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 of 2 MANUAL HARD COPY DISTRIBUTION DOCUMENT TRANSMITTAL 2006-41722 USER INFORMATION:
GERLACH*ROSE M EMPL#:028401 CA#: 0363 Address: NUCSA2 Phone#: 254-3194 r1RANVMTTTAT. TMPhORMATTlNV TO: GERLACH*ROSE M 10/02/2006 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.
TSBI - TECHNICAL SPECIFICATION BASES UNIT 1 MANUAL REMOVE MANUAL TABLE OF CONTENTS DATE: 09/26/2006 ADD MANUAL TABLE OF CONTENTS DATE: 09/29/2006 CATEGORY: DOCUMENTS TYPE: TSB1 Aow
Oct. 02, 2006 Page 2 of 2 ID: TEXT 3.1.4 REMOVE: REV:2 ADD: REV: 3 CATEGORY: DOCUMENTS TYPE: TSB1 ID: TEXT LOES REMOVE: REV:77 ADD: REV: 78 CATEGORY: DOCUMENTS TYPE: TSB1 ID: TEXT TOC REMOVE: REV:10 ADD: REV: 11 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 IN 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 j Manual Name: TSBI-inual
Title:
TECHNICAL SPECIFICATION BASES UNIT 1 MANUAL Table Of Contents Issue Date: 09/29/2006 Procedure Name Rev Issue Date Change ID Change Number TEXT LOES 78 09/29/2006
Title:
LIST OF EFFECTIVE SECTIONS TEXT TOC 11 09/29/2006
Title:
TABLE OF CONTENTS TEXT 2.1.1 2 04/18/2006
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 04718/2006
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 3 09/29/2006
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 2 04/18/2006
Title:
REACTIVITY CONTROL SYSTEMS ROD PATTERN CONTROL Report Date: 09/29/06 Pagel Page I of of 88 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 1 10/19/2005
Title:
REACTIVITY CONTROL 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 3 04/12/2006
Title:
INSTRUMENTATION 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 1 04/18/2005
Title:
INSTRUMENTATION REMOTE SHUTDOWN SYSTEM Page 2 of 8 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 1 11/09/2004
Title:
INSTRUMENTATION PRIMARY CONTAINMENT'ISOLATION INSTRUMENTATION TEXT 3.3.6.2 1 11/09/2004
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) ELECTRICPOWER MONITORING TEXT 3.4.1 3 04/12/2006
Title:
REACTOR COOLANT SYSTEM (RCS) RECIRCULATION LOOPS OPERATING TEXT 3.4.2 0 11/15/2002
Title:
REACTOR COOLANT SYSTEM (RCS) JET PUMPS
-TEXT 3.4.3 1 01/16/2006
Title:
REACTOR COOLANT SYSTEM (RCS) SAFETY/RELIEF VALVES (S/RVS)
Report Date: 09/29/06 Page3 Page 3 of of 8 8 Report Date: 09/29/06
SSES MANUAL 4-Manual Name: TSBI-Manual
Title:
TECHNICAL SPECIFICATION BASES UNIT 1 MANUAL 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
- 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 2 05/10/2006
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 TEXT 3.6.1.1 . 0 11/15/2002
Title:
CONTAINMENT SYSTEMS PRIMARY CONTAINMENT Report Date: 09/29/06 Page 4 Page 4 of of 8 8 Report Date: 09/29/06
SSES MANUAL Manual Name: TSBI-Manual
Title:
TECHNICAL SPECIFICATION BASES UNIT 1 MANUAL TEXT 3.6.1.2 0 11/15/2002
