ML14205A013

Susquehanna, Unit 1, Technical Specification Bases, Manual, Revisions

ML14205A013
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Site:	Susquehanna
Issue date:	07/17/2014
From:	Susquehanna
To:	Document Control Desk, Office of Nuclear Reactor Regulation
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Jul. 17, 2014Page1 of 2MANUAL HARD COPY DISTRIBUTION DOCUMENT TRANSMITTAL 2014-35377 USER INFORMATION:

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SSES MANUALManual Name: TSBIManual Title: TECHNICAL SPECIFICATION BASES UNIT 1 MANUALCON"TROLLED Table Of ContentsIssue Date: 07/16/2014 Procedure Name RevTEXT LOES 118Title: LIST OF EFFECTIVE SECTIONSIssue Date07/16/2014 Change ID Change NumberTEXT TOCTitle: TABLE OF CONTENTS23 07/02/2014 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 3.0 3 08/20/2009 Title: LIMITING CONDITION 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 1CONTROL SYSTEMS0CONTROL SYSTEMS2CONTROL SYSTEMS4CONTROL SYSTEMS1CONTROL SYSTEMS04/18/2006 SHUTDOWN MARGIN (SDM)11/15/2002 REACTIVITY ANOMALIES 01/19/2009 CONTROL ROD OPERABILITY 01/30/2009 CONTROL ROD SCRAM TIMES07/06/2005 CONTROL ROD SCRAM ACCUMULATORS TEXT 3.1.63 02/24/2014 Title: REACTIVITY CONTROL SYSTEMS ROD PATTERN CONTROLPagel of 8 Report Date: 07/17/14Page I of .8Report Date: 07/17/14 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 6 02/24/2014 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 4 02/24/2014 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 3.3.3.1Title: INSTRUMENTATION 9 02/28/2013 POST ACCIDENT MONITORING (PAM) INSTRUMENTATION TEXT 3.3.3.2 1 04/18/2005 Title: INSTRUMENTATION REMOTE SHUTDOWN SYSTEMTEXT 3.3.4.1 2 02/24/2014 Title: INSTRUMENTATION END OF CYCLE RECIRCULATION PUMP TRIP (EOC-RPT)

INSTRUMENTATIO WPage 2 of 8Report Date: 07/17/14 SSES MANUALManual Name: TSBIManual 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 3.3.5.1 3 08/20/2009 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 7 03/31/2014 Title: INSTRUMENTATION PRIMARY CONTAINMENT ISOLATION INSTRUMENTATION TEXT 3.3.6.2 4 09/01/2010 Title: INSTRUMENTATION SECONDARY CONTAINMENT ISOLATION INSTRUMENTATION TEXT 3.3.7.1Title: INSTRUMENTATION 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 3.3.8.2Title: INSTRUMENTATION 0 11/15/2002 REACTOR PROTECTION SYSTEM (RPS) ELECTRIC POWER MONITORING TEXT 3.4.1 4 04/27/2010 Title: REACTOR COOLANT 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 LEAKAGEPage3 of 8 Report Date: 07/17/14Page 3 of .8Report Date: 07/17/14 SSES MANUALManual Name: TSB1Manual Title: TECHNICAL SPECIFICATION BASES UNIT 1 MANUALTEXT 3.4.5 1 01/16/2006 Title: REACTOR COOLANT SYSTEM (RCS) RCS PRESSURE ISOLATION VALVE (PIV) LEAKAGETEXT 3.4.6 4 02/19/2014 Title: REACTOR COOLANT SYSTEM (RCS) RCS LEAKAGE DETECTION INSTRUMENTATION TEXT 3.4.7 2 10/04/2007 Title: REACTOR COOLANT SYSTEM (RCS) RCS SPECIFIC ACTIVITYTEXT 3.4. 8Title: REACTOR COOLANT-HOT SHUTDOWNTEXT 3.4.9Title: REACTOR COOLANT-COLD SHUTDOWN2SYSTEM (RCS)1SYSTEM (RCS)03/28/2013 RESIDUAL HEAT REMOVAL (RHR) SHUTDOWN COOLING SYSTEM03/28/2013 RESIDUAL HEAT REMOVAL (RHR) SHUTDOWN COOLINGSYSTEM0TEXT 3.4.10 3 04/23/2008 Title: REACTOR COOLANT SYSTEM (RCS) RCS PRESSURE AND TEMPERATURE (P/T) LIMITSTEXT 3.4. 11Title: REACTOR COOLANTTEXT 3.5.10 11/15/2002 SYSTEM (RCS) REACTOR STEAM DOME PRESSURE4 07/16/2014 Title: 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 3 02/24/2014 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 5 02/24/2014 TEXT 3.6.1.2 1 04/23/2008 Title: CONTAINMENT SYSTEMS PRIMARY CONTAINMENT AIR LOCKPage4 of 8 Report Date: 07/17/14Page 4 of 3Report Date: 07/17/14 SSES MANUALManual Name: TSB1Manual 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 11 07/02/2014 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 10 04/25/2014 SYSTEMS SECONDARY CONTAINMENT Page5 of 8 Report Date: 07/17/14Page 5 of .8Report Date: 07/17/14 SSES MANUALManual Name: TSBlManual Title: TECHNICAL SPECIFICATION BASES UNIT I MANUALTEXT 3.6.4.2 9 04/25/2014 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 HEAT4 04/05/2010 RESIDUAL HEAT REMOVAL SERVICE WATER (RHRSW) SYSTEM AND THESINK (UHS)TEXT 3.7.2Title: PLANTTEXT 3.7.3Title: PLANTTEXT 3.7.4Title: PLANT2 02/11/2009 SYSTEMS EMERGENCY SERVICE WATER (ESW) SYSTEM1 01/08/2010 SYSTEMS CONTROL ROOM EMERGENCY OUTSIDE AIR SUPPLY (CREOAS)

