THE INFORMATION ON THIS TRANSMITTAL. WHEN REPLACING THIS MATERIAL IN YOUR HARDCOPY MANUAL, ENSURE THE UPDATE DOCUMENT ID IS THE SAME DOCUMENT ID YOU'RE REMOVING FROM YOUR MANUAL. TOOLS FROM THE HUMAN PERFORMANCE TOOL BAG SHOULD BE UTILIZED TO ELIMINATE THE CHANCE OF ERRORS.
ATTENTION: "REPLACE" directions do not affect the Table of Contents, Therefore no TOC will be issued with the updated material.
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 of 2 ID: TEXT 3.6.4.1 REMOVE: REV:4 ADD: REV: 5 CATEGORY: DOCUMENTS TYPE: TSB1 ID: TEXT LOES REMOVE: REV:68 ADD: REVT: 69 ANY DISCREPANCIES WITH THE MATERIAL PROVIDED, CONTACT DCS @ X3107 OR X3136 FOR ASSISTANCE. UPDATES FOR HARDCOPY MANUALS WILL BE DISTRIBUTED WITHIN 5 DAYS IN ACCORDANCE WITH DEPARTMENT PROCEDURES. PLEASE MAKE ALL CHANGES AND ACKNOWLEDGE COMPLETE ::N YOUR NIMS INBOX UPON COMPLETION OF UPDATES. FOR ELECTRONIC MANUAL USERS, ELECTRONICALLY REVIEW THE APPROPRIATE DOCUMENTS AND ACKNOWLEDGE COMPLETE IN YOUR NIMS INBOX.
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 1 08/30/2005
Title:
REACTIVITY CONTROL 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 0 11/22/2004
Title:
OPRM INSTRUMENTATION 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)
Report Date: 03/16/06 Page *2 Page of of 8 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 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 1 11/09/2004
Title:
INSTRUMENTATION PRIMARY CONTAINMENT ISOLATION INSTRUMENTATION TEXT 3.3.6.2 1 1/09/2004.
Title:
INSTRUMENTATION SECONDARY CONTAINMENT ISOLATION INSTRUMENTATION TEXT 3.3.7.1 0 11/15/2002
Title:
INSTRUMENTATION CONTROL ROOM EMERGENCY OUTSIDE AIR SUPPLY (CREOAS) SYSTEM INSTRUMENTATION TEXT 3.3.8.1 1 09/02/2004
Title:
INSTRUMENTATION LOSS OF POWER (LOP) INSTRUMENTATION TEXT 3.3.8.2 0 11/15/2002
Title:
INSTRUMENTATION REACTOR PROTECTION SYSTEM (RPS) ELECTRIC POWER MONITORING TEXT 3.4.1 2 11/22/2004
Title:
REA.CTOR COOLANT SYSTEM (RCS) RECIRCULATION LOOPS OPERATING TEXT 3.4.2 0 11/15/2002
Title:
REA.CTOR COOLANT SYSTEM (RCS) JET PUMPS Report Date: 03/16/06 Page33 Page of of 88 Report Date: 03/16/06
SSES MANUAL Manual Name: TSB1 y Manual
Title:
TECHNICAL SPECIFICATION BASES UNIT 1 MANUAL TEXT 3.4.3 1 01/16/2006
Title:
REACTOR COOLANT SYSTEM (RCS) SAFETY/RELIEF VALVES (S/RVS)
TEXT 3.4.4 0 11/15/2002
Title:
REACTOR COOLANT SYSTEM (RCS) RCS OPERATIONAL LEAKAGE TEXT 3.4.5 1 01/16/2006
Title:
REACTOR COOLANT SYSTEM (RCS) RCS PRESSURE ISOLATION VALVE (PIV) LEAKAGE TEXT 3.4.6 1 04/18/2005
Title:
REACTOR COOLANT SYSTEM (RCS) RCS LEAKAGE DETECTION INSTRUMENTATION TEXT 3.4.7 1 04/18/2005
Title:
REACTOR 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 0 11/15/2002.
