ML13361A087

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Susquehanna, Unit 1 - Revision 112 to Technical Specification Bases Manual
ML13361A087
Person / Time
Site: Susquehanna Talen Energy icon.png
Issue date: 12/11/2013
From:
Susquehanna
To: Gerlach R M
Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML13361A087 (29)
v • d • e


Text

Dec. 11, 2013Page1 of 2MANUAL HARD COPY DISTRIBUTION DOCUMENT TRANSMITTAL 2013-54823 USER INFORMATION:

GERLACH*ROSEY MEMPL#:028401 CA#: 0363Address:

NUCSA2Phone#: 254-3194TRANSMITTAL INFORMATION:

TO: GERLACH*ROSEY M 12/11/2013 LOCATION:

USNRCFROM: NUCLEAR RECORDS DOCUMENT CONTROL CENTER (NUCSA-2)

THE FOLLOWING CHANGES HAVE OCCURRED TO THE HARDCOPY OR ELECTRONIC MANUAL ASSIGNEDTO YOU. HARDCOPY USERS MUST ENSURE THE DOCUMENTS PROVIDED MATCH THE INFORMATION ONTHIS 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. TOOLSFROM THE HUMAN PERFORMANCE TOOL BAG SHOULD BE UTILIZED TO ELIMINATE THE CHANCE OFERRORS.ATTENTION:

"REPLACE" directions do not affect the Table of Contents, Therefore noTOC will be issued with the updated material.

TSBI -TECHNICAL SPECIFICATION BASES UNIT 1 MANUALREMOVE MANUAL TABLE OF CONTENTS DATE: 10/24/2013 ADD MANUAL TABLE OF CONTENTS DATE: 12/10/2013 CATEGORY:

DOCUMENTS TYPE: TSBI4ooIP PC4 Dec. 11, 2013Page 2 of 2ID: TEXT 3.6.4.1REMOVE: REV:8ADD: REV: 9CATEGORY:

DOCUMENTS TYPE: TSB1ID: TEXT LOESADD: REV: 112REMOVE: REV:111ANY DISCREPANCIES WITH THE MATERIAL

PROVIDED, CONTACT DCS @ X3107 OR X3136 FORASSISTANCE.

UPDATES FOR HARDCOPY MANUALS WILL BE DISTRIBUTED WITHIN 3 DAYS INACCORDANCE WITH DEPARTMENT PROCEDURES.

PLEASE MAKE ALL CHANGES AND ACKNOWLEDGE COMPLETE IN YOUR NIMS INBOX UPON COMPLETION OF UPDATES.

FOR ELECTRONIC MANUALUSERS, ELECTRONICALLY REVIEW THE APPROPRIATE DOCUMENTS AND ACKNOWLEDGE COMPLETE INYOUR NIMS INBOX.

SSES MANUJTALManual Name: TSBIManual Title: TECHNICAL SPECIFICATION

'BASES UNIT I MANUALTable Of ContentsIssue Date: 12/10/2013 Procedure Name RevTEXT LOES 112Title: LIST OF EFFECTIVE SECTIONSCN It^L [DIssue Date12/10/2013 Change ID Change NumberTEXT TOCTitle: TABLE OF CONTENTS22 03/28/2013 TEXT 2.1.1 5Title: SAFETY LIMITS (SLS) REACTORTEXT 2.1.2 1Title: SAFETY LIMITS (SLS) REACTOR05/06/2009 CORE SLS10/04/2007 COOLANT SYSTEM(RCS) PRESSURE STEXT 3.0Title: LIMITING CONDITION 3 08/20/2009 FOR OPERATION (LCO) APPLICABILITY TEXT 3.1.1Title: REACTIVITY TEXT 3.1.2Title: REACTIVITY TEXT 3.1.3Title: REACTIVITY TEXT 3.1.4Title: REACTIVITY TEXT 3.1.5Title: REACTIVITY TEXT 3.1.61CONTROL SYSTEMS0CONTROL SYSTEMS04/18/2006 SHUTDOWN MARGIN (SDM)11/15/2002 REACTIVITY ANOMALIES 2 01/19/2009 CONTROL SYSTEMS CONTROL ROD OPERABILITY 4 01/30/2009 CONTROL SYSTEMS CONTROL ROD SCRAM TIMES1 07/06/2005 CONTROL SYSTEMS CONTROL ROD SCRAM ACCUMULATORS 2 04/18/2006 Title: REACTIVITY CONTROL SYSTEMS ROD PATTERN CONTROLPage 1 of 8 Report Date: 12/10/13Page 1of 8Report Date: 12/10/13 SSES MANUALManual Name: TSB1Manual Title: TECHNICAL SPECIFICATION BASES UNIT 1 MANUALTEXT 3.1.7 3 04/23/2008 Title: REACTIVITY CONTROL SYSTEMS STANDBY LIQUID CONTROL (SLC) SYSTEMTEXT 3.1.8 3 05/06/2009 Title: REACTIVITY CONTROL SYSTEMS SCRAM DISCHARGE VOLUME (SDV) VENT AND DRAIN VALVESTEXT 3.2.1 2 04/23/2008 Title: POWER DISTRIBUTION LIMITS AVERAGE PLANAR LINEAR HEAT GENERATION RATE (APLHGR)TEXT 3.2.2 3 05/06/2009 Title: POWER DISTRIBUTION LIMITS MINIMUM CRITICAL POWER RATIO (MCPR)TEXT 3.2.3 2 04/23/2008 Title: POWER DISTRIBUTION LIMITS LINEAR HEAT GENERATION RATE (LHGR)TEXT 3.3.1.1 5 07/23/2013 Title: INSTRUMENTATION REACTOR PROTECTION SYSTEM (RPS) INSTRUMENTATION TEXT 3.3.1.2 2 01/19/2009 Title: INSTRUMENTATION SOURCE RANGE MONITOR (SRM) INSTRUMENTATION TEXT 3.3.2.1 3 04/23/2008 Title: INSTRUMENTATION CONTROL ROD BLOCK INSTRUMENTATION TEXT 3.3.2.2 2 04/05/2010 Title: INSTRUMENTATION FEEDWATER MAIN TURBINE HIGH WATER LEVEL TRIP INSTRUMENTATION TEXT 3.3.3.1 9 02/28/2013 Title: INSTRUMENTATION POST ACCIDENT MONITORING (PAM) INSTRUMENTATION TEXT 3.3.3.2 1 04/18/2005 Title: INSTRUMENTATION REMOTE SHUTDOWN SYSTEMTEXT 3.3.4.1 1 04/23/2008 Title: INSTRUMENTATION END OF CYCLE RECIRCULATION PUMP TRIP (EOC-RPT)