SYSTEM0 11/15/2002 SYSTEMS CONTROL ROOM FLOOR COOLING SYSTEMTEXT 3.7.5Title: PLANT SYSTEMS1 10/04/2007 MAIN CONDENSER OFFGASTEXT 3.7.6Title: PLANTTEXT 3.7.7Title: PLANT2 04/23/2008 SYSTEMS MAIN TURBINE BYPASS SYSTEM1 10/04/2007 SYSTEMS SPENT FUEL STORAGE POOL WATER LEVELTEXT 3.7.8Title: PLANT SYSTEMS0 04/23/2008 TEXT 3.8.17 02/24/2014 Title: ELECTRICAL POWER SYSTEMS AC SOURCES -OPERATING TEXT 3.8.2 0 11/15/2002 Title: ELECTRICAL POWER SYSTEMS AC SOURCES -SHUTDOWNPages of 8 Report Date: 07/17/14Page 6 of aReport Date: 07/17/14 SSES MANUALManual Name: TSB1Manual 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 TEXT 3.8.7Title: ELECTRICAL TEXT 3.8.8Title: ELECTRICAL TEXT 3.9.1Title: REFUELING CTEXT 3.9.2Title: REFUELING TEXT 3.9.3Title: REFUELING TEXT 3.9.4Title: REFUELING CTEXT 3.9.5Title: REFUELING TEXT 3.9.6Title: REFUELING (POWER SYSTPOWER SYSTPOWER SYSTPOWER SYSTPOWER.SYST POWER SYSTDPERATIONS

)PERATIONS

)PERATIONS OPERATIONS

)PERATIONS

)PERATIONS 4 10/23/2013

'EMS DIESEL FUEL OIL, LUBE OIL, AND STARTING AIR3 01/19/2009

'EMS DC SOURCES -OPERATING 1 12/14/2006

'EMS DC SOURCES -SHUTDOWN1 12/14/2006

'EMS BATTERY CELL PARAMETERS 1 10/05/2005

'EMS DISTRIBUTION SYSTEMS -OPERATING 0 11/15/2002

'EMS DISTRIBUTION SYSTEMS -SHUTDOWN0 11/15/2002 REFUELING EQUIPMENT INTERLOCKS 1 09/01/2010 REFUEL POSITION ONE-ROD-OUT INTERLOCK 0 11/15/2002 CONTROL ROD POSITION0 11/15/2002 CONTROL ROD POSITION INDICATION 0 11/15/2002 CONTROL ROD OPERABILITY

-REFUELING 1 10/04/2007 REACTOR PRESSURE VESSEL (RPV) WATER LEVELPage7 of ~ Report Date: 07/17/14Page 7 of -8Report Date: 07/17/14 SSES MANUIALManual 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 Pages of 8 Report Date: 07/17/14Page 8 of -8Report Date: 07/17/14 SUSQUEHANNA STEAM ELECTRIC STATIONLIST OF EFFECTIVE SECTIONS (TECHNICAL SPECIFICATIONS BASES)Section Title RevisionTOC Table of Contents 23B 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 3.0-11a 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 1Page TS / B 3.1-37 2Page TS / B 3.1-38 3Pages 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/BLOES-1 Revision 118SUSQUEHANNA

-UNIT 1TS / B LOES-1Revision 118 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 / B 3.2-11 3Page TS / B 3.2-12 1Page TS / B 3.2-13 2B 3.3 INSTRUMENTATION Pages TS / B 3.3-1 through TS / B 3.3-4 1Page TS / B 3.3-5 2Page TS / B 3.3-6 1Page TS / B 3.3-7 3Page TS / B 3.3-7a 1Page TS / B 3.3-8 5Pages TS / B 3.3-9 through TS / B 3.3-12 3Pages TS / B 3.3-12a 1Pages TS / B 3.3-12b and TS / B 3.3-12c 0Page TS / B 3.3-13 1Page TS / B 3.3-14 3Pages TS / B 3.3-15 and TS / B 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 / B 3.3-25 3Page TS / B 3.3-26 2Page TS / B 3.3-27 1Page TS / B 3.3-28 3Page TS / B 3.3-29 4Page TS / B 3.3-30 3Page TS / B 3.3-30a 0SUSQUEHANNA

-UNIT 1SUSQUEHANNA-UNIT 1 TS / B LOES-2 Revision 118TS / B LOES-2Revision 118 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 5Page 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 I 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 6Pages B 3.3-76 through B 3.3-77 0Page TS / B 3.3-78 1SUSQUEHANNA-UNITi TS / B LOES-3 Revision 118SUSQUEHANNA

-UNIT 1TS / B LOES-3Revision 118 SUSQUEHANNA STEAM ELECTRIC STATIONLIST OF EFFECTIVE SECTIONS (TECHNICAL SPECIFICATIONS BASES)Section Title RevisionPages B 3.3-79 through B 3.3-81 0Page TS / B 3.3-82 2Page 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 / B 3.3-106 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 I 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 8 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 3.3-159and TS / B 3.3-160 1Page TS / B 3.3-161 2Page 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

-UNIT 1 TS I B LOES-4 Revision 118SUSQUEHANNA

-UNIT 1TS / B LOES-4Revision 118 SUSQUEHANNA STEAM ELECTRIC STATIONLIST OF EFFECTIVE SECTIONS (TECHNICAL SPECIFICATIONS BASES)Section Title RevisionPages TS / B 3.3-168 and TS / B 3.3-169 1Page TS / B 3.3-170 3Page TS / B 3.3-171 2Pages TS / B 3.3-172 through TS / B 3.3-177 1Pages TS / B 3.3-178 and TS / B 3.3-179 2Page 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 / 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 B 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 and TS / B 3.4-29 1Page TS / B 3.4-30 2Page TS / B 3.4-31 1Pages TS / B 3.4-32 and TS / B 3.4-33 2Page TS / B 3.4-34 1Page TS I B 3.4-34a 0SUSQUEHANNA

