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Technical Specifications Bases Unit 2 Manual
	ML14122A015
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Site:	Susquehanna
Issue date:	04/26/2014
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To:	; Office of Nuclear Reactor Regulation
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Apr. 26, 2014Page1 of 2MANUAL HARD COPY DISTRIBUTIONDOCUMENT TRANSMITTAL2014-19096USER INFORMATION:GERLACH*ROSEY MEMPL#:028401 CA#: 0363Address: NUCSA2Phone#: 254-3194TRANSMITTAL INFORMATION:TO: GERLACH*ROSEY M 04/26/2014LOCATION: 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.TSB2 -TECHNICAL SPECIFICATIONS BASES UNIT 2 MANUALREMOVE MANUAL TABLE OF CONTENTS DATE: 03/31/2014ADD MANUAL TABLE OF CONTENTS DATE: 04/25/2014CATEGORY: DOCUMENTS TYPE: TSB2co Apr. 26, 2014Page2 of 2ID: TEXT 3.6.4.1ADD: REV: 10REMOVE: REV:9CATEGORY: DOCUMENTSID: TEXT 3.6.4.2ADD: REV: 9REMOVE: REV:8TYPE: TSB2CATEGORY:ID: TEXTREMOVE:DOCUMENTSLOESREV:119TYPE: TSB2ADD: REV: 120CATEGORY:ID : TEXTSREMOVE :DOCUMENTSTOCREV:20TYPE: TSB2ADD: REV: 21ANY 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 ACKNOWLEDGECOMPLETE IN YOUR NIMS INBOX UPON COMPLETION OF UPDATES. FOR ELECTRONIC MANUALUSERS, ELECTRONICALLY REVIEW THE APPROPRIATE DOCUMENTS AND ACKNOWLEDGE COMPLETE INYOUR NIMS INBOX.

SSES MANUJALManual Name: TSB2Manual Title: TECHNICAL SPECIFICATIONS BASES UNIT 2 MANUALTable Of ContentsIssue Date: 04/25/2014Procedure Name RevTEXT LOES 120Title: LIST OF EFFECTIVE SECTIONSIssue Date04/25/2014Change ID Change NumberTEXT TOCTitle: TABLE OF CONTENTS21 04/25/2014TEXT 2.1.1 4Title: SAFETY LIMITS (SLS) REACTORTEXT 2.1.2 1Title: SAFETY LIMITS (SLS) REACTOR05/06/2009CORE SLS10/04/2007COOLANT SYSTEM (RCS) PRESSURE SLTEXT 3.0 3 08/20/2009Title: LIMITING CONDITION FOR OPERATION (LCO) APPLICABILITYTEXT 3. 1.1Title: REACTIVITYTEXT 3.1.2Title: REACTIVITYTEXT 3.1.3Title: REACTIVITYTEXT 3.1.4Title: REACTIVITYTEXT 3.1.5Title: REACTIVITYTEXT 3.1.6Title: REACTIVITY1 03/24/2005CONTROL SYSTEMS SHUTDOWN MARGIN (SDM)0 11/18/2002CONTROL SYSTEMS REACTIVITY ANOMALIES2 01/19/2009CONTROL SYSTEMS CONTROL ROD OPERABILITY4 01/30/2009CONTROL SYSTEMS CONTROL ROD SCRAM TIMES1CONTROL SYSTEMS07/06/2005CONTROL ROD SCRAM ACCUMULATORS3 02/24/2014CONTROL SYSTEMS ROD PATTERN CONTROLPagel of 8 Report Date: 04/25/14Page 1 of .8Report Date: 04/25/14 SSES MANTA-LManual Name: TSB2Manual Title: TECHNICAL SPECIFICATIONS BASES UNIT 2 MANUALTEXT 3.1.7Title: REACTIVITY CONTROLTEXT 3.1.8Title: REACTIVITY CONTROL3 10/04/2007SYSTEMS STANDBY LIQUID CONTROL3 05/06/2009SYSTEMS SCRAM DISCHARGE VOLUME(SLC) SYSTEM(SDV) VENT AND DRAIN VALVESTEXT 3.2.1 4 05/06/2009Title: POWER DISTRIBUTION LIMITS AVERAGE PLANAR LINEAR HEAT GENERATION RATE (APLHGR)TEXT 3. 2.2Title: POWER DISTRIBUTIONTEXT 3.2.3Title: POWER DISTRIBUTION3 05/06/2009LIMITS MINIMUM CRITICAL POWER RATIO (MCPR)2 05/06/2009LIMITS LINEAR HEAT GENERATION RATE LHGRTEXT 3.3.1.1 5 02/24/2014Title: INSTRUMENTATION REACTOR PROTECTION SYSTEM (RPS) INSTRUMENTATIONTEXT 3.3.1.2 2 01/19/2009Title: INSTRUMENTATION SOURCE RANGE MONITOR (SRM) INSTRUMENTATIONTEXT 3.3.2.1Title: INSTRUMENTATION3 02/24/2014CONTROL ROD BLOCK INSTRUMENTATIONTEXT 3.3.2.2 2 02/22/2012Title: INSTRUMENTATION FEEDWATER -MAIN