INSTRUMENTATIOW Page 2 of .8Report Date: 12/10/13 SSES MANUALManual Name: TSBlManual Title: TECHNICAL SPECIFICATION BASES UNIT 1 MANUALTEXT 3.3.4.2 0 11/15/2002 Title: INSTRUMENTATION ANTICIPATED TRANSIENT WITHOUT SCRAM RECIRCULATION PUMP TRIP(ATWS-RPT)

INSTRUMENTATION TEXT 3.3.5.1Title: INSTRUMENTATION TEXT 3.3.5.2Title: INSTRUMENTATION 3 08/20/2009 EMERGENCY CORE COOLING SYSTEM (ECCS) INSTRUMENTATION 0 11/15/2002 REACTOR CORE ISOLATION COOLING (RCIC) SYSTEM INSTRUMENTATION TEXT 3.3.6.1 5 07/23/2013 Title: INSTRUMENTATION PRIMARY CONTAINMENT ISOLATION INSTRUMENTATION TEXT 3.3.6.2Title: INSTRUMENTATION TEXT 3.3.7.1Title: INSTRUMENTATION INSTRUMENTATION 4 09/01/2010 SECONDARY CONTAINMENT ISOLATION INSTRUMENTATION 2 10/27/2008 CONTROL ROOM EMERGENCY OUTSIDE AIR SUPPLY (CREOAS)

SYSTEMTEXT 3.3.8.1 2 12/17/2007 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 3.4.1Title:. REACTOR COOLANT4 04/27/2010 SYSTEM (RCS) RECIRCULATION LOOPS OPERATING TEXT 3.4.2 3 10/23/2013 Title: REACTOR COOLANT SYSTEM (RCS) JET PUMPSTEXT 3.4.3 3 01/13/2012 Title: REACTOR COOLANT SYSTEM RCS SAFETY RELIEF VALVES S/RVSTEXT 3.4.4Title: REACTOR COOLANT0 11/15/2002 SYSTEM (RCS) RCS OPERATIONAL LEAKAGEPage~ of 8 Report Date: 12/10/13Page 3 of 8Report Date: 12/10/13 SSES MANUTALManual Name: TSBIManual Title: TECHNICAL SPECIFICATION BASES UNIT 1 MANUALTEXT 3.4.5Title: REACTOR COOLANTTEXT 3.4.6Title: REACTOR COOLANTTEXT 3.4.7Title: REACTOR COOLANTTEXT 3.4.8Title: REACTOR COOLANT-HOT SHUTDOWNTEXT 3.4.9Title: REACTOR COOLANT-COLD SHUTDOWNTEXT 3.4.10Title: REACTOR COOLANTTEXT 3.4.11Title: REACTOR COOLANTTEXT 3.5.11 01/16/2006 SYSTEM (RCS) RCS PRESSURE ISOLATION VALVE (PIV) LEAKAGE3 01/25/2011 SYSTEM (RCS) RCS LEAKAGE DETECTION INSTRUMENTATION 2 10/04/2007 SYSTEM (RCS) RCS SPECIFIC ACTIVITY2 03/28/2013 SYSTEM (RCS) RESIDUAL HEAT REMOVAL (RHR) SHUTDOWN COOLING SYSTEM1 03/28/2013 SYSTEM (RCS) RESIDUAL HEAT REMOVAL (RHR) SHUTDOWN COOLING3 04/23/2008 SYSTEM (RCS) RCS PRESSURE AND TEMPERATURE (P/T) LIMITS0 11/15/2002 SYSTEM (RCS) REACTOR STEAM DOME PRESSURE2 01/16/2006 SYSTEM0Title: EMERGENCY CORE COOLING SYSTEMS (ECCS) AND REACTORSYSTEM ECCS -OPERATING TEXT 3.5.2 0 11/15/2002 Title: EMERGENCY CORE COOLING SYSTEMS (ECCS) AND REACTORSYSTEM ECCS -SHUTDOWNTEXT 3.5.3 2 07/09/2010 Title: EMERGENCY CORE COOLING SYSTEMS (ECCS) AND REACTORSYSTEM RCIC SYSTEMCORE ISOLATION COOLING (RCIC)CORE ISOLATION COOLING (RCIC)CORE ISOLATION COOLING (RCIC)TEXT 3.6.1.1Title: PRIMARY CONTAINMENT 4 11/09/2011 TEXT 3.6.1.2 1 04/23/2008 Title: CONTAINMENT SYSTEMS PRIMARY CONTAINMENT AIR LOCKPage4 of 8 Report Date: 12/10/13Page 4 of 8Report Date: 12/10/13 SSES MANUALManual Name: TSBIManual Title: TECHNICAL SPECIFICATION BASES UNIT 1 MANUALTEXT 3.6.1.3Title: CONTAINMENT TEXT 3.6.1.4Title: CONTAINMENT TEXT 3.6.1.5Title: CONTAINMENT TEXT 3.6.1.6Title: CONTAINMENT TEXT 3.6.2.1Title: CONTAINMENT TEXT 3.6.2.2Title: CONTAINMENT TEXT 3.6.2.3Title: CONTAINMENT TEXT 3.6.2.4Title: CONTAINMENT TEXT 3.6.3.1Title: CONTAINMENT TEXT 3.6.3.2Title: CONTAINMENT TEXT 3.6.3.3Title: CONTAINMENT TEXT 3.6.4.1Title: CONTAINMENT 10 05/23/2012 SYSTEMS PRIMARY CONTAINMENT ISOLATION VALVES (PCIVS)1 04/23/2008 SYSTEMS CONTAINMENT PRESSURE1 10/05/2005 SYSTEMS DRYWELL AIR TEMPERATURE 0 11/15/2002 SYSTEMS SUPPRESSION CHAMBER-TO-DRYWELL VACUUM BREAKERS2 04/23/2008 SYSTEMS SUPPRESSION POOL AVERAGE TEMPERATURE 0 11/15/2002 SYSTEMS SUPPRESSION POOL WATER LEVEL1 01/16/2006 SYSTEMS RESIDUAL HEAT REMOVAL (RHR) SUPPRESSION POOL COOLING0 11/15/2002 SYSTEMS RESIDUAL HEAT REMOVAL (RHR) SUPPRESSION POOL SPRAY2 06/13/2006 SYSTEMS PRIMARY CONTAINMENT HYDROGEN RECOMBINERS 1 04/18/2005 SYSTEMS DRYWELL AIR FLOW SYSTEM1 02/28/2013 SYSTEMS PRIMARY CONTAINMENT OXYGEN CONCENTRATION 9 12/10/2013 SYSTEMS SECONDARY CONTAINMENT Pages of 8 Report Date: 12/10/13Page 5 of 8Report Date: 12/10/13 SSES MANUALManual Name: TSB1Manual Title: TECHNICAL SPECIFICATION BASES UNIT 1 MANUALTEXT 3.6.4.2 8 03/28/2013 Title: CONTAINMENT SYSTEMS SECONDARY CONTAINMENT ISOLATION VALVES (SCIVS)TEXT 3.6.4.3 4 09/21/2006 Title: CONTAINMENT SYSTEMS STANDBY GAS TREATMENT (SGT) SYSTEMTEXT 3.7.1Title: PLANT SYSTEMSULTIMATE HEATTEXT 3.7.2Title: PLANT SYSTEMSTEXT 3.7.3Title: PLANT SYSTEMSTEXT 3.7.4Title: PLANT SYSTEMSTEXT 3.7.5Title: PLANT SYSTEMSTEXT 3.7.6Title: PLANT SYSTEMSTEXT 3.7.7Title: PLANT SYSTEMSTEXT 3.7.8Title: PLANT SYSTEMSTEXT 3.8.14 04/05/2010 RESIDUAL HEAT REMOVAL SERVICE WATER (RHRSW) SYSTEM AND THESINK (UHS)2 02/11/2009 EMERGENCY SERVICE WATER (ESW) SYSTEM1 01/08/2010 CONTROL ROOM EMERGENCY OUTSIDE AIR SUPPLY (CREOAS)