Title:
CONTAINMENT 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
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 2 06/13/2006
Title:
CONTAINMENT SYSTEMS PRIMARY CONTAINMENT HYDROGEN RECOMBINERS TEXT 3.6.3.2 1 04/18/2005
Title:
CONTAINMENT SYSTEMS DRYWELL AIR FLOW SYSTEM TEXT 3.6.3.3 0 11/15/2002
Title:
CONTAINMENT SYSTEMS PRIMARY CONTAINMENT OXYGEN CONCENTRATION Report Date: 09/29/06 PageS Page 5 of of 88 Report Date: 09/29/06
SSES MANUAL Manual Name: TSBI- 'ii 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 TEXT 3.7.1 0 . 11/15/2002
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 K)
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 4 04/18/2006
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 0 11/15/2002
Title:
ELECTRICAL POWER SYST'EMS DIESEL FUEL OIL, LUBE OIL, AND STARTING AIR TEXT 3.8.4 1 06/13/2006
Title:
ELECTRICAL POWER SYST'EMS DC SOURCES - OPERATING TEXT 3.8.5 0 11/15/2002
Title:
ELECTRICAL POWER SYST'EMS DC SOURCES - SHUTDOWN TEXT 3.8.6 0 11/15/2002
Title:
ELECTRICAL POWER SYST'ENS BATTERY CELL PARAMETERS TEXT 3.8.7 1 10/05/2005
Title:
ELECTRICAL POWER SYST'EMS DISTRIBUTION SYSTEMS - OPERATING TEXT 3.8.8 0 11/15/2002
Title:
ELECTRICAL POWER SYST'EMS DISTRIBUTION SYSTEMS - SHUTDOWN TEXT 3.9.1 0 11/15/2002
Title:
REFUELING C)PERATIONS REFUELING EQUIPMENT INTERLOCKS TEXT 3.9.2 0 11/15/2002
Title:
REFUELING C)PERATIONS REFUEL POSITION ONE-ROD-OUT INTERLOCK TEXT 3.9.3 0 11/15/2002
Title:
REFUELING C)PERATIONS CONTROL ROD POSITION TEXT 3.9.4 0 11/15/2002
Title:
REFUELING C)PERATIONS CONTROL ROD POSITION INDICATION TEXT 3.9.5 0 11/15/2002
Title:
REFUELING C)PERATIONS CONTROL ROD OPERABILITY - REFUELING.
TEXT 3.9.6
- 0 11/15/2002
Title:
REFUELING C)PERATIONS REACTOR PRESSURE VESSEL (RPV) WATER LEVEL Report Date: 09/29/06 Page Page77 of of 8 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 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 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 0 11/15/2002
Title:
SPECIAL OPERATIONS MULTIPLE CONTROL ROD WITHDRAWAL - REFUELING TEXT 3.10.7 1 04/18/2006
Title:
SPECIAL OPERATIONS CONTROL ROD TESTING - OPERATING TEXT 3.10.8 1 04/12/2006
Title:
SPECIAL OPERATIONS SHUTDOWN MARGIN (SDM) TEST - REFUELING Report Date: 09/29/06 Page 8 Page 8of 88 Report Date: 09/29/06
SUSQUEHANNA STEAM ELECTRIC STATION LIST OF EFFECTIVE SECTIONS (TECHNICAL SPECIFICATIONS BASES)
Section Title Revision TOC table of Contents 11 B 2.0 SAFETY LIMITS BASES
- Page B 2.0-1 0
Page TS / B 2.0-2 3 Page TS / B 2.0-3 4 Pages TS / B 2.0-4 and TS / B 2.0-5 3 Page TS / B 2.0-6 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
- 1 ' 0 Pages TS / B 3.0-5 through TS / B 3.0-7 Pages TS / B 3.0-8 through TS / B 3.0-9 LI 1 2