-UNIT I TSIBLOES-5 Revision 118SUSQUEHANNA

-UNIT 1TS / B LOES-5Revision 118 SUSQUEHANNA STEAM ELECTRIC STATIONLIST OF EFFECTIVE SECTIONS (TECHNICAL SPECIFICATIONS BASES)Section Title RevisionPages TS / B 3.4-35 and TS / B 3.4-36 g1Page TS / B 3.4-37 2Page TS / B 3.4-38 1Pages 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 3Page TS / B 3.5-4 1Page TS / B 3.5-5 2Page TS / B 3.5-6 1Pages TS / B 3.5-7 through TS / B 3.5-10 0Page TS / B 3.5-11 1Page TS / B 3.5-12 0Page TS / B 3.5-13 2Pages TS / B 3.5-14 and TS / B 3.5-15 0Pages TS / B 3.5-16 and TS / B 3.5-17 3Page TS / B 3.5-18 1Pages B 3.5-19 through B 3.5-24 0Page TS / B 3.5-25 1Page TS/B 3.5-26 and TS / B 3.5-27 2Page 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 / B 3.6-1a 3Page TS / B 3.6-2 4Page TS / B 3.6-3 3Page TS /B 3.6-4 4Pages TS / B 3.6-5 and TS / B 3.6-6 3SUSQUEHANNA

-UNIT 1 TS/B LOES-6 Revision 118SUSQUEHANNA

-UNIT 1TS / B LOES-6Revision 118 SUSQUEHANNA STEAM ELECTRIC STATIONLIST OF EFFECTIVE SECTIONS (TECHNICAL SPECIFICATIONS BASES)Section Title RevisionPage TS I B 3.6-6a 2Page TS / B 3.6-6b 4Page TS / B 3.6-6c 0Page B 3.6-7 0Page B 3.6-8 1Pages B 3.6-9 through B 3.6-14 0Page TS / B 3.6-15 3Page TS / B 3.6-15a 0Page TS / B 3.6-15b 2Pages TS / B 3.6-16 and TS / B 3.6-17 2Page TS / B 3.6-17a 1Pages TS / B 3.6-18 and TS / B 3.6-19 0Page TS / B 3.6-20 1Page TS / B 3.6-21 2Page TS / B 3.6-22 1Page TS / B 3.6-22a 0Page TS / B 3.6-23 1Pages TS / B 3.6-24 and TS / B 3.6-25 0Pages TS / B 3.6-26 and TS / B 3.6-27 2Page TS J B 3.6-28 7Page TS / B 3.6-29 2Page TS / B 3.6-30 1Page TS / B 3.6-31 3Pages TS / B 3.6-32 and TS / B 3.6-33 1Pages TS / B 3.6-34 and TS / B 3.6-35 0Page TS / B 3.6-36 1Page TS / B 3.6-37 0Page TS / B 3.6-38 3Page TS / B 3.6-39 2Page TS / B 3.6-40 6Page TS / B 3.6-40a 1Page B 3.6-41 1Pages B 3.6-42 and B 3.6-43 0Pages TS / B 3.6-44 and TS / B 3.6-45 1Page TS / B 3.6-46 2Pages TS / B 3.6-47 through TS / B 3.6-51 1Page TS / B 3.6-52 2Pages TS / B 3.6-53 through TS / B 3.6-56 0Page TS / B 3.6-57 1.Page TS / 3.6-58 2Pages B 3.6-59 through B 3.6-63 0Pages TS / B 3.6-64 and TS / B 3.6-65 1Pages B 3.6-66 through B 3.6-69 0SUSQUEHANNA

-UNIT I TSIBLOES-7 Revision 118SUSQUEHANNA

-UNIT 1TS / B LOES-7Revision 118 SUSQUEHANNA STEAM ELECTRIC STATIONLIST OF EFFECTIVE SECTIONS (TECHNICAL SPECIFICATIONS BASES)Section Title RevisionPages TS / B 3.6-70 through TS / B 3.6-75 1Pages B 3.6-76 and B 3.6-77 0Page 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 I B 3.6-88a 2Page TS / B 3.6-89 6Page 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 / B 3.6-100 and TS / B 3.6-100a 6Page TS / B 3.6-100b 4Page TS / B 3.6-100c 0Pages 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 1 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 0SUSQUEHANNA

-UNIT I TS/BLOES-8 Revision 118SUSQUEHANNA

-UNIT 1TS / B LOES-8Revision 118 SUSQUEHANNA STEAM ELECTRIC STATIONLIST OF EFFECTIVE SECTIONS (TECHNICAL SPECIFICATIONS BASES)Section Title RevisionPages TS / B 3.7-19 through TS / B 3.7-23 1Page TS / B 3.7-24 1Pages 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 / B 3.7-37 0B 3.8 ELECTRICAL POWER SYSTEMS BASESPage TS / B 3.8-1 3Pages TS I 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 3.8-30 2Pages TS / B 3.8-31 and TS / B 3.8-32 3Pages TS / B 3.8-33 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 0Page TS / B 3.8-81 1Pages B 3.8-82 through B 3.8-90 0SUSQUEHANNA

-UNIT 1TS / B LOES-9Revision 118 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 2SUSQUEHANNA

-UNIT 1 TS I B LOES-1 0 Revision 118SUSQUEHANNA

-UNIT 1TS / B LOES-1 0Revision 118 PPL Rev. 4ECCS-Operating B 3.5.1B 3.5B 3.5.1EMERGENCY CORE COOLING SYSTEMS (ECCS) ANDREACTOR CORE ISOLATION COOLING (RCIC) SYSTEMECCS-Operating BASESBACKGROUND The ECCS is designed, in conjunction with the primary and secondary containment, to limit the release of radioactive materials to theenvironment following a loss of coolant accident (LOCA). The ECCS usestwo independent methods (flooding and spraying) to cool the core duringa LOCA. The ECCS network consists of the High Pressure CoolantInjection (HPCI) System, the Core Spray (CS) System, the low pressurecoolant injection (LPCI) mode of the Residual Heat Removal (RHR)System, and the Automatic Depressurization System (ADS). Thesuppression pool provides the required source of water for the ECCS.Although no credit is taken in the safety analyses for the condensate storage tank (CST), it is capable of providing a source of water for theHPCI and CS systems.On receipt of an initiation signal, ECCS pumps automatically start;simultaneously, the system aligns and the pumps inject water, taken eitherfrom the CST or suppression pool, into the Reactor Coolant System (RCS)as RCS pressure is overcome by the discharge pressure of the ECCSpumps. Although the system is initiated, ADS action is delayed, allowingthe operator to interrupt the timed sequence if the system is not needed.The HPCI pump discharge pressure quickly exceeds that of the RCS, andthe pump injects coolant into the vessel to cool the core. If the break issmall, the HPCI System will maintain coolant inventory as well as vessellevel while the RCS is still pressurized.