TURBINE HIGH WATER LEVEL TRIP INSTRUMENTATIONTEXT 3.3.3.1 8 02/28/2013Title: INSTRUMENTATION POST ACCIDENT MONITORING (PAM) INSTRUMENTATIONTEXT 3.3.3.2 1 04/18/2005Title: INSTRUMENTATION REMOTE SHUTDOWN SYSTEMTEXT 3.3.4.1 1 05/06/2009Title: INSTRUMENTATION END OF CYCLE RECIRCULATION PUMP TRIP (EOC-RPT) INSTRUMENTATIONPage 2 of 8Report Date: 04/25/14 SSES MANUJALManual Name: TSB2Manual Title: TECHNICAL SPECIFICATIONS BASES UNIT 2 MANUALTEXT 3.3.4.2 0 11/18/2002Title: INSTRUMENTATION ANTICIPATED TRANSIENT WITHOUT SCRAM RECIRCULATION PUMP TRIP(ATWS-RPT) INSTRUMENTATIONTEXT 3.3.5.1 5 02/24/2014Title: INSTRUMENTATION EMERGENCY CORE COOLING SYSTEM (ECCS) INSTRUMENTATIONTEXT 3.3.5.2 0 11/18/2002Title: INSTRUMENTATION REACTOR CORE ISOLATION COOLING (RCIC) SYSTEM INSTRUMENTATIONTEXT 3.3.6.1 7 03/31/2014Title: INSTRUMENTATION PRIMARY CONTAINMENT ISOLATION INSTRUMENTATIONTEXT 3.3.6.2 4 09/01/2010Title: INSTRUMENTATION SECONDARY CONTAINMENT ISOLATION INSTRUMENTATIONTEXT 3.3.7.1Title: INSTRUMENTATIONINSTRUMENTATION2 10/27/2008CONTROL ROOM EMERGENCY OUTSIDE AIR SUPPLY (CREOAS) SYSTEMTEXT 3.3.8.1 3 12/17/2007Title: INSTRUMENTATION LOSS OF POWER (LOP) INSTRUMENTATIONTEXT 3.3.8.2 0 11/18/2002Title: INSTRUMENTATION REACTOR PROTECTION SYSTEM (RPS) ELECTRIC POWER MONITORINGTEXT 3.4.1 4 07/20/2010Title: REACTOR COOLANT SYSTEM (RCS) RECIRCULATION LOOPS OPERATINGTEXT 3.4.2 3 10/23/2013Title: REACTOR COOLANT SYSTEM (RCS) JET PUMPSTEXT 3.4.3 3 01/13/2012Title: REACTOR COOLANT SYSTEM (RCS) SAFETY/RELIEF VALVES (S/RVS)TEXT 3.4.4 0 11/18/2002Title: REACTOR COOLANT SYSTEM (RCS) RCS OPERATIONAL LEAKAGEPage 3 of 8Report Date: 04/25/14

.qSE~q MANT.TAI.Manual Name: TSB2Manual Title: TECHNICAL SPECIFICATIONS BASES UNIT 2 MANUALTEXT 3.4.5 3 03/10/2010Title: REACTOR COOLANT SYSTEM (RCS) RCS PRESSURE ISOLATION VALVE (PIV) LEAKAGETEXT 3.4.6 4 02/19/2014Title: REACTOR COOLANT SYSTEM (RCS) RCS LEAKAGE DETECTION INSTRUMENTATIONTEXT 3.4.7 2 10/04/2007Title: REACTOR COOLANT SYSTEM (RCS) RCS SPECIFIC ACTIVITYTEXT 3.4.8Title: REACTOR COOLANT-HOT SHUTDOWNTEXT 3.4.9Title: REACTOR COOLANT-COLD SHUTDOWN2SYSTEM (RCS)1SYSTEM (RCS)03/28/2013RESIDUAL HEAT REMOVAL (RHR) SHUTDOWN COOLING SYSTEM03/28/2013RESIDUAL HEAT REMOVAL (RHR) SHUTDOWN COOLING SYSTEM0TEXT 3.4.10 3 05/06/2009Title: REACTOR COOLANT SYSTEM (RCS) RCS PRESSURE AND TEMPERATURE (P/T) LIMITSTEXT 3.4.11 0 11/18/2002Title: REACTOR COOLANT SYSTEM (RCS) REACTOR STEAM DOME PRESSURETEXT 3.5.13 01/16/2006Title: EMERGENCY CORE COOLING SYSTEMS (ECCS) AND REACTOR CORE ISOLATIONSYSTEM ECCS -OPERATINGTEXT 3.5.2 1 02/24/2014Title: EMERGENCY CORE COOLING SYSTEMS (ECCS) AND REACTOR CORE ISOLATIONSYSTEM ECCS -SHUTDOWNTEXT 3.5.3 3 02/24/2014Title: EMERGENCY CORE COOLING SYSTEMS (ECCS) AND REACTOR CORE ISOLATIONSYSTEM RCIC SYSTEMCOOLING (RCIC)COOLING (RCIC)COOLING (RCIC)TEXT 3.6.1.1Title: PRIMARY CONTAINMENT5 02/24/2014TEXT 3.6.1.2 1 05/06/2009Title: CONTAINMENT SYSTEMS PRIMARY CONTAINMENT AIR LOCKPage4 of 8 Report Date: 04/25/14Page 4 of 8Report Date: 04/25/14 SSES MANUAL.Manual Name: TSB2Manual Title: TECHNICAL SPECIFICATIONS BASES UNIT 2 MANUALTEXT 3.6.1.3Title: CONTAINMENTTEXT 3.6.1.4Title: CONTAINMENTTEXT 3.6.1.5Title: CONTAINMENTTEXT 3.6.1.6Title: CONTAINMENTTEXT 3.6.2.1Title: CONTAINMENTTEXT 3.6.2.2Title: CONTAINMENTTEXT 3.6.2.3Title: CONTAINMENTTEXT 3.6.2.4Title: CONTAINMENTTEXT 3.6.3.1Title: CONTAINMENTTEXT 3.6.3.2Title: CONTAINMENTTEXT 3.6.3.3Title: CONTAINMENTTEXT 3.6.4.1Title: CONTAINMENT13 02/24/2014SYSTEMS PRIMARY CONTAINMENT ISOLATION VALVES (PCIVS)1 05/06/2009SYSTEMS CONTAINMENT PRESSURE1 10/05/2005SYSTEMS DRYWELL AIR TEMPERATURE0 11/18/2002SYSTEMS SUPPRESSION CHAMBER-TO-DRYWELL VACUUM BREAKERS2 12/17/2007SYSTEMS SUPPRESSION POOL AVERAGE TEMPERATURE0 11/18/2002SYSTEMS SUPPRESSION POOL WATER LEVEL1 01/16/2006SYSTEMS RESIDUAL HEAT REMOVAL (RHR) SUPPRESSION POOL COOLING0 11/18/2002SYSTEMS RESIDUAL HEAT REMOVAL (RHR) SUPPRESSION POOL SPRAY2 06/13/2006SYSTEMS PRIMARY CONTAINMENT HYDROGEN RECOMBINERS1 04/18/2005SYSTEMS DRYWELL AIR FLOW SYSTEM1 02/28/2013SYSTEMS PRIMARY CONTAINMENT OXYGEN CONCENTRATION10 04/25/2014SYSTEMS SECONDARY CONTAINMENTPages of 8 Report Date: 04/25/14Page 5 of 8Report Date: 04/25/14 SSES MANUALManual Name: TSB2Manual Title: TECHNICAL SPECIFICATIONS BASES UNIT 2 MANUALTEXT 3.6.4.2 9 04/25/2014Title: CONTAINMENT SYSTEMS SECONDARY CONTAINMENT ISOLATION VALVES (SCIVS)TEXT 3.6.4.3 4 09/21/2006Title: CONTAINMENT SYSTEMS STANDBY GAS TREATMENT (SGT) SYSTEMTEXT 3. 7.1Title: PLANT SYSTEMSULTIMATE HEAT5 04/27/2012RESIDUAL HEAT REMOVAL SERVICE WATER (RHRSW) SYSTEM AND THESINK (UHS)TEXT 3.7.2Title: PLANTTEXT 3.7.3Title: PLANTTEXT 3. 7. 4Title: PLANTTEXT 3.7.5Title: PLANTTEXT 3. 7. 6Title: PLANTTEXT 3.7.7Title: PLANTTEXT 3.7. 8Title: MAINETEXT 3.8. 12 05/02/2008SYSTEMS EMERGENCY SERVICE WATER (ESW) SYSTEM1 01/08/2010SYSTEMS CONTROL ROOM EMERGENCY OUTSIDE AIR SUPPLY (CREOAS) SYSTEM0 11/18/2002SYSTEMS CONTROL ROOM FLOOR COOLING SYSTEM1 10/04/2007SYSTEMS MAIN CONDENSER OFFGAS3 01/25/2011SYSTEMS MAIN TURBINE BYPASS SYSTEM1 10/04/2007SYSTEMS SPENT FUEL STORAGE POOL WATER LEVEL0 05/06/2009TURBINE PRESSURE REGULATION SYSTEM9 02/24/2014Title: ELECTRICAL POWER SYSTEMS AC SOURCES -OPERATINGTEXT 3.8.2 0 11/18/2002Title: ELECTRICAL POWER SYSTEMS AC SOURCES -SHUTDOWNPages of 8 Report Date: 04/25/14Page jk of 8Report Date: 04/25/14 SSES MANUALManual Name: TSB2Manual Title: TECHNICAL SPECIFICATIONS BASES UNIT 2 MANUALTEXT 3.8.3Title: ELECTRICALTEXT 3.8.4Title: ELECTRICALTEXT 3.8.5Title: ELECTRICALTEXT 3.8.6Title: ELECTRICALTEXT 3.8.7Title: ELECTRICALTEXT 3.8.8Title: ELECTRICAL4POWER SYSTEMS10/23/2013DIESEL FUEL OIL LUBE OILAND STARTING AIR3 01/19/2009POWER SYSTEMS DC SOURCES -OPERATING1POWER SYSTEMS1POWER SYSTEMS4POWER SYSTEMS12/14/2006DC SOURCES -SHUTDOWN12/14/2006BATTERY CELL PARAMETERS10/05/2005DISTRIBUTION SYSTEMS -OPERATING0 11/18/2002POWER SYSTEMS DISTRIBUTION SYSTEMS -SHUTDOWNTEXT 3.9.1Title: REFUELINGTEXT 3.9.2Title: REFUELINGTEXT 3.9.3Title: REFUELINGTEXT 3.9.4Title: REFUELINGTEXT 3.9.5Title: REFUELINGOPERATIONSOPERATIONSOPERATIONSOPERATIONSOPERATIONS0 11/18/2002REFUELING EQUIPMENT INTERLOCKS1 09/01/2010REFUEL POSITION ONE-ROD-OUT INTERLOCK0 11/18/2002CONTROL ROD POSITION0 11/18/2002CONTROL ROD POSITION INDICATION0 11/18/2002CONTROL ROD OPERABILITY -REFUELINGTEXT 3.9.61 10/04/2007Title: REFUELING OPERATIONS REACTOR PRESSURE VESSEL (RPV) WATER LEVELPage2 of 8 Report Date: 04/25/14Page 7 of .8Report Date: 04/25/14 SSES MANUALManual Name: TSB2Manual Title: TECHNICAL SPECIFICATIONS BASES UNIT 