Pages TS / B 3.0-10 through TS / B 3.0-12' 1 1 II Pages TS/ B 3.0-13 through TS / B 3.0-15 2 Pages TS / B 3.0-16 and TS / B 3.0-17. 0 REACTIVITY CONTROL BASES B 3.1 Pages B 3.1-1 through B 3.1-4 0 Page TS / B 3.1-5 K.. II 1 Pages TS / B 3.1-6 and TS /,B 3.1-7 2 Pages B 3.1-8 through B 3.1L13= 0 Page TS / B 3.1-,4 - 1 1 Pages B 3.1-15,through B 3.1-21 0 Page TS / B 3.1.22 0 Ib Page TS hB3.1A23 I Page TSI/.B,3!.1-24 Page TS 1B 3.1 *25 0 Page TS / B 3.1'-26 Page'TS/B 3.1-27 0 PageTS/B3.1-28 2 Page TS/B3.1-29 Pages B 3.1730 through B 3.1-33' 0
';Pages TS / B 3.3-34 through TS IB 3ý3-36
- .Pages TS I B 3.1-37 and TS / B 3.1-38 2
- Pages B 3.1-39 through B 3.1-44 0 Page TSI B 3.1545 1
- Pages B 311-46 and B 3.1-47 0
,Pages TS i B 3.1-48 and TS I B 3.149 1
':Page B-3.1 -50 0 Page TS 6B3.1-51 1 SUSQUEHANNA - UNIT I TSIBLOES-1 TS / B LOES-1 Revision 78 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 /lB3.3-20 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 TSlBLOES-2 Revision 78 SUSQUEHANNA - UNIT SUSQUEHANNA -
UNIT II 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 / B3.3-52 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 / B3.3-68 4 Page TS / B3.3-69, 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 / B3.3-74.: 3 Page TS / B3.3-75:1 2 Page TS / B3.3-75a 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 / B3.3-104' 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 / B3.3-109 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 / B3.3-1 23 Iand TS I B 3.3-124 1 PageTS / B 3.3-124: 0 Page B3.3-125 1[ 1ý 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 I1 TSIBLOES-3 Revision 78 SUSQUEHANNA7'UNIT -
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 B3.4-55 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 Revision 78 SUSQUEHANNA - UNIT UNIT I1 TS / B LOES-4 TSIB LOES-4 Revision 78
SUSQUEHANNA STEAM ELECTRIC STATION LIST OF EFFECTIVE SECTIONS (TECHNICAL SPECIFICATIONS BASES)
Section Title Revision 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 Page TS / B 3.5-6 0 Pages B 3.5-7 through B 3.5-10 0 Page TS / B 3.5-11 0 Page TS / B 3.5-12 0 Page TS / B 3.5-13: 0 Pages TS / B 3.5-14 and TS I B 3.5-15 0 Pages TS / B 3.5-16 through TS / B 3.5-18 1 Pages B 3.5-19 through B 3.5-24 0 Page TS / B 3.5-25 1 Pages TS / B 3.5-26 and TS / B 3.5-27 1 Pages 1 j B 3.5-28,through B 3.5-31 0 Il ,
B 3.6 CONTAINMENT SYSTEMS BASES PageTS/B3.6-1 , 2 Page TS / B 3.6-1a 3 Pages TS / B 3.6-2 through TS I B 3.6-5 2 PageTS/B3.6-6 3 Pages TS / B 3.6-6a and TS , B 3.6-6b 2 Page TS / B 3.6-6c' 0 Pages B 3.6-7 through B 3.6-14 0 Page TS/B3.6-15 2 Pages TS / B 3.6-1 5a and TS B 3.6-15b .0 Pa3ge6B3.6-16 0 Page TS / B 3.6-17: i 1 PageTS/B3.6-17a 0 Pages TS / B 3.6-18 and TS / B 3.6-19 0 Page TS/B 1 Page TS / B 3.6-201 3.6121r ,:
2 PageTS/B3.61 22 0 Page TS / B 3.6-22a'! 0 Page TS / B 3.6-23', 1 Pages TS / B 3.6-24 through TS I B 3.6-2. 5 0 PageTS/B3.6-26!