If HPCI fails, it is backed up byADS in combination with LPCI and CS. In this event absent operatoraction, the ADS timed sequence would time out and open the selectedsafety/relief valves (S/RVs) depressurizing the RCS, thus allowing theLPCI and CS to overcome RCS pressure and inject coolant into thevessel. If the break is large, RCS pressure initially drops rapidly and theLPCI and CS cool the core.Water from the break returns to the suppression pool where it is usedagain and again. Water in the suppression pool is circulated through aheat exchanger cooled by the RHR Service Water System. Depending onthe location and size of(continued)

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PPL Rev. 4ECCS-Operating B 3.5.1BASESBACKGROUND the break, portions of the ECCS may be ineffective; however the overall(continued) design is effective in cooling the core regardless of the size or location ofthe piping break. Although no credit is taken in the safety analysis for theRCIC System, it performs a similar function as HPCI, but has reducedmakeup capability.

Nevertheless, it will maintain inventory and cool thecore while the RCS is still pressurized following a reactor pressure vessel(RPV) isolation.

All ECCS subsystems are designed to ensure that no single activecomponent failure will prevent automatic initiation and successful operation of the minimum required ECCS equipment.

The CS System (Ref. 1) is composed of two independent subsystems.

Each subsystem consists of two motor driven pumps, a spray spargerabove the core, and piping and valves to transfer water from thesuppression pool to the sparger.

The CS System is designed to providecooling to the reactor core when reactor pressure is low. Upon receipt ofan initiation signal, the CS pumps in both subsystems are automatically started when AC power is available.

When the RPV pressure dropssufficiently, CS System flow to the RPV begins. A full flow test line isprovided to route water from and to the suppression pool to allow testingof the CS System without spraying water in the RPV.LPCI is an independent operating mode of the RHR System. There aretwo LPCI subsystems (Ref. 2), each consisting of two motor driven pumpsand piping and valves to transfer water from the suppression pool to theRPV via the corresponding recirculation loop. The two LPCI subsystems can be interconnected via the RHR System cross tie valves; however, atleast one of the two cross tie valves is maintained closed with its powerremoved to prevent loss of both LPCI subsystems during a LOCA. TheLPCI subsystems are designed to provide core cooling at low RPVpressure.

Upon receipt of an initiation signal, all four LPCI pumps areautomatically started.

RHR System valves in the LPCI flow path areautomatically positioned to ensure the proper flow path for water from thesuppression pool to inject into the recirculation loops. When the RPVpressure drops sufficiently, the LPCI flow to the RPV, via thecorresponding recirculation loop, begins. The water then enters thereactor through the jet pumps.(continued)

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PPL Rev. 4ECCS-Operating B 3.5.1BASESBACKGROUND Full flow test lines are provided for each LPCI subsystem to route water(continued) from the suppression pool, to allow testing of the LPCI pumps withoutinjecting water into the RPV. These test lines also provide suppression pool cooling capability, as described in LCO 3.6.2.3, "RHR Suppression Pool Cooling."

The HPCI System (Ref. 3) consists of a steam driven turbine pump unit,piping, and valves to provide steam to the turbine, as well as piping andvalves to transfer water from the suction source to the core via thefeedwater system line, where the coolant is distributed within the RPVthrough the feedwater sparger.

Suction piping for the system is providedfrom the CST and the suppression pool. Pump suction for HPCI isnormally aligned to the CST source to minimize injection of suppression pool water into the RPV. Whenever the CST water supply is low, anautomatic transfer to the suppression pool water source ensures anadequate suction head for the pump and an uninterrupted water supplyfor continuous operation of the HPCI System. The steam supply to theHPCI turbine is piped from a main steam line upstream of the associated inboard main steam isolation valve.The HPCI System is designed to provide core cooling for a wide range ofreactor pressures (165 psia to 1225 psia). Upon receipt of an initiation signal, the HPCI turbine stop valve and turbine control valve open and theturbine accelerates to a specified speed. As the HPCI flow increases, theturbine control valve is automatically adjusted to maintain design flow.Exhaust steam from the HPCI turbine is discharged to the suppression pool. A full flow test line is provided to route water to the CST to allowtesting of the HPCI System during normal operation without injecting waterinto the RPV.The ECCS pumps are provided with minimum flow bypass lines, whichdischarge to the suppression pool. The valves in these lines automatically open to prevent pump damage due to overheating when other discharge line valves are closed. To ensure rapid delivery of water to the RPV andto minimize water hammer effects, all ECCS pump discharge lines arefilled with water. The HPCI, LPCI and CS System discharge lines are keptfull of water using a "keep fill" system that is supplied using thecondensate transfer system.(continued)

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PPL Rev. 4ECCS-Operating B 3.5.1BASESBACKGROUND (continued)

The ADS (Ref. 4) consists of 6 of the 16 S/RVs. It is designed to providedepressurization of. the RCS during a small break LOCA if HPCI fails or isunable to maintain required water level in the RPV. ADS operation reduces the RPV pressure to within the operating pressure range of thelow pressure ECCS subsystems (CS and LPCI), so that these subsystems can provide coolant inventory makeup. Each of the S/RVs used forautomatic depressurization is equipped with two gas accumulators andassociated inlet check valves. The accumulators provide the pneumatic power to actuate the valves.APPLICABLE SAFETYANALYSESThe ECCS performance is evaluated for the entire spectrum of breaksizes for a postulated LOCA. The accidents for which ECCS operation isrequired are presented in References 5, 6, and 7. The required analysesand assumptions are defined in Reference

8. The results of theseanalyses are also described in Reference 9.This LCO helps to ensure that the following acceptance criteria for theECCS, established by 10 CFR 50.46 (Ref. 10), will be met following aLOCA, assuming the worst case single active component failure in theECCS:a. Maximum fuel element cladding temperature is < 2200°F;b. Maximum cladding oxidation is < 0.17 times the total claddingthickness before oxidation;

c. Maximum hydrogen generation from a zirconium water reaction is< 0.01 times the hypothetical amount that would be generated if all ofthe metal in the cladding surrounding the fuel, excluding the claddingsurrounding the plenum volume, were to react;d. The core is maintained in a coolable geometry; ande. Adequate long term cooling capability is maintained.