SYSTEM0 11/15/2002 CONTROL ROOM FLOOR COOLING SYSTEM1 10/04/2007 MAIN CONDENSER OFFGAS2 04/23/2008 MAIN TURBINE BYPASS SYSTEM1 10/04/2007 SPENT FUEL STORAGE POOL WATER LEVEL0 04/23/2008 6 05/06/2009 0Title: ELECTRICAL POWER SYSTEMS AC SOURCES -OPERATING TEXT 3.8.2 0 11/15/2002 Title: ELECTRICAL POWER SYSTEMS AC SOURCES -SHUTDOWNsPage~ of 8 Report Date: 12/10/13Page 6 of .8Report Date: 12/10/13 SSES M.ANTAILManual Name: TSBIManual Title: TECHNICAL SPECIFICATION BASES UNIT 1 MANUALTEXT 3.8.3Title: ELECTRICAL TEXT 3.8.4Title: ELECTRICAL TEXT 3.8.5Title: ELECTRICAL TEXT 3.8.6Title: ELECTRICAL 4POWER SYSTEMS3POWER SYSTEMS1POWER SYSTEMS10/23/2013 DIESEL FUEL OIL, LUBE OIL, AND STARTING AIR01/19/2009 DC SOURCES -OPERATING 12/14/2006 DC SOURCES -SHUTDOWN1 12/14/2006 POWER SYSTEMS BATTERY CELL PARAMETERS TEXT 3.8.7Title: ELECTRICAl TEXT 3.8.8Title: ELECTRICAl TEXT 3.9.1Title: REFUELING TEXT 3.9.2Title: REFUELING TEXT 3.9.3Title: REFUELING TEXT 3.9.4Title: REFUELING TEXT 3.9.5Title: REFUELING TEXT 3.9.6Title: REFUELING 1 10/05/2005 POWER SYSTEMS DISTRIBUTION SYSTEMS -OPERATING 0 11/15/2002 POWER SYSTEMS DISTRIBUTION SYSTEMS -SHUTDOWN0 11/15/2002 OPERATIONS REFUELING EQUIPMENT INTERLOCKS 1 09/01/2010 OPERATIONS REFUEL POSITION ONE-ROD-OUT INTERLOCK 0 11/15/2002 OPERATIONS CONTROL ROD POSITION0 11/15/2002 OPERATIONS CONTROL ROD POSITION INDICATION 0 11/15/2002 OPERATIONS CONTROL ROD OPERABILITY

-REFUELING 1 10/04/2007 OPERATIONS REACTOR PRESSURE VESSEL (RPV) WATER LEVELPage2 of 8 Report Date: 12/10/13Page 7 of 8Report Date: 12/10/13 SSES MANUJALManual Name: TSBIManual Title: TECHNICAL SPECIFICATION BASES UNIT 1 MANUALTEXT 3.9.7 0 11/15/2002 Title: REFUELING OPERATIONS RESIDUAL HEAT REMOVAL (RHR) -HIGH WATER LEVELTEXT 3.9.8 0 11/15/2002 Title: REFUELING OPERATIONS RESIDUAL HEAT REMOVAL (RHR) -LOW WATER LEVELTEXT 3.10.1Title: SPECIALTEXT 3.10.2Title: SPECIALTEXT 3.10.3Title: SPECIALTEXT 3.10.4Title: SPECIALTEXT 3.10.5Title: SPECIALTEXT 3.10.6Title: SPECIALTEXT 3.10.7Title: SPECIALTEXT 3.10.8Title: SPECIALOPERATIONS OPERATIONS OPERATIONS OPERATIONS OPERATIONS OPERATIONS OPERATIONS OPERATIONS 1 01/23/2008 INSERVICE LEAK AND HYDROSTATIC TESTING OPERATION 0 11/15/2002 REACTOR MODE SWITCH INTERLOCK TESTING0 11/15/2002 SINGLE CONTROL ROD WITHDRAWAL

-HOT SHUTDOWN0 11/15/2002 SINGLE CONTROL ROD WITHDRAWAL

-COLD SHUTDOWN0 11/15/2002 SINGLE CONTROL ROD DRIVE (CRD) REMOVAL -REFUELING 0 11/15/2002 MULTIPLE CONTROL ROD WITHDRAWAL