Title:
REACTOR COOLANT SYSTEM (RCS) RESIDUAL HEAT REMOVAL (RHR) SHUTDOWN COOLING SYSTEM
- COLD SHUTDOWN TEXT 3.4.10 0 11/15/2002
Title:
REACTOR COOLANT 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 (RCIC)
SYSTEM ECCS - OPERATING TEXT 3.5.2 0 11/15/2002
Title:
EMERGENCY CORE COOLING SYSTEMS (ECCS) AND REACTOR CORE ISOLATION COOLING (RCIC)
SYSTEM ECCS - SHUTDOWN TEXT 3.5.3 1 04/18/2005
Title:
EMERGENCY CORE COOLING SYSTEMS (ECCS) AND REACTOR CORE ISOLATION COOLING (RCIC)
SYSTEM RCIC SYSTEM Report Date: 03/16/06 Page44 Page of of 88 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 3 12/08/2005
Title:
CONTAINMENT SYSTEMS PRIMARY CONTAINMENT ISOLATION VALVES (PCIVS)
TEXT 3.6.1.4 0 11/15/2002
Title:
CONTAINMENT SYSTEMS CONTAINMENT PRESSURE TEXT 3.6.1.5 1 10/05/2005
Title:
CONTAINMENT SYSTEMS DRYWELL AIR TEMPERATURE TEXT 3.6.1.6 0 11/15/2002 Qji
Title:
CONTAINMENT SYSTEMS SUPPRESSION CHAMBER-TO-DRYWELL VACUUM BREAKERS TEXT 3.6.2.1 0 11/15/2002.
Title:
CONTAINMENT SYSTEMS SUPPRESSION POOL AVERAGE TEMPERATURE TEXT 3.6.2.2 0 11/15/2002
Title:
CONTAINMENT SYSTEMS SUPPRESSION POOL WATER LEVEL TEXT 3.6.2.3 1 01/16/2006
Title:
CONTAINMENT SYSTEMS RESIDUAL HEAT REMOVAL (RHR) SUPPRESSION POOL COOLING TEXT 3.6.2.4 0 11/15/2002
Title:
CONTAINMENT SYSTEMS RESIDUAL HEAT REMOVAL (RHR) SUPPRESSION POOL SPRAY TEXT 3.6.3.1 1 04/18/2005
Title:
CONTAINMENT SYSTEMS PRIMARY CONTAINMENT HYDROGEN RECOMBINERS TEXT 3.6.3.2 1 04/18/2005
Title:
CONTAINMENT SYSTEMS DRYWELL AIR FLOW SYSTEM Report Date: 03/16/06 PageS5 Page of of 88 Report Date: 03/16/06
SSES MANUAL Manual Name: TSB1 Manual
Title:
TECHNICAL SPECIFICATION BASES UNIT 1 MANUAL TEXT 3.6.3.3 0 11/15/2002
Title:
CONTAINMENT SYSTEMS PRIMARY CONTAINMENT OXYGEN CONCENTRATION TEXT 3.6.4.1 5 03/16/2006 ,
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 3 10/24/2005
Title:
CONTAINMENT SYSTEMS STANDBY GAS TREATMENT (SGT) SYSTEM TEXT 3.7.1 0 11/15/2602
Title:
PLANT SYSTEMS RESIDUAL HEAT REMOVAL SERVICE WATER (RHRSW) SYSTEM AND THE ULTIMATE HEAT SINK (UHS)
TEXT 3.7.2 1 11/09/2004
Title:
PLANT 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 0 11/15/2002
Title:
PLANT SYSTEMS SPENT FUEL STORAGE POOL WATER LEVEL TEXT 3.8.1 3 10/05/2005
Title:
ELECTRICAL POWER SYSTEMS AC SOURCES - OPERATING Report Date: 03/16/06 Page 66 Page of of 88 Report Date: 03/16/06
SSES MANUAL d, Manual Name: TSB1 Manual
Title:
- TECHNICAL SPECIFICATION BASES UNIT 1 MANUAL TEXT 3.8.2 0 11/15/2002
Title:
ELECTRICAL POWER SYSTEMS AC SOURCES - SHUTDOWN TEXT 3.8.3 0 11/15/2002
Title:
ELECTRICAL POWER SYSTEMS DIESEL FUEL OIL, LUBE OIL, AND STARTING AIR TEXT 3.8.4 0 11/15/2002
Title:
ELECTRICAL POWER SYSTEMS DC SOURCES - OPERATING TEXT 3.8.5 0 11/15/2002
Title:
ELECTRICAL POWER SYSTEMS DC SOURCES - SHUTDOWN TEXT 3.8.6 0 11/15/2002
Title:
ELECTRICAL POWER SYSTEMS BATTERY CELL PARAMETERS TEXT 3.8.7 1 10/05/2005 to
Title:
ELECTRICAL POWER SYSTEMS DISTRIBUTION SYSTEMS - OPERATING TEXT 3.8.8 0 11/15/2002.