(continued)

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PPL Rev. 4ECCS-Operating B 3.5.1BASESAPPLICABLE SPC performed LOCA calculations for the SPC ATRIUM'T-10 fuel design.SAFETY The limiting single failures for the SPC analyses are discussed inANALYSES Reference

11. For a large break LOCA, the SPC analyses identify the(continued) recirculation loop suction piping as the limiting break location.

The SPCanalysis identifies the failure of the LPCI injection valve into the intactrecirculation loop as the most limiting single failure.For a small break LOCA, the SPC analyses identify the recirculation loopdischarge piping as the limiting break location, and a battery failure as themost severe single failure.

One ADS valve failure is analyzed as a limitingsingle failure for events requiring ADS operation.

The remaining OPERABLE ECCS subsystems provide the capability to adequately coolthe core and prevent excessive fuel damage.The ECCS satisfy Criterion 3 of the NRC Policy Statement (Ref. 15).LCO Each ECCS injection/spray subsystem and six ADS valves are required tobe OPERABLE.

The ECCS injection/spray subsystems are defined as thetwo CS subsystems, the two LPCI subsystems, and one HPCI System.The low pressure ECCS injection/spray subsystems are defined as thetwo CS subsystems and the two LPCI subsystems.

With less than the required number of ECCS subsystems

OPERABLE, the potential exists that during a limiting design basis LOCA concurrent with the worst case single failure, the limits specified in Reference 10could be exceeded.

All ECCS subsystems must therefore be OPERABLEto satisfy the single failure criterion required by Reference 10.LPCI subsystems may be considered OPERABLE during alignment andoperation for decay heat removal when below the actual RHR cut inpermissive pressure in MODE 3, if capable of being manually realigned (remote or local) to the LPCI mode and not otherwise inoperable.

Atthese low pressures and decay heat levels, a reduced complement ofECCS subsystems should provide the required core cooling, therebyallowing operation of RHR shutdown cooling when necessary.

(continued)

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PPL Rev. 4ECCS-Operating B 3.5.1BASES (continued)

APPLICABILITY All ECCS subsystems are required to be OPERABLE during MODES 1, 2,and 3, when there is considerable energy in the reactor core and corecooling would be required to prevent fuel damage in the event of a breakin the primary system piping. In MODES 2 and 3, when reactor steamdome pressure is < 150 psig, ADS and HPCI are not required to beOPERABLE because the low pressure ECCS subsystems can providesufficient flow below this pressure.

ECCS requirements for MODES 4and 5 are specified in LCO 3.5.2, "ECCS-Shutdown."

ACTIONS A Note prohibits the application of LCO 3.0.4.b to an inoperable HPCIsubsystem.

There is an increased risk associated with entering a MODEor other specified condition in the Applicability with an inoperable HPCIsubsystem and the provisions of LCO 3.0.4.b, which allow entry into aMODE or other specified condition in the Applicability with the LCO notmet after performance of a risk assessment addressing inoperable systems and components, should not be applied in this circumstance.

A. 1If any one low pressure ECCS injection/spray subsystem is inoperable forreasons other than Condition B, the inoperable subsystem must berestored to OPERABLE status within 7 days. In this Condition, theremaining OPERABLE subsystems provide adequate core cooling duringa LOCA. However, overall ECCS reliability is reduced, because a singlefailure in one of the remaining OPERABLE subsystems, concurrent with aLOCA, may result in the ECCS not being able to perform its intendedsafety function.

The 7 day Completion Time is based on a reliability study(Ref. 12) that evaluated the impact on ECCS availability, assumingvarious components and subsystems were taken out of service.

Theresults were used to calculate the average availability of ECCS equipment needed to mitigate the consequences of a LOCA as a function of allowedoutage times (i.e., Completion Times).B. 1If one LPCI pump in one or both. LPCI subsystems is inoperable, theinoperable LPCI pumps must be restored to OPERABLE status within7 days. In this Condition, the remaining OPERABLE LPCI pumps and atleast one CS subsystem (continued)

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PPL Rev. 4ECCS-Operating B 3.5.1BASESACTIONS B.1 (continued) provide adequate core cooling during a LOCA. However, overall ECCSreliability is reduced, because a single failure in one of the remaining OPERABLE subsystems, concurrent with a LOCA, may result in theECCS not being able to perform its intended safety function.

A 7 dayCompletion Time is based on a reliability study cited in Reference 12 andhas been found to be acceptable through operating experience.

C.1 and C.2If the inoperable low pressure ECCS subsystem or LPCI pump(s) cannotbe restored to OPERABLE status within the associated Completion Time,the plant must be brought to a MODE in which the LCO does not apply.To achieve this status, the plant must be brought to at least MODE 3within 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 on operating experience, to reach therequired plant conditions from full power conditions in an orderly mannerand without challenging plant systems.D.1 and D.2If the HPCI System is inoperable and the RCIC System is verified to beOPERABLE, the HPCI System must be restored to OPERABLE statuswithin 14 days. In this Condition, adequate core cooling is ensured by theOPERABILITY of the redundant and diverse low pressure ECCSinjection/spray subsystems in conjunction with ADS. Also, the RCICSystem will automatically provide makeup water at most reactor operating pressures.

Verification of RCIC OPERABILITY is therefore required whenHPCI is inoperable.

This may be performed as an administrative check byexamining logs or other information to determine if RCIC is out of servicefor maintenance or other reasons.

It does not mean to perform theSurveillances needed to demonstrate the OPERABILITY of the RCICSystem. If the OPERABILITY of the RCIC System cannot be verified,

however, Condition H must be immediately entered.

If a single activecomponent fails concurrent with a design basis LOCA, there is a potential, depending on the specific

failure, that the minimum required ECCSequipment (continued)

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PPL Rev. 4ECCS-Operating B 3.5.1BASESACTIONS D.1 and D.2 (continued) will not be available.

A 14 day Completion Time is based on a reliability study cited in Reference 12 and has been found to be acceptable throughoperating experience.

E.1 and E.2If Condition A or Condition B exists in addition to an inoperable HPCISystem, the inoperable low pressure ECCS injection/spray subsystem orthe LPCI pump(s) or the HPCI System must be restored to OPERABLEstatus within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />. In this Condition, adequate core cooling isensured by the OPERABILITY of the ADS and the remaining low pressureECCS subsystems.