-REFUELING 1 04/18/2006 CONTROL ROD TESTING -OPERATING 1 04/12/2006 SHUTDOWN MARGIN (SDM) TEST -REFUELING Page~ of 8 Report Date: 12/10/13Page 8 of .8Report Date: 12/10/13 SUSQUEHANNA STEAM ELECTRIC STATIONLIST OF EFFECTIVE SECTIONS (TECHNICAL SPECIFICATIONS BASES)Section Title RevisionTOC Table of Contents 22B 2.0 SAFETY LIMITS BASESPage B 2.0-1 0Page TS / B 2.0-2 3Page TS / B 2.0-3 5Page TS / B 2.0-4 3Page TS / B 2.0-5 5Page TS / B 2.0-6 1Pages TS / B 2.0-7 through TS / B 2.0-9 1B 3.0 LCO AND SR APPLICABILITY BASESPage TS / B 3.0-1 1Pages TS / B 3.0-2 through TS / B 3.0-4 0Pages TS / B 3.0-5 through TS / B 3.0-7 1Page TS / B 3.0-8 3Pages TS / B 3.0-9 through TS / B 3.0-11 2Page TS / B 3.0-11 a 0Page TS / B 3.0-12 1Pages TS / B 3.0-13 through TS / B 3.0-15 2Pages TS / B 3.0-16 and TS / B 3.0-17 0B 3.1 REACTIVITY CONTROL BASESPages B 3.1-1 through B 3.1-4 0Page TS / B 3.1-5 1Pages TS / B 3.1-6 and TS / B 3.1-7 2Pages B 3.1-8 through B 3.1-13 0Page TS / B 3.1-14 1Page B 3.1-15 0Page TS / B 3.1-16 1Pages B 3.1-17 through B 3.1-19 0Pages TS / B 3.1-20 and TS / B 3.1-21 1Page TS / B 3.1-22 0Page TS / B 3.1-23 1Page TS / B 3.1-24 0Pages TS / B 3.1-25 through TS / B 3.1-27 1Page TS / B 3.1-28 2Page TS / B 3.1-29 1Pages B 3.1-30 through B 3.1-33 0Pages TS / B 3.3-34 through TS / B 3.3-36 1Pages TS / B 3.1-37 and TS / B 3.1-38 2Pages TS / B 3.1-39 and TS / B 3.1-40 2Page TS / B 3.1-40a 0Pages TS / B 3.1-41 and TS / B 3.1-42 2SUSQUEHANNA

-UNIT 1 TS I B LOES-1 Revision 112SUSQUEHANNA

-UNIT 1TS / B LOES-1Revision 112 SUSQUEHANNA STEAM ELECTRIC STATIONLIST OF EFFECTIVE SECTIONS (TECHNICAL SPECIFICATIONS BASES)Section Title RevisionPage TS / B 3.1.43 1Page TS / B 3.1-44 0Page TS / B 3.1-45 3Pages TS / B 3.1-46 through TS / B 3.1-49 1Page TS / B 3.1-50 0Page TS / B 3.1-51 3B 3.2 POWER DISTRIBUTION LIMITS BASESPage TS / B 3.2-1 2Pages TS / B 3.2-2 and TS / B 3.2-3 3Pages TS / B 3.2-4 and TS / B 3.2-5 2Page TS / B 3.2-6 3Page B 3.2-7 1Pages TS / B 3.2-8 and TS / B 3.2-9 3Page TS / B 3.2.10 2Page TS / 8 3.2-11 3Page TS / 8 3.2-12 1Page TS / B 3.2-13 28 3.3 INSTRUMENTATION Pages TS / B 3.3-1 through TS / B 3.3-4 1Page TS / 8 3.3-5 2Page TS / 8 3.3-6 1Page TS / 8 3.3-7 3Page TS / B 3.3-7a 1Page TS / 8 3.3-8 5Pages TS / B 3.3-9 through TS / 8 3.3-12 3Pages TS / B 3.3-12a IPages TS / B 3.3-12b and TS / B 3.3-12c 0Page TS / B 3.3-13 1Page TS / 8 3.3-14 3Pages TS / B 3.3-15 and TS / 8 3.3-16 1Pages TS / B 3.3-17 and TS / B 3.3-18 4Page TS / B 3.3-19 1Pages TS / B 3.3-20 through TS / B 3.3-22 2Page TS / B 3.3-22a 0Pages TS / B 3.3-23 and TS / B 3.3-24 2Pages TS / B 3.3-24a and TS / B 3.3-24b 0Page TS / 8 3.3-25 3Page TS / B 3.3-26 2Page TS / 8 3.3-27 1Pages TS / B 3.3-28 through TS / B 3.3-30 3Page TS / B 3.3-30a 0SUSQUEHANNA-UNITi TS I B LOES-2 Revision 112SUSQUEHANNA

-UNIT 1TS / B LOES-2Revision 112 SUSQUEHANNA STEAM ELECTRIC STATIONLIST OF EFFECTIVE SECTIONS (TECHNICAL SPECIFICATIONS BASES)Section Title RevisionPage TS / B 3.3-31 4Page TS / B 3.3-32 5Pages TS / B 3.3-32a 0Page TS / B 3.3-32b 1Page TS / B 3.3-33 5Page TS / B 3.3-33a 0Page TS / B 3.3-34 1Pages TS / B 3.3-35 and TS / B 3.3-36 2Pages TS / B 3.3-37 and TS / B 3.3-38 1Page TS / B 3.3-39 2Pages TS / B 3.3-40 through TS / B 3.3-43 1Page TS / B 3.3-44 4Pages TS / B 3.3-44a and TS / B 3.3-44b 0Page TS / B 3.3-45 3Pages TS / B 3.3-45a and TS / B 3.3-45b 0Page TS / B 3.3-46 3Pages TS / B 3.3-47 2Pages TS / B 3.3-48 through TS / B 3.3-51 3Pages TS / B 3.3-52 and TS / B 3.3-53 2Page TS / B 3-3-53a 0Page TS / B 3.3-54 4Page TS / B 3.3-55 2Pages TS / B 3.3-56 and TS / B 3.3-57 1Page TS / B 3.3-58 0Page TS / B 3.3-59 1Page TS / B 3.3-60 0Page TS / B 3.3-61 1Pages TS / B 3.3-62 and TS / B 3.3-63 0Pages TS / B 3.3-64 and TS / B 3.3-65 2Page TS / B 3.3-66 4Page TS / B 3.3-67 3Page TS / B 3.3-68 4Page TS / B 3.3-69 5Pages TS / B 3.3-70 4Page TS / B 3.3-71 3Pages TS / B 3.3-72 and TS / B 3.3-73 2Page TS / B 3.3-74 3Page TS / B 3.3-75 2Page TS / B 3.3-75a 6Page TS / B 3.3-75b 7Page TS / B 3.3-75c 6SUSQUEHANNA