Title:
ELECTRICAL POWER SYSTEMS DISTRIBUTION SYSTEMS - SHUTDOWN TEXT 3.9.1 0 11/15/2002
Title:
REFUELING OPERATIONS REFUELING EQUIPMENT INTERLOCKS TEXT 3.9.2 0 11/15/2002
Title:
REFUELING OPERATIONS REFUEL POSITION ONE-ROD-OUT INTERLOCK TEXT 3.9.3 0 11/15/2002
Title:
REFUELING OPERATIONS CONTROL ROD POSITION TEXT 3.9.4 0 11/15/2002
Title:
REFUELING OPERATIONS CONTROL ROD POSITION INDICATION TEXT 3.9.5 0 11/15/2002
Title:
REFUELING OPERATIONS CONTROL ROD OPERABILITY - REFUELING Report Date: 03/16/06 Page 7 Page 7 of of 88 Report Date: 03/16/06
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) WATER LEVEL 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 0 11/15/2002
Title:
SPECIAL OPERATIONS INSERVICE LEAK AND HYDROSTATIC TESTING OPERATION TEXT 3.10.2 0 11/15/2002
Title:
SPECIAL OPERATIONS REACTOR MODE SWITCH INTERLOCK TESTING TEXT 3.10.3 0 11/15/2002
Title:
SPECIAL OPERATIONS SINGLE CONTROL ROD WITHDRAWAL - HOT SHUTDOWN Y-N TEXT 3.10.4 0 11/15/2002.
Title:
SPECIAL OPERATIONS SINGLE CONTROL ROD WITHDRAWAL - COLD SHUTDOWN TEXT 3.10.5 0 11/15/2002
Title:
SPECIAL OPERATIONS SINGLE CONTROL ROD DRIVE (CRD) REMOVAL - REFUELING TEXT 3.10.6 O 11/15/2002
Title:
SPECIAL OPERATIONS MULTIPLE CONTROL ROD WITHDRAWAL - REFUELING TEXT 3.10.7 0 11/15/2002
Title:
SPECIAL OPERATIONS CONTROL ROD TESTING - OPERATING TEXT 3.10.8 0 11/15/2002
Title:
SPECIAL OPERATIONS SHUTDOWN MARGIN (SDM) TEST - REFUELING Report Date: 03/16/06 Page8 Page 8 of of 8 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 Page TS I B 3.1-23 1 Pages B 3.1-24 thrwugh B 3.1-27 ,0 PageTS/B3.1-28 1 PageTS/B3.1-29 1 Pages B 3.1-30 through B 3.1-33 0 Pages TS / B 3.3-34 through TS / B 3.3-36 1 PageTS/B3.1-37 .2 Page'TS / B 3.1-38 1
<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 Titil
- rX. I Revision Page B 3.2-7 0 Pages TS / B 3.2-8,through TS / B 3.2-10 1 D . I
. L Page TS / B 3.2-11 2 Page B 3.2-12 0
. Page TS / B 3.2-13 2 Pages B 3.2114 and B 3.2-15 0 Page TS / B 3.2-16 ' 2 Pages B 3.2-17 and B 3.2-18 0 Page TS / B3.2-19 3 I. B 3.3,: INSTRUMENTATION Pages TS / B 3.3-1 through TS / B 3.3-4 I 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