However, the overall ECCS reliability is significantly reduced because a single failure in one of the remaining OPERABLEsubsystems concurrent with a design basis LOCA may result in the ECCSnot being able to perform its intended safety function.

Since both a highpressure system (HPCI) and a low pressure subsystem are inoperable, amore restrictive Completion Time of 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> is required to restore eitherthe HPCI System or the low pressure ECCS injection/spray subsystem toOPERABLE status. This Completion Time is based on a reliability studycited in Reference 12 and has been found to be acceptable throughoperating experience.

F. IThe LCO requires six ADS valves to be OPERABLE in order to providethe ADS function.

Reference 11 contains the results of an analysis thatevaluated the effect of one ADS valve being out of service.

Per thisanalysis, operation of only five ADS valves will provide the requireddepressurization.

However, overall reliability of the ADS is reduced,because a single failure in the OPERABLE ADS valves could result in areduction in depressurization capability.

Therefore, operation is onlyallowed for a limited time. The 14 day Completion Time is based on areliability study cited in Reference 12 and has been found to beacceptable through operating experience.

(continued)

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PPL Rev. 4ECCS-Operating B 3.5.1BASESACTIONS G.1 and G.2(continued)

If Condition A or Condition B exists in addition to one inoperable ADSvalve, adequate core cooling is ensured by the OPERABILITY of HPCIand the remaining low pressure ECCS injection/spray subsystem.

However, overall ECCS reliability is reduced because a single activecomponent failure concurrent with a design basis LOCA could result in theminimum required ECCS equipment not being available.

Since both ahigh pressure system (ADS) and a low pressure subsystem areinoperable, a more restrictive Completion Time of 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> is required torestore either the low pressure ECCS subsystem or the ADS valve toOPERABLE status. This Completion Time is based on a reliability studycited in Reference 12 and has been found to be acceptable throughoperating experience.

H.1 and H.2If any Required Action and associated Completion Time of Condition D, E,F, or G is not met, or if two or more ADS valves are inoperable, the plantmust be brought to a condition in which the LCO does not apply. Toachieve this status, the plant must be brought to at least MODE 3 within12 hours and reactor steam dome pressure reduced to < 150 psig 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.1.1When multiple ECCS subsystems are inoperable, as stated in Condition I,LCO 3.0.3 must be entered immediately.

SURVEILLANCE SR 3.5.1.1REQUIREMENTS The flow path piping has the potential to develop voids and pockets ofentrained air. Maintaining the pump discharge lines of the HPCI System,CS System, and LPCI subsystems (continued)

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PPL Rev. 4ECCS-Operating B 3.5.1BASESSURVEILLANCE SR 3.5.1.1 (continued)

REQUIREMENTS full of water ensures that the ECCS will perform properly, injecting its fullcapacity into the RCS upon demand. This will also prevent a waterhammer following an ECCS initiation signal. One acceptable method ofensuring that the lines are full is to vent at the high points. The 31 dayFrequency is based on the gradual nature of void buildup in the ECCSpiping, the procedural controls governing system operation, and operating experience.

SR 3.5.1.2Verifying the correct alignment for manual, power operated, and automatic valves in the ECCS flow paths provides assurance that the proper flowpaths will exist for ECCS operation.

This SR does not apply to valves thatare locked, sealed, or otherwise secured in position since these wereverified to be in the correct position prior to locking,

sealing, or securing.

A valve that receives an initiation signal is allowed to be in a nonaccident position provided the valve will automatically reposition in the properstroke time. This SR does not require any testing or valve manipulation; rather, it involves verification that those valves capable of potentially beingmispositioned are in the correct position.

This SR does not apply tovalves that cannot be inadvertently misaligned, such as check valves. Forthe HPCI System, this SR also includes the steam flow path for the turbineand the flow controller position.

The 31 day Frequency of this SR was derived from the Inservice TestingProgram requirements for performing valve testing at least once every92 days. The Frequency of 31 days is further.justified because the valvesare operated under procedural control and because improper valveposition would only affect a single subsystem.

This Frequency has beenshown to be acceptable through operating experience.

This SR is modified by a Note that allows LPCI subsystems to beconsidered OPERABLE during alignment and operation for decay heatremoval with reactor steam dome pressure less than the RHR cut inpermissive pressure in MODE 3, if capable of being manually realigned (remote or local) to the(continued)

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PPL Rev. 4ECCS-Operating B 3.5.1BASESSURVEILLANCE SR 3.5.1.2 (continued)

REQUIREMENTS LPCI mode and not otherwise inoperable.

This allows operation in theRHR shutdown cooling mode during MODE 3, if necessary.

SR 3.5.1.3Verification every 31 days that ADS gas supply header pressure is> 135 psig ensures adequate gas pressure for reliable ADS operation.

The accumulator on each ADS valve provides pneumatic pressure forvalve actuation.

The design pneumatic supply pressure requirements forthe accumulator are such that, following a failure of the pneumatic supplyto the accumulator, at least one valve actuations can occur with thedrywell at 70% of design pressure.

The ECCS safety analysis assumes only one actuation to achieve thedepressurization required for operation of the low pressure ECCS. Thisminimum required pressure of > 135 psig is provided by the containment instrument gas system. The 31 day Frequency takes into consideration administrative controls over operation of the gas system and alarmsassociated with the containment instrument gas system.SR 3.5.1.4Verification every 31 days that at least one RHR System cross tie valve isclosed and power to its operator is disconnected ensures that each LPCIsubsystem remains independent and a failure of the flow path in onesubsystem will not affect the flow path of the other LPCI subsystem.

Acceptable methods of removing power to the operator include openingthe breaker, or racking out the breaker, or removing the breaker.

If bothRHR System cross tie valves are open or power has not been removedfrom at least one closed valve operator, both LPCI subsystems must beconsidered inoperable.