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-UNIT 1TS / B LOES-3Revision 112 SUSQUEHANNA STEAM ELECTRIC STATIONLIST OF EFFECTIVE SECTIONS (TECHNICAL SPECIFICATIONS BASES)Section Title RevisionPages B 3.3-76 through 3.3-77 0Page TS / B 3.3-78 1Pages B 3.3-79 through B 3.3-81 0Page B 3.3-82 1Page B 3.3-83 0Pages B 3.3-84 and B 3.3-85 1Page B 3.3-86 0Page B 3.3-87 1Page B 3.3-88 0Page B 3.3-89 1Page TS / B 3.3-90 1Page B 3.3-91 0Pages TS / B 3.3-92 through TS / B 3.3-100 1Pages TS / B 3.3-101 through TS / B 3.3-103 0Page TS / B 3.3-104 2Pages TS / B 3.3-105 and TS / B3.3-106 0Page TS / B 3.3-107 1Page TS / B 3.3-108 0Page TS / B 3.3-109 1Pages TS / B 3.3-110 and TS / B 3.3-111 0Pages TS / B 3.3-112 and TS / B 3.3-112a 1Pages TS / B 3.3-113 through TS / B 3.3-115 1Page TS / B 3.3-116 3Page TS / B 3.3-117 1Pages TS / B 3.3-118 through TS / B 3.3-122 0Pages TS / B 3.3-123 and TS / B 3.3-124 1Page TS / B 3.3-124a 0Page TS / B 3.3-125 0Pages TS / B 3.3-126 and TS / B 3.3-127 1Pages TS / B 3.3-128 through TS/ B 3.3-130 0Page TS / B 3.3-131 1Pages TS / B 3.3-132 through TS / B 3.3-134 0Pages B 3.3-135 through B 3.3-137 0Page TS / B 3.3-138 1Pages B 3.3-139 through B 3.3-149 0Pages TS / B 3.3-150 and TS / B 3.3-151 1Pages TS / B 3.3-152 through TS / B 3.3-154 2Page TS / B 3.3-155 1Pages TS / B 3.3-156 through TS / B 3.3-158 2Pages TS / B 3.3-159 through TS / B 3.3-162 1Page TS / B 3.3-163 2Page TS / B 3.3-164 1Pages TS / B 3.3-165 through TS / B 3.3-167 2SUSQUEHANNA

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-UNIT 1TS / B LOES-4Revision 112 SUSQUEHANNA STEAM ELECTRIC STATIONLIST OF EFFECTIVE SECTIONS (TECHNICAL SPECIF-ICATIONS BASES)Section Title RevisionPages TS / B 3.3-168 and TS / B 3.3-169 1Page TS / B 3.3-170 2Pages TS / B 3.3-171 through TS / B 3.3-177 1Pages TS / B 3.3-178 through TS / B 3.3-179a 2Pages TS / B 3.3-179b and TS / B 3.3-179c 0Page TS / B 3.3-180 1Page TS / B 3.3-181 3Page TS / B 3.3-182 1Page TS / B 3.3-183 2Page TS / B 3.3-184 1Page TS / B 3.3-185 4Page TS / B 3.3-186 1Pages TS / B 3.3-187 and TS / B 3.3-188 2Pages TS / B 3.3-189 through TS / B 3.3-191 1Page TS / B 3.3-192 0Page TS / B 3.3-193 1Pages TS / B 3.3-194 and TS I B 3.3-195 0Page TS / B 3.3-196 2Pages TS / B 3.3-197 through TS / B 3.3-204 0Page TS / B 3.3-205 1Pages B 3.3-206 through B 3.3-209 0Page TS / B 3.3-210 1Pages 8 3.3-211 through B 3.3-219 0B 3.4 REACTOR COOLANT SYSTEM BASESPages B 3.4-1 and B 3.4-2 0Pages TS / B 3.4-3 and Page TS / B 3.4-4 4Page TS / B 3.4-5 3Pages TS / B 3.4-6 through TS / B 3.4-9 2Page TS / B 3.4-10 1Pages TS / 3.4-11 and TS / B 3.4-12 0Page TS / B 3.4-13 2Page TS / B 3.4-14 1Page TS / B 3.4-15 2Pages TS / B 3.4-16 and TS / B 3.4-17 4Page TS / B 3.4-18 2Pages B 3.4-19 through B 3.4-27 0Pages TS / B 3.4-28 through TS / B 3.4-30 1Page TS / B 3.4-31 0Pages TS / B 3.4-32 and TS / B 3.4-33 1Page TS / B 3.4-34 0Pages TS / B 3.4-35 and TS / B 3.4-36 1Page TS / B 3.4-37 2Page TS / B 3.4-38 1SUSQUEHANNA

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-UNIT 1TS / B LOES-5Revision 112 SUSQUEHANNA STEAM ELECTRIC STATIONLIST OF EFFECTIVE SECTIONS (TECHNICAL SPECIFICATIONS BASES)Section Title RevisionPages B 3.4-39 and B 3.4-40 0Page TS / B 3.4-41 2Pages TS / B 3.4-42 through TS / B 3.4-45 0Page TS / B 3.4-46 1Pages TS B 3.4-47 and TS / B 3.4-48 0Page TS / B 3.4-49 3Page TS / B 3.4-50 1Page TS / B 3.4-51 3Page TS / B 3.4-52 2Page TS / B 3.4-53 1Pages TS / B 3.4-54 through TS / B 3.4-56 2Page TS / B 3.4-57 3Pages TS / B 3.4-58 through TS / B 3.4-60 1B 3.5 ECCS AND RCIC BASESPages B 3.5-1 and B 3.5-2 0Page TS / B 3.5-3 2Page TS / B 3.5-4 1Page TS / B 3.5-5 2Page TS / B 3.5-6 1Pages B 3.5-7 through B 3.5-10 0Page TS / B 3.5-11 1Page TS / B 3.5-12 0Page TS / B 3.5-13 1Pages TS / B 3.5-14 and TS / B 3.5-15 0Pages TS / 8 3.5-16 through TS / B 3.5-18 1Pages B 3.5-19 through B 3.5-24 0Page TS / B 3.5-25 through TS / B 3.5-27 1Page TS / B 3.5-28 0Page TS / B 3.5-29 1Pages TS / B 3.5-30 and TS / B 3.5-31 0B 3.6 CONTAINMENT SYSTEMS BASESPage TS / B 3.6-1 2Page TS / 8 3.6-1a 3Page TS / B 3.6-2 4Page TS / 8 3.6-3 3Page TS / B 3.6-4 4Pages TS / B 3.6-5 and TS / B 3.6-6 3Page TS / B 3.6-6a 2Page TS / B 3.6-6b 3Page TS / B 3.6-6c 0Page 8 3.6-7 0SUSQUEHANNA