. L Pages TS / B 3.3-15 and TS / B 3.3-16 Pages TS / B 3.3-17 and TS / B 3.3-18 IIi 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 1%,W' 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 / B1 3.3-66 Page TS / B3.3-67, Page TS/B:3.3-68 I
Pages TS / B 3.3-69 and TS / B 3.3-70 i Page TS / Bs3.3-711 i Pages TS / 3.3-72 through TS /3.3-75 i
, i
. Page TS/ B1B3.3-75a Pages TS / B 3.3-75b and TS / B 3.3-75c I
i I Pages B 3.3176 through 3.3-77 I II m PageTS/B3.3-78' i l i
II I
4 Pages B 3.3!79 through B 3.3-89 Page TS / B,3.3-90',
Ii I Page B 3.3-91 i i m
I Page TS / Bl3.3-92 through TS / B.3.3-100 I
Pages B 3.3-101 through B 3.3-103
'opr TS/BLOES-2 Revision 69 SUSQUEHANNA - UNIT SUSQUEHANNA -
UNIT ,1I TS / B LOES-2 Revision 69
. i I
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SUSQIJEHANNA STEAM ELECTRIC STATION LIST COF EFFECTIVE SECTIONS (TECHNICAL SPECIFICATIONS BASES)
'Section Title Revision 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 Page B 3.3-108 0 Page TS / B 3.3-109 1 Pages B 3.3-110 and B 3.3-111 0 Pages TS / B 3.3-112 and TS / B 3.3-112a 1 Pages TS / B 3.3-113 and TS / B 3.3-114 1 Page TS / B 3.3-115 1 Page TS / B 3.3-116 2 Page TS / B 3.3-117 1 Pages B 3.3-118 through B 3.3-122 0 Pages TS / B 3.3-123 and TS / B 3.3-124 1 Page TS / B 3.3-124a 0 Page B 3.3-125 0 Page TS / B 3.3-126 1 Page TS / B 3.3-127 1 Pages B 3.3-128 through B 3.3-130 0 Page TS / B 3.3-131 1 Pages B 3.3-132 through B 3.3-137 0 Page TS / B 3.3-138 1 Pagles B 3.3-139 through B 3.3-149 Page 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 Page TS / B 3.3-179a 2 Page TS / B 3.3-179b 0 Page TS / B 3.3-179c 0 Page TS / B 3.3-180 1 PageTS/B3.3-181 2 Pages TS / B 3.3-1 82 through TS / 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 Page TS / B 3.4-3'and Page TS I B 3.4-4 3 Pages TS I 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 I B 3.4-16 through TS / B 3.4-18 2 TS/BLOES-3 Revision 69 SUSQUEHANNA--UNIT SUSQUEHANNA UNIT I1 TS / B LOES-3 Revisionl 69 I ,I
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 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 / B 3.4-41 1 Pages B 3.4-42 through B 3.4-48 0 Page TS / B 3.4-49 2 Page TS / B 3.4-50 1 Page TS / B 3.4-51 2 Pages TS / B 3.4-52 and TS I B 3.4-53 1 Page TS / B.3.4-54 2 Page TS / B 3.4-55 2 Page TS / B 3.4-56 1 PageTS/ B 3.4-57 2 Pages TS / B 3.4-58 through TS / B 3.4-60 1 B 3.5 ECCS AND RCIC BASES Pages B 3.5-1 and B 3.5-2 0 Page TS / B!3.5-3 2 Page TS / B 3.5-4 1 Page TS / B 3.5-5. - 2 Page7TS/B3.5-6 I Pages B 3.5-7 through B 3.5-10 0 Page TS / B 3.5-11' 1 PageTS/B3.5-12 0 Page TS / B3.5-13 I PageTS/B3.5-14 and;TS/B3.5-15 0 Pages TS I B,3.5-16 through TS / B 3.5-18 1 Pages B 3.5 1l9 through B 3.5-24 0 Page TS I B 3.5-25 1 Pages TS i B l3.5-26 and TS I B 3.5-27 1 Pages B 3.5-28 throughi B 3.5-31 0 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 Page TS / B 3.6-6 ' l 3 Pages TS / B 3.6 6a and TS / B 3.6-6b 2 PageTS / B 3.6-6c 0 Pages B 3.6-`7 through B 3.6-14 0 Page'TS B 3.6-15 2 SUSQUEHANNA - UNIT 1 TS I B LOES-4 Revision 69
SUSQUEHANNA STEAM ELECTRIC STATION LIST OF EFFECTIVE SECTIONS (TECHNICAL SPECIFICATIONS BASES) wp) Section Title Revision Pages TS / B 3.6-15a and TS / B 3.6-15b 0 Page B 3.6-16 0 Page TS / B 3.6-17 1 Page TS / B 3.6-17a 0 Pages TS / B 3.6-18 and TS / B 3.6-19 0 Page TS / B 3.6-20 I Page TS / B 3.6-21 2 Page TS / B 3.6-22' I Page TS / B 3.6-22a 0 Page TS / B 3.6-23l I Pages TS / B 3.6-24 through TS I B 3.6-25 0 Page TS / B 3.6-26! I Page TS / B 3.6-27 2 Page TS / B 3.6-28 5 Page TS / B 3.6-29 I Page TS / B 3.6-30' I Page TS / B 3.6-31 3 Page B 3.6-32 0 Page TS / B 3.6-33 I Pages B 3.6-34 and B 3.6-35 0 Page TS / B 3.6-36i I Page B 3.6-37 I *0 Page TS / B 3.6-38! I Page B 3.6-39 0 Page TS / B 3.6-40, 4 Pages B 3.6-41 through B 3;6-43 3 Pages TS / B 3.6-44 and TS / B 3.6-45 I Page TS / B 3.6-46 2 Pages TS / B 3.6-47, through TS / B 3.6-51 I Page TS / B 3.6-52 2 Pages B 3.6-53 through B 3.6-63 0 Pages TS I B 3.6-,64 and TS / B 3.6-65 I Pages B 3.6-66 through B 3.6-72 0 Page TS' B 3.6-731i I Pages B 3.6-74 through B 3.6-77 0 PageTSIB3.6-78l I Pages B 3.6-79 through B 3.3.6-83 0 '
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Sectior Title RevisiDn Pages TS / B 3.6-92 through TS / B 3.6-96 I Page TS /B 3.6-97 2 Pages TS I B 3.6-98 and TS / B 3.6-99 . 1 Page TS / B 3.6-100 2 Pages TS / B 3.6-101 and TS / B 3.6-102 1 Pages TS / B 3.6-103 and TS / B 3.6-104 2 Page TS / B 3.6-105 3 Pages TS B 3.6-106 and TS / B 3.6-107 2 B 3.7 PLANT SYSTEMS BASES Pages TS / B 3.7-1 through TS / B 3.7-6 2 Page TS / B 3.7-6a 2 Pages TS / B 3 3.7-6b and TS / B 3.7-6c 0 .