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UNIT I1 TS / B LOES-5 Revision 78
SUSQUEHANNA STEAM ELECTRIC STATION LIST OFEFFECTIVE SECTIONS (TECHNICAL SPECIFICATIONS BASES)
Section Title Revision Page B 3.6-32 0 Page TS / B 3.6-33 1 Pages B 3.6-34 and B 3.6-35 0 Page TS / B 3.6-36 1 Page B 3.6-37 0 Page TS / B 3.6-38 1 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 1 Page TS / B 3.6-46 2 Pages TS / B 3.6-47 through TS / B 3.6-51 1 Page TS / B 3.6-52 2 Pages B 3.6-53 through B 3.6-63 0 Pages TS / B 3.6-64 and TS / B 3.6-65 1 Pages B 3.6-66 through B 3.6-69 0 Pages TS / B 3.6-70 through TS / B 3.6-72 1 Page TS / B 3.6-73 2 Pages TS / B 3.6-74 and TS / B 3.6-75 1 Pages B 3.6-76 and B 3.6-77 0 Page TS / B 3.6-78 1 Pages B 3.6-79 through B 3.3.6-83 0 Page TS / B 3.6-84 3 Page TS / B 3.6-85 2 Page TS / B 3.6-86 4 Page TS / B 3.6-87 through TS / 8 3.6-88a 2 Page TS / B 3.6-89 .3 Page TS / B 3.6-90 2 Page TS / B 3.6-91 3 Pages TS / B 3.6-92 through TS / B3.6-96 1 Page TS / B 3.6-97 2 Pages TS / 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 Page TS / B 3.6-106 2 Page TS / B3.6-107 3 B 3.7 PLANT SYSTEMS BASES Pages TS / B 3.7-1 through TS / B 3.7-6 2 Page TS / B3.7-6a 2 Pages TS / B 3 3.7-6b and TS / B 3.7-6c 0 Page TS / B 3.7-7 2
- Pages TS / B 3.7-8 through TS / B 3.7-13 1 Pages TS / B 3.7-14 through TS / B 3.7-18 2 UNIT I TS/BLOES-6 Revision 78 SUSQUEHANNA -UNIT1I SUSQUEHANNA - TS / B LOES-6 Revision 78
SUSQUEHANNA STEAM ELECTRIC STATION LIST OF EFFECTIVESECTIONS (TECHNICAL SPECIFICATIONS BASES)
Section Title Revision 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 Page TS / B 3.7-30 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 3.8-3 2 Page TS / B 3.8-4 3 Pages TS / B 3.8-4a and TS / B 3.8-4b 0 Page TS / B 3.8-5 4 Page TS I B 3.8-6 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 I B 3.8-37 2 Pages B 3.8-38 through B 3.8-53 0 Pages TS / B 3.8-54 through TS I B 3.8-61 1 Pages TS / B 3.8-62 and TS B I 3.8-63 3 Page TS / B 3.8-64 2 Page TS / B 3.8-65 *3 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 B 3.9 REFUELING OPERATIONS BASES Page's TS / B3.9-1 Iarid TSr/ B 3.9-1a 1 Page's TS / B3.9-2 ýthr6ugh TS / B 3.9-4 1 Pages B 3.9-5 through B 3,9-30 0 B 3.10 SPECIAL OPERATIONS BASES Page'TSI/B3.10-1I I r Pagesl B 3.10-2 throug B 3.10-31 0 Page'TS/B 3.10-32 2 Page' B3.10-33 0 Page'TS / B 3.10-34 I I Pages' B 3.10-35 arid 83.1036 0 Page'TS/B3.10-37 11 I
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1 "13.10-38 1!! , I 2 TSB1 text LOES 9/21/06 Revision 78 SUSQUEHANNA - UNIT SUSQUEHANNA - UNIT 1I TS /-B LOES-7
ý: TSIB 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 INSTRUMENTATION (continued)
B3.3.8.1 Loss of Power (LOP) Instrumentation ................. TS/B3.3-205 B3.3.8.2 Reactor Protection System (RPS) Electric Power Monitoring ................................... 3.3-213 B3.41 REACTOR COOLANT SYSTEM (RCS) ............................................... B3.4-1 B3.4.1 Recirculation Loops Operating ....................................................... B3.4-1 B3.4.2 Jet Pum ps ...................................................................................... B3.4-10 B3.4.3 Safety/Relief Valves (S/RVs) .................................................... TS/B3.4-15 B3.4.4 RCS Operational LEAKAGE ......................... 3.4-19 B3.4.5 RCS Pressure Isolation Valve (PIV) Leakage ................................. B3.4-24 B3.4.6 RCS Leakage Detection Instrumentation ................. 