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-UNIT 1TS / B LOES-7Revision 112 SUSQUEHANNA STEAM ELECTRIC STATIONLIST OF EFFECTIVE SECTIONS (TECHNICAL SPECIF'ICATIONS BASES)Section Title RevisionPage TS / B 3.6-78 1Pages B 3.6-79 and B 3.3.6-80 0Page TS / B 3.6-81 1Pages TS / B 3.6-82 and TS / B 3.6-83 0Page TS / B 3.6-84 4Page TS / B 3.6-85 2Page TS / B 3.6-86 4Pages TS / B 3.6-87 through TS / B 3.6-88a 2Page TS / B 3.6-89 5Page TS / B 3.6-90 3Page TS / B 3.6-90a 0Pages TS / B 3.6-91 and TS / B 3.6-92 3Page TS / B 3.6-93 2Pages TS / B 3.6-94 through TS / B 3.6-96 1Page TS / B 3.6-97 2Page TS / B 3.6-98 1Page TS / B 3.6-99 2Pages TS I B 3.6-100 and TS / B 3.6-100a 5Page TS / B 3.6-100b 3Pages TS / B 3.6-101 and TS / B 3.6-102 1Pages TS / B 3.6-103 and TS / B 3.6-104 2Page TS / B 3.6-105 3Page TS / B 3.6-106 2Page TS / B 3.6-107 3B 3.7 PLANT SYSTEMS BASESPages TS / B 3.7-1 3Page TS / B 3.7-2 4Pages TS / B 3.7-3 through TS / B 3.7-5 3Page TS / B 3.7-5a 1Page TS / B 3.7-6 3Page TS / B 3.7-6a 2Page TS / B 3.7-6b 1Page TS / B 3.7-6c 2Page TS / B 3.7-7 3Page TS / B 3.7-8 2Pages TS / B 3.7-9 through TS / B 3.7-11 1Pages TS / B 3.7-12 and TS / B 3.7-13 2Pages TS / B 3.7-14 through TS / B 3.7-18 3Page TS / B 3.7-18a 1Pages TS / B 3.7-18b through TS / B 3.7-18e 0Pages TS / B 3.7-19 through TS / B 3.7-23 1Page TS / B 3.7-24 1SUSQUEHANNA

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-ISUSQUEHANNA STEAM ELECTRIC STATIONLIST OF EFFECTIVE SECTIONS (TECHNICAL SPECIFICATIONS BASES)Section Title RevisionPages TS / B 3.7-25 and TS / B 3.7-26 0Pages TS / B 3.7-27 through TS / B 3.7-29 5Page TS / B 3.7-30 2Page TS / B 3.7-31 1Page TS / B 3.7-32 0Page TS / B 3.7-33 1Pages TS / B 3.7-34 through TS I B 3.7-37 0B 3.8 ELECTRICAL POWER SYSTEMS BASESPage TS / B 3.8-1 3Pages TS / B 3.8-2 and TS / B 3.8-3 2Page TS / B 3.8-4 3Pages, TS / B 3.8-4a and TS / B 3.8-4b 0Page TS / B 3.8-5 5Page TS / B 3.8-6 3Pages TS / B 3.8-7 through TS/B 3.8-8 2Page TS / B 3.8-9 4Page TS / B 3.8-10 3Pages TS / B 3.8-11 and TS / B 3.8-17 2Page TS / B 3.8-18 3Pages TS / B 3.8-19 through TS / B 3.8-21 2Pages TS / B 3.8-22 and TS / B 3.8-23 3Pages TS / B 3.8-24 through TS / B 3.8-37 2Pages B 3.8-38 through B 3.8-44 0Page TS / B 3.8-45 3Pages TS / B 3.8-46 through TS / B 3.8-48 0Pages TS / B 3.8-49 and TS / B 3.8-50 3Page TS / B 3.8-51 1Page TS / B 3.8-52 0Page TS / B 3.8-53 1Pages TS / B 3.8-54 through TS / B 3.8-57 2Pages TS / B 3.8-58 through TS / B 3.8-61 3Pages TS / B 3.8-62 and TS / B 3.8-63 5Page TS / B 3.8-64 4Page TS / B 3.8-65 5Pages TS / B 3.8-66 through TS / B 3.8-77 1Pages TS / B 3.8-77A through TS / B 3.8-77C 0Pages B 3.8-78 through B 3.8-80 0* Page TS / B 3.8-81 1Pages B 3.8-82 through B 3.8-90 0SUSQUEHANNA-UNIT 1TS / B LOES-9Revision 112 SUSQUEHANNA STEAM ELECTRIC STATIONLIST OF EFFECTIVE SECTIONS (TECHNICAL SPECIFICATIONS BASES)Section Title RevisionB 3.9 REFUELING OPERATIONS BASESPages TS / B 3.9-1 and TS / B 3.9-1a 1Pages TS / B 3.9-2 through TS / B 3.9-5 1Pages TS / B 3.9-6 through TS / B 3.9-8 0Pages B 3.9-9 through B 3.9-18 0Pages TS / B 3.9-19 through TS / B 3.9-21 1Pages B 3.9-22 through B 3.9-30 0B 3.10 SPECIAL OPERATIONS BASESPage TS / B 3.10-1 2Pages TS / B 3.10-2 through TS / B 3.10-5 1Pages B 3.10-6 through B 3.10-31 0Page TS / B 3.10-32 2Page B 3.10-33 0Page TS / B 3.10-34 1Pages B 3.10-35 and B 3.10-36 0Page TS / B 3.10-37 1Page TS / B 3.10-38 2TSB1 Text LOES.doc11/2212013 SUSQUEHANNA

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-UNIT 1TS / B LOES-10Revision 112 PPL Rev. 9Secondary Containment B 3.6.4.1B 3.6 CONTAINMENT SYSTEMSB 3.6.4.1 Secondary Containment BASESBACKGROUND The secondary containment structure completely encloses the primarycontainment structure such that a dual-containment design is utilized tolimit the spread of radioactivity to the environment to within limits. Thefunction of the secondary containment is to contain, dilute, and hold upfission products that may leak from primary containment into secondary containment following a Design Basis Accident (DBA). In conjunction withoperation of the Standby Gas Treatment (SGT) System and closure ofcertain valves whose lines penetrate the secondary containment, thesecondary containment is designed to reduce the activity level of thefission products prior to release to the environment and to isolate andcontain fission products that are released during certain operations thattake place inside primary containment, when primary containment is notrequired to be OPERABLE, or that take place outside primary containment (Ref. 1).The secondary containment is a stnjcture that completely encloses theprimary containment and reactor coolant pressure boundary components.

This structure forms a control volume that serves to hold up and dilute thefission products.

It is possible for the pressure in the control volume torise relative to the environmental pressure (e.g., due to pump and motorheat load additions).

The secondary containment boundary consists of the reactor buildingstructure and associated removable walls and panels, hatches, doors,dampers, sealed penetrations and valves. Certain plant piping systems(e.g., Service Water, RHR Service Water, Emergency Service Water,Feedwater, etc.) penetrate the secondary containment boundary.

Theintact piping within secondary containment provides a passive barrierwhich maintains secondary containment requirements.

Breaches of thesepiping systems within secondary containment will be controlled to maintainsecondary containment requirements.

The secondary containment isdivided into Zone I, Zone II and Zone Ill, each of which must beOPERABLE depending on plant status and the alignment of thesecondary containment boundary.