PageTS/B3.7-7 2 Pages TS / B 3.7-8 through TS / B 3.7-11 1 Pages TS / B 3.7-12 and TS / B 3.7-13 1 Pages TS / B 3.7-14 through TS / B 3.7-18 2 Page TS / B 3.7-18a 0 Pages TS / B 3.7-19 through TS / B 3.7-23 1 Pages B 3.7-24 through B 3.7-26 0 Pages TS / B 3.7-27 through TS / B 3.7-29 4 Pag'eTS/B3.7-30 2 Pages B 3.7-31 -through B 3.7-33 0 B 3.8 ELECTRICAL POWER SYSTEMS BASES Pages TS / B 3.8-1 through TS / B 3.8-4 2 Page TS /IB 3.8-5 4 PageTS/B3.8-6 3 Pages TS / B 3.8-7 through TS/B 3.8-8 2 Page TS / B 3.8-9 4 Page TS / B 3.8-10 3 Pages TS / B 3.8-11 and TS / B 3.8-17 2 Page TS/B,3.8-18 3 Pages TS / B ,3.8-19 through TS / B 3.8-21 2 Pages TS / B 3.8-22 and TS / B 3.8-23 3 Pages TS / B 3.8-24 through TS / B 3.8-37 2 Pages B 3.8-38 through B 3.8-53 0 Pages TS / B 3.8-54 through TS / B 3.8-61 1 PageITS / B,3.8-62 2 Page'TS i B 3.8-63 2 Page TS I B 3.8-64 1 Page TS I B 3.8-65 2 Pages B 3.8-66 through B 3.8-80 0 Page TS / B 3.8-81' 1 Pages B 3.8-82 through B 3.8-90 0 TS/BLOES-6 Revision 69 SUSQ UEHANNA - UNIT II SUSQLJEHANNA- TS I B LOES6 Revision 69
SUSQUEHANNA STEAM ELECTRIC STATION LIST OF EFFECTIVE SECTIONS (TECHNICAL SPECIFICATIONS BASES)
Section Title Revision B 3.9 REFUELING OPERATIONS BASES Pages TS / B 3.9-1 and TS / B 3.9-1a I Pages TS / B 3.9-2 through TS / B 3.9-4 Pages B 3.9-5 through B 3.9-30 0 B 3.10 SPECIAL OPERATIONS BASES Page TS / B 3.10-1 I Pages B 3.10-2 through B 3.10-31 0 Page TS/B3.10-32;; I Pages B 3.10-33 through B 3.10-37 0 Page TS/B3.10-38 I TSB1 text LOES 3/11/06 SUSQUEHANNA - UNIT 1 E TS / B LOES-7 R Revision 69
PPL. Rev. 5 Secondary Containment B 3.6.4.1 AI .
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B 3.6 CONTAINMENT SYSTEMS B 3.6.4.1- Secondary Containment BASES BACKGROUND 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 I
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. I 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.
(continued)
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.
(co ntin ued)
SUSQUEHANNA - UNIT I TS / B 3.6-86 Revision 3
PPL. Rev. 5 Secondary Containment B 3.6.4.1 BASES ACTIONS B.1 and B.2 (c:)ntinued)
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 1 :
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 I
power conditions in an orderly manner and without challenging plant systems.
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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 sufficiently 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 SR 3.6.4.1.1 (continued)
MMMILU
~1 lORUrK^U-re 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 I 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 I assurance that exfiltration from the secondary containment will not occur.
In this application, the term "sealed" has no connotation of leak tightness.
~vr 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.
I 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 I
.I II 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, i
only Zone IlIl hatches and/or dampers are open to the railroad access i shaft. 'Whenthe railroad bay door (No. 101)' is open; all Zone I and IlIl i
i hatches, removable walls, dampers, and one door in each access opening i connected to the railroad access bay are closed. The truck bay hatch is Ii i
closed and the truck bay door (No. 102) is closed unless Zone II is isolated from Zones I and Ill. [
(continued)
!t SU%, ,QUEHANNA - UNIT 11 TS / B 3.6-88 Revision 2 I . A;
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 TS / B 3.6-88a RE!ViSion 2
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PPL Rev. 5 Secondary Containment B 3.6.4.1 BAE;ES SUR VEIL LA NCE SR 3.6.4.1.4 and SR 3.6.4.1.5 REQUIREWMENTS (ccntinuied) 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
SECONDARY MAXIMUM DRAWDOWN TIME(SEC) MAXIMUM FLOW RATE (3FM)
CONTAINMENT * (SR 3.6.4.1.4 (SR 3.6.4.1.5 ACCEPTANCE CRITERIA) ACCEPTANCE CRITERIA)
TEST CONFIGURATION I
Zcnes I. II and III. < 125 Seconds *4000 CFM
- - (Zones 1,11, and III) (From Zones 1,11, and I11)
I .1q Zcnes landII. ;l ;117 Seconds . 2885CFM I (Zones I and III) (From Zones I and I1I)
I f 1
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(continued)
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I IKIT UI'II I d1 I TS / B 3.6-89 Revision 3
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