The 31 day Frequency has been foundacceptable, considering that these valves are under strict administrative controls that will ensure the valves continue to remain closed with motivepower removed.(continued)

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PPL Rev. 4ECCS-Operating B 3.5.1BASESSURVEILLANCE REQUIREMENTS (continued)

SR 3.5.1.5Verification every 31 days that each 480 volt AC swing bus transfers automatically from the normal source to the alternate source on loss ofpower while supplying its respective bus demonstrates that electrical power is available to ensure proper operation of the associated LPCIinboard injection and minimum flow valves and the recirculation pumpdischarge and bypass valves. Therefore, each 480 volt AC swing busmust be OPERABLE for the associated LPCI subsystem to beOPERABLE.

The test is performed by actuating the load test switch or bydisconnecting the preferred power source to the transfer switch andverifying that swing bus automatic transfer is accomplished.

The 31 dayFrequency has been found to be acceptable through operating experience.

SR 3.5.1.6Cycling the recirculation pump discharge and bypass valves through onecomplete cycle of full travel demonstrates that the valves are mechanically OPERABLE and provides assurance that the valves will close whenrequired to ensure the proper LPCI flow path is'established.

Uponinitiation of an automatic LPCI subsystem injection signal, these valvesare required to be closed to ensure full LPCI subsystem flow injection inthe reactor via the recirculation jet pumps. De-energizing the valve in theclosed position will also ensure the proper flow path for the LPCIsubsystem.

Acceptable methods of de-energizing the valve includeopening the breaker, or racking out the breaker, or removing the breaker.The specified Frequency is once during reactor startup before THERMALPOWER is > 25% RTP. However, this SR is modified by a Note thatstates the Surveillance is only required to be performed if the lastperformance was more than 31 days ago. Therefore, implementation ofthis Note requires this test to be performed during reactor startup beforeexceeding 25% RTP. Verification during reactor startup prior to reaching> 25% RTP is an exception to the normal Inservice Testing Programgeneric valve cycling Frequency of 92 days, but is considered acceptable due to(continued)

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-UNIT 1TS / B 3.5-12Revision 0

PPL Rev. 4ECCS-Operating B 3.5.1BASESSURVEILLANCE SR 3.5.1.6 (continued)

REQUIREMENTS the demonstrated reliability of these valves. If the valve is inoperable andin the open position, the associated LPCI subsystem must be declaredinoperable.

SR 3.5.1.7, SR 3.5.1.8, and SR 3.5.1.9The performance requirements of the low pressure ECCS pumps aredetermined through application of the 10 CFR 50, Appendix K criteria(Ref. 8). This periodic Surveillance is performed (in accordance with theASME OM Code requirements for the ECCS pumps) to verify that theECCS pumps will develop the flow rates required by the respective analyses.

The low pressure ECCS pump flow rates ensure that adequatecore cooling is provided to satisfy the acceptance criteria of Reference 10.The pump flow rates are verified against a system head equivalent to theRPV pressure expected during a LOCA. The total system pump outletpressure is adequate to overcome the elevation head pressure betweenthe pump suction and the vessel discharge, the piping friction losses, andRPV pressure present during a LOCA. These values may be established during preoperational testing.The flow tests for the HPCI System are performed at two different pressure ranges such that system capability to provide rated flow is testedat both the higher and lower operating ranges of the system. Additionally, adequate steam flow must be passing through the main turbine or turbinebypass valves to continue to control reactor pressure when the HPCISystem diverts steam flow. Reactor steam pressure is considered adequate when _ 920 psig to perform SR 3.5.1.8 and >_ 150 psig toperform SR 3.5.1.9.

However, the requirements of SR 3.5.1.9 are met bya successful performance at any pressure

-< 165 psig. Adequate steamflow is represented by at least 1.25 turbine bypass valves open.Therefore, sufficient time is allowed after adequate pressure and flow areachieved to perform these tests. Reactor startup is allowed prior toperforming the low pressure Surveillance test because the reactorpressure is low and the time allowed to satisfactorily perform theSurveillance test is short. The reactor pressure is allowed to be increased to normal operating pressure since it is assumed that the low pressure testhas been satisfactorily (continued)

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-UNIT 1TS / B 3.5-13Revision 2

PPL Rev. 4ECCS-Operating B 3.5.1BASESSURVEILLANCE SR 3.5.1.7, SR 3.5.1.8.

and SR 3.5.1.9 (continued)

REQUIREMENTS completed and there is no indication or reason to believe that HPCI isinoperable.

Therefore, SR 3.5.1.8 and SR 3.5.1.9 are modified by Notes that state theSurveillances are not required to be performed until 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after thereactor steam pressure and flow are adequate to perform the test.The Frequency for SR 3.5.1.7 and SR 3.5.1.8 is in accordance with theInservice Testing Program requirements.

The 24 month Frequency forSR 3.5.1.9 is based on the need to perform the Surveillance under theconditions that apply just prior to or during a startup from a plant outage.Operating experience has shown that these components usually pass theSR when performed at the 24 month Frequency, which is based on therefueling cycle. Therefore, the Frequency was concluded to beacceptable from a reliability standpoint.

SR 3.5.1.10The ECCS subsystems are required to actuate automatically to performtheir design functions.

This Surveillance verifies that, with a requiredsystem initiation signal (actual or simulated),

the automatic initiation logicof HPCI, CS, and LPCI will cause the systems or subsystems to operateas designed, including actuation of the system throughout its'emergency operating

sequence, automatic pump startup and actuation of allautomatic valves to their required positions.

This functional test includesthe LPCI and CS interlocks between Unit 1 and Unit 2 and specifically requires the following:

A functional test of the interlocks associated with theLPCI and CS pump starts in response to an automatic initiation signal in Unit 1 followed by a false automatic initiation signal in Unit 2;A functional test of the interlocks associated with the LPCIand CS pump starts in response to an automatic initiation signal in Unit 2 followed by a false automatic initiation signal in Unit 1; and(continued)

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-UNIT 1TS / B 3.5-14Revision 0

PPL Rev. 4ECCS-Operating B 3.5.1BASESSURVEILLANCE SR 3.5.1.10 (continued)

REQUIREMENTS A functional test of the interlocks associated with the LPCIand CS pump starts in response to simultaneous occurrences of an automatic initiation signal in both Unit 1and Unit 2 and a loss of Offsite power condition affecting both Unit 1 and Unit 2.The purpose of this functional test (preferred pump logic) is to assure thatif a false LOCA signal were to be received on one Unit simultaneously with an actual LOCA signal on the second Unit, the preferred LPCI andCS pumps are started and the non-preferred LPCI and CS pumps aretripped for each Unit. This functional test is performed by verifying thatthe non-preferred LPCI and CS pumps are tripped.