Specifically, the Unit 1 secondary containment boundary can be modified to exclude Zone II. Similarly, theUnit 2 secondary containment boundary can be modified to excludeZone I. Secondary containment may consist of only Zone III when inMODE 4 or 5 during CORE ALTERATIONS, or during handling ofirradiated fuel within the Zone III secondary containment boundary.

(continued)

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PPL Rev. 9Secondary Containment B 3.6.4.1BASESBACKGROUND (continued)

To prevent ground level exfiltration

-while allowing the secondary containment to be designed as a conventional structure, the secondary containment requires support systems to maintain the control volumepressure at less than the external pressure.

Requirements for the safetyrelated systems are specified separately in LCO 3.6.4.2, "Secondary Containment Isolation Valves (SCIVs),"

and LCO 3.6.4.3, "Standby GasTreatment (SGT) System."

When one or more zones are excluded fromsecondary containment, the specific requirements for support systems willalso change (e.g., required secondary containment isolation valves).APPLICABLE SAFETYANALYSESThere are two principal accidents for which credit is taken for secondary containment OPERABILITY.

These are a loss of coolant accident (LOCA)(Ref. 2) and a fuel handling accident inside secondary containment (Ref. 3). The secondary containment performs no active function inresponse to either of these limiting events; however, its leak tightness isrequired to ensure that the release of radioactive materials from theprimary containment is restricted to thpse leakage paths and associated leakage rates assumed in the accident analysis and that fission productsentrapped within the secondary containment structure will be treated bythe SGT System prior to discharge to the environment.

Secondary containment satisfies Criterion 3 of the NRC Policy Statement (Ref. 4).LCOAn OPERABLE secondary containment provides a control volume intowhich fission products that bypass or leak from primary containment, orare released from the reactor coolant pressure boundary components located in secondary containment, can be diluted and processed prior torelease to the environment.

For the. secondary containment to beconsidered

OPERABLE, it must have adequate leak tightness to ensurethat the required vacuum can be established and maintained.

The leaktightness of secondary containment must also ensure that the release ofradioactive materials to the environment is restricted to those leakagepaths and associated leakage rates assumed in the accident analysis.

Forexample, secondary containment bypass leakage must be restricted to theleakage rate required by LCO 3.6.1.3.

The secondary containment boundary required to be OPERABLE is dependent on the operating statusof both units, as well as the configuration of walls, doors, hatches, SCIVs,and available flow paths to the SGT System.(continued)

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PPL Rev. 9Secondary Containment B 3.6.4.1BASES (continued)

APPLICABILITY In MODES 1, 2, and 3, a LOCA could lead to a fission product release toprimary containment that leaks to secondary containment.

Therefore, secondary containment OPERABILITY is required during the sameoperating conditions that require primary containment OPERABILITY.

In MODES 4 and 5, the probability and consequences of the LOCA arereduced due to the pressure and temperature limitations in these MODES.Therefore, maintaining secondary containment OPERABLE is notrequired in MODE 4 or 5 to ensure a control volume, except for othersituations for which significant releases of radioactive material can bepostulated, such as during operations with a potential for draining thereactor vessel (OPDRVs),

during CORE ALTERATIONS, or duringmovement of irradiated fuel assemblies in the secondary containment.

ACTIONS A. 1If secondary containment is inoperable, it must be restored to OPERABLEstatus 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 oftime to correct the problem that is commensurate with the importance ofmaintaining secondary containment during MODES 1, 2, and 3. This timeperiod also ensures that the probability of an accident (requiring secondary containment OPERABILITY) occurring during periods wheresecondary 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.

TheTemporary 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 ofthe Reactor Building Recirculating Fan Damper Motors. The Temporary Completion 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 onDecember 31, 2005.B.1 and B.2If secondary containment cannot be restored to OPERABLE status withinthe required Completion Time, the plant must be brought to a MODE inwhich the LCO does not apply. To achieve this status, the plant must bebrought 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 within36 hours. The allowed Completion Times are reasonable, based onoperating experience, to reach the required plant conditions from fullpower conditions in an orderly manner and without challenging plantsystems.(continued)

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PPL Rev. 9Secondary Containment B 3.6.4.1BASESACTIONS C.1, C.2, and C.3(continued)

Movement of irradiated fuel assemblies in the secondary containment, CORE ALTERATIONS, and OPDRVs can be postulated to cause fissionproduct release to the secondary containment.

In such cases, thesecondary containment is the only barrier to release of fission products tothe environment.

CORE ALTERATIONS and movement of irradiated fuelassemblies must be immediately suspended if the secondary containment is inoperable.

Suspension of these activities shall not preclude completing an action thatinvolves moving a component to a safe position.

Also, action must beimmediately initiated to suspend OPDRVs to minimize the probability of avessel 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 isnot applicable.

If moving irradiated fuel assemblies while in MODE 4 or 5,LCO 3.0.3 would not specify any action. If moving irradiated fuelassemblies while in MODE 1, 2, or 3, the fuel movement is independent ofreactor operations.

Therefore, in either case, inability to suspendmovement of irradiated fuel assemblies would not be a sufficient reason torequire a reactor shutdown.

SURVEILLANCE SR 3.6.4.1.1 REQUIREMENTS This SR ensures that the secondary containment boundary issufficiently leak tight to preclude exfiltration under expected windconditions.

Expected wind conditions are defined as sustained windspeeds of less than or equal to 16 mph at the 60m meteorological tower or less than or equal to 11 mph at the 1 Om meteorological towerif the 60m tower wind speed is not available.

Changes in indicated reactor building differential pressure observed during periods of short-term wind speed gusts above these sustained speeds do not bythemselves impact secondary containment integrity.

However, ifsecondary containment integrity is known to be compromised, the LCOmust be entered regardless of wind speed.(continued)

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PPL Rev. 9Secondary Containment B 3.6.4.1BASESSURVEILLANCE SR 3.6:4.1.1 (continued)

REQUIREMENTS The 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> Frequency of this SR was developed based on operating experience related to secondary containment vacuum variations during theapplicable MODES and the low probability of a DBA occurring betweensurveillances.