8 3.4-30 B3.4.7 RCS Specific Activity .............................. B3.4-35 B3.4.8 Residual Heat Removal (RHR) Shutdown Cooling System - Hot Shutdown ........................................................... B3.4-39 B3.4.9 Residual Heat Removal (RHR) Shutdown Cooling System - Cold Shutdown ......................... b3.4-44 B3.4.1 0 RCS Pressure and Temperature (P/T) Limits ......................... TS/B3.4-49 B3.4.11 Reactor Steam Dome Pressure ................................................ TS/B3.4-58 B3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) AND REACTOR CORE ISOLATION COOLING (RCIC) SYSTEM ............... B3.5-1 B3.5.1 ECCS - Operating ......................................................................... B3.5-1 B3.5.2 ECCS - Shutdown ......................................................................... B3.5-19 B3.5.3 RCIC System ........................................................................ "..TS/B3.5-25 B3.6 CONTAINMENT SYSTEMS ........................................................... TS/B3.6-1 B3.6.1 ..1 Primary Containment ........................................ TS/83.6-1 B3.6.1.2 Primary Containment Air Lock.......................... B3.6-7 B3.6.1.3 Primary Containment Isolation Valves (PCIVs) ......................... TS/B3.6-15 B3.6.1.4 Containment Pressure .................................................................... B3.6-41 B3.6.1.5 Drywell Air Temperature .......................................................... TS/B3.6-44 B3.6.1.6 Suppression Chamber-to-Drywell Vacuum Breakers ....... TS/B3.6-47 B3.6.2.1 Suppression Pool Average Temperature ..................... I....... . B3.6-53 B3.6.2.2 Suppression Pool Water Level ........................ B3.6-59 B3.6.2.3 Residual Heat Removal (RHR) Suppression Pool Cooling ....................... . .................................... * ...... ....... 83.6-62 B3.6.2.4 Residual Heat Removal (RHR) Suppression Pool Spray ..... B3.6-66 B3.6.3.1 Not Used .................. ....... ;.................................................... TS/B3.6-70 B3.6.3.2 Drywell Air Flow System ........................................ B3.6-76 B3.6.3.3 Primary Containment Oxygen Concentration................. B3.6-81 83.6.4.1 Secondary Containment.... ..... K..........................................
TS/B3.6-84 B3.6.4.2 Secondary Containment Isolation Valves (SC0Vs)......... TS/B3.6-91 B3.6.4.3 Standby Gas Treatment (SGT) System. ............... TS/B3.6-1o 1 (continued)
Revision 11 TS/BTOC-2 SUSQUEHANNA UNIT 1I SUSQUEHANNA-- UNIT TS/BTOC-2 Revision 11
TABLE OF CONTENTS (TECHNICAL SPECIFICATIONS BASES)
B3.7 PLANT SYSTEMS ......................................................................... TS/B3.7-1 B3.7.1 Residual Heat Removal Service Water (RHRSW) System and the Ultimate Heat Sink (UHS) ...................................... TS/B3.7-1 B3.7.2 Emergency Service Water (ESW) System ................................ TS/B3.7-7 B3.7.3 Control Room Emergency Outside Air Supply (CREOAS) System ............................................................. TSIB3.7-12 B3.7.4 Control Room Floor Cooling System ........................................ TS/B3.7-19 B3.7.5 Main Condenser Offgas ................................................................. B3.7-24 B3.7.6 Main Turbine Bypass System ................................................... TS/83.7-27 B3.7.7 Spent Fuel Storage Pool Water Level ................... B3.7-31 B3.8 ELECTRICAL POWER SYSTEM ................................................... TS/13.8-1 B3.8.1 !'AC Sources - Operating ......................... TSIB3.8-1 B3.8.2 ;AC Sources - Shutdown ................................................................ B3.8-38 B3.8.3 Diesel Fuel Oil, Lube Oil, and Starting Air ...................................... B3.8-45 B3.8.4 DC Sources - Operating .......................................................... TS/B3.8-54 B3.8.5 DC Sources -Shutdown ............................ B3.8-66 B3.8.6 Battery Cell Parameters ................................................................. B3.8-71 B3.8.7 Distribution Systems - Operating ................................................... B3.8-78 B3.8.8 Distribution !Systems -. Shutdown ................................................... B3.8-86 B3.9 REFUELING OPERATIONS .......................................................... TS/B3.9-1 B3.9.1 Refueling Equipment Interlocks ................................................ TS/B3.9-1 B3.9.2 Refuel Position One-Rod-Out Interlock .................................. B3.9-5 B3.9.3 Control Rod Position .............................. 3.9-9 B3.9.4 Control Rod Position Indication ...................................................... B3.9-12 B3.9.5 Control Rod OPERABILITY- Refueling ......................................... B3.9-16 B3.9.6" Reactor Pressure Vessel (RPV) Water Level ................................. B3.9-19 B3.9.7 'Residual Heat Removal (RHR) - High Water Level. ...................... B3.9-22 B3.9.8 IResidual Heat Removal (RHR) - Low Water Level ......................... B3.9-26 B3.10 SPECIAL OPERATIONS ................................. TS/B3.10-1 B3.10.1 Inservice Leak and Hydrostatic Testing Operation ................... TS/B3.10-1 B3.10.2 Reactor Mode'Switch Interlock Testing .......................................... B3.10-6 B3.10.3 Single Control Rod Withdirawal - Hot Shutdown ............................. B3.10-11 B3.10.4 Single Control Rod Withdrawal - Cold Shutdown ........................... B3.10-16 B3.10.5 Single Control Rod Drive (CRD) Removal - Refueling ................... B3.10-21 B3.10.6 Multiple Control Rod Withdrawal - Refueling .................................. B3.10-26 B3.10.7 Control Rod Testing "Operating ................................................... B3.10-29 B3.10.8 SHUTDOWN MARGIN (SDM) Test- Refueling ............................. B3.10-33 TSB1 Text TOC 9/20/2006 .
Revision 11 UNIT I1 TS/BTOC-3 SUSQUEHANNA - UNIT SUSQUEHANNA -
TS/BTOC-3 Revision 11
PPL Rev. 3 Control Rod Scram Times B 3.1.4 B3.1 REACTIVITY CONTROL SYSTEMS B 3.1.4 Control Rod Scram Times BASES 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: Ifthe 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 APPLICABLE SAFETY The analytical methods and assumptions used in evaluating the control SAFETY ANALYSES rod scram function are presented in References 2, 3, and 4. The Design ANALYSES 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 The scram function of the CRD System protects the MCPR Safety Limit SAFETY- (SL) (see Bases for SL 2.1.1, "Reactor Core SLs," and LCO 3.2.2, ANALYSES "MINIMUM CRITICAL POWER RATIO (MCPR)") and the 1% cladding (continued) 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 accomplished through measurement of the "dropout" times. To ensure (continued) 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 The four SRs of this LCO are modified by a Note stating that REQUIREMENTS 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 I rods are required to be tested before exceeding 40% RTP following I 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 I
associated core cell and by work on control rods or the CRD System.
(continued)
SUSQUEHANNA - UNIT 1 TS / B 3.1-25 Revision 1
PPL Rev. 3 Control Rod Scram Times B 3.1.4 BASES SURVEILLANCE SR 3.1.4.2 REQUIREMENTS (continued) 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)
SUSQUEHANNA - UNIT 1 TS / B 3.1-27 Revision 1
PPL Rev. 3 Control Rod Scram Times B 3.1.4 BASES REFERENCES 4. FSAR, Section 15.0.
(continued)
- 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.
SUSQUEHANNA - UNIT 1 TS / B 3.1-28 Revision 2