The verification thatpreferred LPCI and CS pumps start is performed under a separatesurveillance test. Only one division of LPCI preferred pump logic isrequired to be OPERABLE for each Unit, because no additional failuresneeds to be postulated with a false LOCA signal. If the preferred or non-preferred pump logic for CS is inoperable, the associated CS pumps shallbe declared inoperable and the pumps should not be operated to ensurethat the opposite Unit's CS pumps or 4.16 kV ESS Buses are protected.

This SR also ensures that the HPCI System will automatically restart onan RPV low water level (Level 2) signal received subsequent to an RPVhigh water level (Level 8) tdp and that the suction is automatically transferred from the CST to the suppression pool. The LOGIC SYSTEMFUNCTIONAL TEST performed in LCO 3.3.5.1 overlaps this Surveillance.

This SR can be accomplished by any series of sequential overlapping ortotal steps such that the entire channel is tested.The 24 month Frequency is acceptable because operating experience hasshown that these components usually pass the SR when performed at the24 month Frequency, which is based on the refueling cycle. Therefore, the Frequency was concluded to be acceptable from a reliability standpoint.

This SR is modified by a Note that excludes vessel injection/spray duringthe Surveillance.

Since all active components are testable and full flowcan be demonstrated by recirculation through the test line, coolantinjection into the RPV is not required during the Surveillance.

(continued)

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PPL Rev. 4ECCS-Operating B 3.5.1BASESSURVEILLANCE REQUIREMENTS (continued)

SR 3.5.1.11The ADS designated S/RVs are required to actuate automatically uponreceipt of specific initiation signals.

A system functional test is performed to demonstrate that the mechanical portions of the ADS function (i.e.,solenoids) operate as designed when initiated either by an actual orsimulated initiation signal, causing proper actuation of all the requiredcomponents.

SR 3.5.1.12 and the LOGIC SYSTEM FUNCTIONAL TESTperformed in LCO 3.3.5.1 overlap this Surveillance to provide completetesting of the assumed safety function.

The 24 month Frequency is based on the need to perform portions of theSurveillance under the conditions that apply during a plant outage and thepotential for an unplanned transient if the Surveillance were performed with the reactor at power. Operating experience has shown that thesecomponents usually pass the SR when performed at the 24 monthFrequency, which is based on the refueling cycle. Therefore, theFrequency was concluded to be acceptable from a reliability standpoint.

This SR is modified by a Note that excludes valve actuation.

Thisprevents an RPV pressure blowdown.

SR 3.5.1.12A manual actuation of each ADS valve actuator is performed to verify thatthe valve and solenoid are functioning properly.

This is demonstrated bythe methods described below. Proper operation of the valve tailpipes isensured through the use of foreign material exclusion duringmaintenance.

Valve OPERABILITY and the setpoints for overpressure protection areverified, per ASME requirements, prior to valve installation.

(continued)

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PPL Rev. 4ECCS-Operating B 3.5.1BASESSURVEILLANCE SR 3.5.1.12 (continued)

REQUIREMENTS Manual actuation of the actuator at atmospheric temperature and pressureduring cold shutdown is performed.

Proper functioning of the valveactuator and solenoid is demonstrated by visual observation of actuatormovement.

The ADS actuator will be disconnected from the valve toensure no damage is done to the valve seat or to the valve internals.

Each valve shall be bench-tested prior to reinstallation.

The bench-test along with the test on the ADS actuator establishes the OPERABILITY ofthe valves.SR 3.5.1.11 and the LOGIC SYSTEM FUNCTIONAL TEST performed inLCO 3.3.5.1 overlap this Surveillance to provide complete testing of theassumed safety function.

The Frequency of 24 months ensures that bothsolenoids for each ADS valve are alternately tested. The Frequency isbased on the need to perform the Surveillance under the conditions thatapply just prior to or during a startup from a plant outage. Operating experience has shown that these components usually pass the SR whenperformed at the 24 month Frequency, which is based on the refueling cycle. Therefore, the Frequency was concluded to be acceptable from areliability standpoint.

SR 3.5.1.13This SR ensures that the ECCS RESPONSE TIME for each ECCSinjection/spray subsystem is less than or equal to the maximum valueassumed in the accident analysis.

Response Time testing acceptance criteria are included in Reference

13. This SR is modified by a Note thatallows the instrumentation portion of the response time to be assumed tobe based on historical response time data and therefore, is excluded fromthe ECCS RESPONSE TIME testing.

This is allowed sincetheinstrumentation response time is a small part of the ECCS RESPONSETIME (e.g., sufficient margin exists in the diesel generator start time whencompared to the instrumentation response time) (Ref. 14).(continued)

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-UNIT 1TS / B 3.5-17Revision 3

PPL Rev. 4ECCS-Operating B 3.5.1BASESSURVEILLANCE REQUIREMENTS SR 3.5.1.13 (continued)

The 24-month Frequency is consistent with the typical industry refueling cycle and is acceptable based upon plant operating experience.

REFERENCES

1. FSAR, Section 6.3.2.2.3.

2. FSAR, Section 6.3.2.2.4.

3. FSAR, Section 6.3.2.2.1.

4. FSAR, Section 6.3.2.2.2.

5. FSAR, Section 15.2.4.6. FSAR, Section 15.2.5.7. FSAR, Section 15.2.6.8. 10 CFR 50, Appendix K.9. FSAR, Section 6.3.3.10. 10 CFR 50.46.11. FSAR, Section 6.3.3.12. Memorandum from R.L. Baer (NRC) to V. Stello, Jr. (NRC),"Recommended Interim Revisions to LCOs for ECCS Components,"

December 1, 1975.13. FSAR, Section 6.3.3.3.14. NEDO 32291-A, "System Analysis for the Elimination of SelectedResponse Time Testing Requirements, October 1995.15. Final Policy Statement on Technical Specifications Improvements, July 22, 1993 (58 FR 39132).SUSQUEHANNA

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