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 view ofother indications available in' the control room, including alarms, to alertthe 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 wallsand one access door in each access opening required to be closed areclosed ensures that the infiltration of outside air of such a magnitude as toprevent maintaining the desired negative pressure does not occur.Verifying that all such openings are closed also provides adequateassurance 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 onedoor in each access opening to secondary containment zones is closed.In some cases (e.g., railroad bay), secondary containment accessopenings are shared such that a secondary containment barrier may havemultiple inner or multiple outer doors. The intent is to maintain thesecondary containment barrier intact, which is achieved by maintaining the inner or outer portion of the barrier closed at all times. However, allsecondary containment access doors are normally kept closed, exceptwhen the access opening is being used for entry and exit or whenmaintenance is being performed on an access opening.When the railroad bay door (No. 101) is closed; all Zone I and III hatches,removable walls, dampers, and one door in each access openingconnected to the railroad access bay are closed; or, only Zone Iremovable walls and/or doors are open to the railroad access shaft; or,only Zone III hatches and/or dampers are open to the railroad accessshaft. When the railroad bay door (No. 101) is open; all Zone I and IIIhatches, removable walls, dampers, and one door in each access openingconnected to the railroad access bay are closed. The truck bay hatch isclosed and the truck bay door (No. 102) is closed unless Zone II is isolatedfrom Zones I and Il1..,, (continued)

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PPL Rev. 9Secondary Containment B 3.6.4.1BASESSURVEILLANCE REQUIREMENTS SR 3.6.4.1.2 and SR 3.6.4.1.3 (continued)

When an access opening between required secondary containment zonesis being used for exit and entry, then at least one door (where two doorsare provided) must remain closed. 'The access openings betweensecondary containment zones which are not provided with two doors areadministratively controlled to maintain secondary containment integrity during exit and entry. This Surveillance is modified by a Note that allowsaccess 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 door forentry 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 azone required for secondary containment OPERABILITY, the Noteallowance 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 theother indications of door and hatch status that are available to theoperator.

(continued)

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PPL Rev. 9Secondary Containment B 3.6.4.1BAS ESSURVEILLANCE REQUIREMENTS (continued)

SR 3.6.4.1.4 and SR 3.6.4.1.5 The SGT System exhausts the secondary containment atmosphere to theenvironment through appropriate treatment equipment.

To ensure that allfission products are treated, SR 3.6.4.1.4 verifies that the SGT System willrapidly 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 down the secondary containment to > 0.25 inches of vacuumwater gauge in less than or equal to the maximum time allowed.

Thiscannot be accomplished if the secondary containment boundary is notintact. 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 orequal to the maximum flow rate penrnitted 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.

Asnoted, both SR 3.6.4.1.4 and SR 3.6.4.1.5 acceptance limits aredependent upon the secondary containment configuration when testing isbeing performed.

The acceptance criteria for the SRs based onsecondary containment configuration is defined as follows:SECONDARY MAXIMUM DRAWDOWN TIME(SEC)

MAXIMUM FLOW RATE (CFM)CONTAINMENT (SR 3.6.4.1.4 (SR 3.6.4.1.5 TEST CONFIGURATION ACCEPTANCE CRITERIA)

ACCEPTANCE CRITERIA)

Group 1Zones 1, 11 and III (Unit 1 < 300 Seconds _4000 CFMRailroad Bay aligned to (Zones 1, 11, and Ill) (From Zones I, II, and Ill)Secondary Containment).

Zones I and III (Unit 1 < 300 Seconds < 2885 CFMRailroad Bay aligned to (Zones I and Il) (From Zones I and Ill)Secondary Containment).

Group 2Zones I, II and III (Unit 1 300 Seconds 3910 CFMRailroad Bay not aligned (Zones 1, 11, and Ill) (From Zones I, I1, and Ill)to Secondary Containment).

Zones I and III (Unit 1 < 300 Seconds < 2800 CFMRailroad Bay not aligned (Zones I and III) (From Zones I and Ill)to Secondary Containment).

Only one of the above listed configurations needs to be tested to confirm secondary containment OPERABILITY.

(continued)

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PPL Rev. 9Secondary Containment B 3.6.4.1BASESSURVEILLANCE SR 3.6.4.1.4 and SR 3.6.4.1.5 (continued)

REQUIREMENTS A Note also modifies the Frequency for each SR. This Note identifies thateach configuration is to be tested every 60 months. Testing eachconfiguration 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 usuallypass the Surveillance and all active components are tested morefrequently.

Therefore, these tests are used to ensure secondary containment boundary integrity.

The Unit 1 Railroad Bay can be aligned as a No Zone (isolated fromsecondary containment) or as part of secondary containment (Zone I orIll). Drawdown testing of the secondary containment shall be performed with the Unit 1 Railroad Bay aligned in the most limiting configuration.

More specifically, secondary containment drawdown testing will beperformed with the Unit I Railroad Bay aligned as a No Zone with theRailroad Bay door open or as part of secondary containment.,

The specificalignment will be selected based on the alignment that provides the leastamount of inleakage and drawdown time margin (on a percentage basis)to the acceptance criteria.

This could result in one alignment (e.g., NoZone with the Railroad Bay door open) being limiting for one criterion (e.g.,drawdown time) and the other alignment (e.g., Railroad Bay aligned tosecondary containment) being limiting for the other criterion (e.g.,inleakage).

It also could result in one alignment being limiting for bothcriteria.

Noteethat aligning the Railroad Bay to either Zone I or III is acceptable since either zone is part of secondary containment.

It is preferred to alignthe Railroad Bay to Zone III for testing since Zone III is included in allpossible secondary containment isolation alignments.

The most limitingUnit 1 Railroad Bay alignment shall be established each Surveillance period(60 month). Subsequent drawdown testing during the same Surveillance period only requires testing of the Unit 1 Railroad Bay in the most limitingconfiguration.

For example, Zone 1, 11, and III Surveillance testing isperformed with the Unit 1 Railroad, Bay aligned both as a No Zone with theRailroad Bay door open and as Zone Ill. If the Surveillance testingdetermined the most limiting configuration occurs with the Unit 1 RailroadBay aligned as Zone III, then subsequent Zone I and III drawdown testingduring the same Surveillance period only needs to be performed with theUnit I Railroad Bay aligned as Zone Il1.(continued)

SUSQUEHANNA

-UNIT 1TS / B 3.6-90Revision 3

PPL Rev. 9Secondary Containment B 3.6.4.1BASESSURVEILLANCE REQUIREMENTS SR 3.6.4.1.4 and SR 3.6.4.1.5 (continued)

Since these SRs are secondary containment tests, they need not beperformed with each SGT subsystem.

The SGT subsystems are tested ona STAGGERED TEST BASIS, however, to ensure that in addition to therequirements of LCO 3.6.4.3, either SGT subsystem will performSR 3.6.4.1.4 and SR 3.6.4.1.5.

Operating experience has shown thesecomponents usually pass the Surveillance when performed at the24 month. Frequency.

Therefore, the Frequency was concluded to beacceptable 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 Improvements, July 22, 1993 (58 FR 39132).SUSQUEHANNA

-UNIT 1TS / B 3.6-90aRevision 0

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