2 MANUALTEXT 3.9.7 0 11/18/2002Title: REFUELING OPERATIONS RESIDUAL HEAT REMOVAL (RHR) -HIGH WATER LEVELTEXT 3.9.8 0 11/18/2002Title: 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: SPECIALOPERATIONSOPERATIONSOPERATIONSOPERATIONSOPERATIONSOPERATIONSOPERATIONSOPERATIONS1 01/23/2008INSERVICE LEAK AND HYDROSTATIC TESTING OPERATION0 11/18/2002REACTOR MODE SWITCH INTERLOCK TESTING0 11/18/2002SINGLE CONTROL ROD WITHDRAWAL -HOT SHUTDOWN0 11/18/2002SINGLE CONTROL ROD WITHDRAWAL -COLD SHUTDOWN0 11/18/2002SINGLE CONTROL ROD DRIVE (CRD) REMOVAL -REFUELING0 11/18/2002MULTIPLE CONTROL ROD WITHDRAWAL -REFUELING1 03/24/2005CONTROL ROD TESTING -OPERATING2 04/09/2007SHUTDOWN MARGIN (SDM) TEST -REFUELINGPage8 of 8 Report Date: 04/25/14Page 8 of 8Report Date: 04/25/14 TABLE OF CONTENTS (TECHNICAL SPECIFICATIONS BASES)B2.0 SA FETY LIM ITS (SLs) ............................................................................ TS/B2.0-1B2.1.1 Reactor C ore SLs ..................................................................... TS/B2.0-1B2.1.2 Reactor Coolant System (RCS) Pressure SL ........................... TS/B2.0-6B3.0 LIMITING CONDITION FOR OPERATION (LCO) APPLICABILITY ........ TS/B3.0-1B3.0 SURVEILLANCE REQUIREMENT (SR) APPLICABILITY .......... TS/B3.0-10B3.1 REACTIVITY CONTROL SYSTEMS .................................................... B3.1-1B3.1.1 Shutdow n M argin (SDM ) ................................................................ B3.1-1B3.1.2 Reactivity A nom alies ...................................................................... B3.1-8B3.1.3 Control Rod OPERABILITY ...................................................... TS/B3.1-13B3.1.4 Control Rod Scram Times ........................................................ TS/B3.1-22B3.1.5 Control Rod Scram Accumulators ............................................ TS/B3.1-29B3.1.6 Rod Pattern Control .................................................................. TS/B3.1-34B3.1.7 Standby Liquid Control (SLC) System ...................................... TS/B3.1-39B3.1.8 Scram Discharge Volume (SDV) Vent and Drain Valves .......... TS/B3.1-47B3.2 POWER DISTRIBUTION LIMITS ................................................... TS/B3.2-1B3.2.1 Average Planar Linear Heat Generation Rate (APLHGR) ........ TS/B3.2-1B3.2.2 Minimum Critical Power Ratio (MCPR) ..................................... TS/B3.2-5B3.2.3 Linear Heat Generation Rate (LHGR) ....................................... TS/B3.2-10B3.3 INSTRUM ENTATIO N ..................................................................... TS/B 3.3-1B3.3.1.1 Reactor Protection System (RPS) Instrumentation ................... TS/B3.3-1B3.3.1.2 Source Range Monitor (SRM) Instrumentation ......................... TS/B3.3-35B3.3.2.1 Control Rod Block Instrumentation ........................................... TS/B3.3-44B3.3.2.2 Feedwater -Main Turbine High Water Level TripInstrum entation ................................................................... TS/B3 .3-55B3.3.3.1 Post Accident Monitoring (PAM) Instrumentation ..................... TS/B3.3-64B3.3.3.2 Remote Shutdown System ....................................................... TS/B3.3-76B3.3.4.1 End of Cycle Recirculation Pump Trip (EOC-RPT)Instrum entation ................................................................... T S/B 3.3-81B3.3.4.2 Anticipated Transient Without Scram RecirculationPump Trip (ATWS-RPT) Instrumentation .............................. TS/B3.3-92B3.3.5.1 Emergency Core Cooling System (ECCS)Instrum entation ................................................................... TS/B3.3-1 01B3.3.5.2 Reactor Core Isolation Cooling (RCIC) SystemInstrum entation ......................................................................... B 3.3-135B3.3.6.1 Primary Containment Isolation Instrumentation .............................. B3.3-147B3.3.6.2 Secondary Containment Isolation Instrumentation ................... TS/B3.3-180B3.3.7.1 Control Room Emergency Outside Air Supply (CREOAS)System Instrumentation ...................................................... TS/B3.3-192(continued)SUSQUEHANNA -UNIT 2TS / B TOC -1Revision 21 TABLE OF CONTENTS (TECHNICAL SPECIFICATIONS BASES)B3.3 INSTRUMENTATION (continued)B3.3.8.1 Loss of Power (LOP) Instrumentation ....................................... TS/B3.3-206B3.3.8.2 Reactor Protection System (RPS) Electric PowerM onito ring ................................................................................ B 3 .3-2 14B3.4 REACTOR COOLANT SYSTEM (RCS) ......................................... TS/B3.4-1B3.4.1 Recirculation Loops Operating ................................................. TS/B3.4-1B3.4.2 Jet P um ps ................................................................................ T S/B3.4-10B3.4.3 Safety/Relief Valves (S/RVs) ........................................................... B3.4-15B3.4.4 RCS Operational LEAKAGE ..................................................... TS/B3.4-19B3.4.5 RCS Pressure Isolation Valve (PIV) Leakage ........................... TS/B3.4-24B3.4.6 RCS Leakage Detection Instrumentation .................................. TS/B3.4-30B3.4.7 RCS Specific Activity ................................................................ TS/B3.4-35B3.4.8 Residual Heat Removal (RHR) Shutdown CoolingSystem -Hot Shutdown ........................................................... B3.4-39B3.4.9 Residual Heat Removal (RHR) Shutdown CoolingSystem -Cold Shutdown ................................................... TS/B3.4-44B3.4.10 RCS Pressure and Temperature (P/T) Limits ........................... TS/B3.4-49B3.4.11 Reactor Steam Dome Pressure TS/B3.4-58B3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) AND REACTORCORE ISOLATION COOLING (RCIC) SYSTEM ............................ TS/B3.5-1B3.5.1 ECCS -Operating ................................................................... TS/B3.5-1B3.5.2 ECCS -Shutdown ................................................................... TS/B3.5-19B3.5.3 RCIC System ........................................................................... TS/B3.5-25B3.6 CONTAINMENT SYSTEMS ........................................................... TS/B3.6-1B3.6. 1.1 Primary Containment ................................................................ TS/B3.6-1B3.6.1.2 Primary Containment Air Lock ........................................................ B3.6-7B3.6.1.3 Primary Containment Isolation Valves (PCIVs) ......................... TS/B3.6-15B3.6.1.4 Containment Pressure .............................................................. TS/B3.6-40B3.6.1.5 Drywell Air Temperature ........................................................... TS/B3.6-43B3.6.1.6 Suppression Chamber-to-Drywell Vacuum Breakers ................ TS/B3.6-46B3.6.2.1 Suppression Pool Average Temperature .................................. TS/B3.6-52B3.6.2.2 Suppression Pool Water Level ....................................................... B3.6-58B3.6.2.3 Residual Heat Removal (RHR) Suppression PoolC o o ling ...................................................................................... B 3 .6 -6 1B3.6.2.4 Residual Heat Removal (RHR) Suppression Pool Spray ................ B3.6-65B3.6.3.1 N ot U sed ................................................................................. TS/B3.6-69B3.6.3.2 Drywell Air Flow System ................................................................. B3.6-75B3.6.3.3 Primary Containment Oxygen Concentration ............................ TS/B3.6-80B3.6.4.1 Secondary Containment ........................................................... TS/B3.6-83B3.6.4.2 Secondary Containment Isolation Valves (SCIVs) .................... TS/B3.6-90B3.6.4.3 Standby Gas Treatment (SGT) System .................................... TS/B3.6-100(continued)SUSQUEHANNA -UNIT 2TS / B TOC -2Revision 21 TABLE OF CONTENTS (TECHNICAL SPECIFICATIONS BASES)B3.7 PLANT SYSTEMS ......................................................................... TS/B3.7-1B3.7.1 Residual Heat Removal Service Water (RHRSW) Systemand the Ultimate Heat Sink (UHS) ...................................... TS/B3.7-1B3.7.2 Emergency Service Water (ESW) System ................................ TS/B3.7-7B3.7.3 Control Room Emergency Outside Air Supply(CREOAS) System ............................................................. TS/B3.7-12B3.7.4 Control Room Floor Cooling System ........................................ TS/B3.7-19B3.7.5 Main Condenser Offgas ........................................................... TS/B3.7-24B3.7.6 Main Turbine Bypass System ................................................... TS/B3.7-27B3.7.7 Spent Fuel Storage Pool Water Level ...................................... TS/B3.7-31B3.7.8 Main Turbine Pressure Regulation System .............................. TS/B3.7-34B3.8 ELECTRICAL POWER SYSTEM ................................................... TS/B3.8-1B3.8.1 AC Sources -Operating .......................................................... TS/B3.8-1B3.8.2 AC Sources -Shutdown ................................................................ B3.8-39B3.8.3 Diesel Fuel Oil, Lube Oil, and Starting Air ................................ TSIB3.8-47B3.8.4 DC Sources -Operating .......................................................... TS/B3.8-56B3.8.5 DC Sources -Shutdown .......................................................... TS/B3.8-70B3.8.6 Battery Cell Parameters ........................................................... TS/B3.8-77B3.8.7 Distribution Systems -Operating ................................................... B3.8-84B3.8.8 Distribution Systems -Shutdown ................................................... B3.8-94B3.9 REFUELING OPERATIONS .......................................................... TS/B3.9-1B3.9.1 Refueling Equipment Interlocks ................................................ TS/B3.9-1B3.9.2 Refuel Position One-Rod-Out Interlock ..................................... TS/B3.9-5B3.9.3 C ontrol Rod Position ...................................................................... B3.9-9B3.9.4 Control Rod Position Indication ...................................................... B3.9-12B3.9.5 Control Rod OPERABILITY- Refueling ......................................... B3.9-16B3.9.6 Reactor Pressure Vessel (RPV) Water Level ........................... TS/B3.9-19B3.9.7 Residual Heat Removal (RHR) -High Water Level ........................ B3.9-22B3.9.8 Residual Heat Removal (RHR) -Low Water Level ......................... B3.9-26B3.10 SPECIAL OPERATIONS ............................................................... TS/B3.10-1B3.10.1 Inservice Leak and Hydrostatic Testing Operation ................... TS/B3.10-1B3.10.2 Reactor Mode Switch Interlock Testing .......................................... B3.10-6B3.10.3 Single Control Rod Withdrawal -Hot Shutdown ............................. B3.10-11B3.10.4 Single Control Rod Withdrawal -Cold Shutdown ........................... B3.10-16B3.10.5 Single Control Rod Drive (CRD) Removal -Refueling ................... B3.10-21B3.10.6 Multiple Control Rod Withdrawal -Refueling .................................. B3.10-26B3.10.7 Control Rod Testing -Operating .................................................... B3.10-30B3.10.8 SHUTDOWN MARGIN (SDM) Test- Refueling ............................. B3.10-34TSB2 TOC.doc4/17/2014SUSQUEHANNA -UNIT 2 TS / B TOC -3 Revision 21SUSQUEHANNA -UNIT 2TS / B TOC -3Revision 21 SUSQUEHANNA STEAM ELECTRIC STATIONLIST OF EFFECTIVE SECTIONS (TECHNICAL SPECIFICATIONS BASES)Section Title RevisionTOC Table of Contents 21B 2.0 SAFETY LIMITS BASESPage TS / B 2.0-1 1Pages TS / B 2.0-2 and TS / B 2.0-3 4Page TS / B 2.0-4 6Pages TS / B 2.0-5 through TS / B 2.0-8 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 Page 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 3.1-12 0Page TS / B 3.1-13 0Page TS / B 3.1-14 1Page TS / B 3.1-15 0Page TS / B 3.1-16 1Pages TS / B 3.1-17 through TS / 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 TS / B 3.1-30 through TS / B 3.1-33 0Pages TS / B 3.1.34 through TS/ B 3.1-36 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 0Page TS / B 3.1-41 1Page TS / B 3.1-42 2SUSQUEHANNA -UNIT 2 TS/B LOES-1 Revision 120SUSQUEHANNA -UNIT 2TS / B] LOES-1Revision 120 SUSQUEHANNA STEAM ELECTRIC STATIONLIST OF EFFECTIVE SECTIONS (TECHNICAL SPECIFICATIONS BASES)Section Title RevisionPages TS / B 3.1-43 1Page TS / B 3.1-44 0Page TS / B 3.1-45 3Page 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 BASESPages TS / B 3.2-1 and TS / B 3.2-2 2Page TS / B 3.2-3 4Page TS / B 3.2-4 1Page TS / B 3.2-5 3Page TS / B 3.2-6 4Page TS / B 3.2-7 3Pages TS / B 3.2-8 and TS / B 3.2-9 4Pages TS / B 3.2-10 through TS / B 3.2-12 2Page TS / B 3.2-13 1B 3.3 INSTRUMENTATIONPages 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 3.3-8 4Pages TS / B 3.3-9 through TS /B 3.3-13 3Page TS / B 3.3-14 4Pages TS / B 3.3-15 and TS / B 3.3-16 2Pages TS / B 3.3-17 through TS / B 3.3-21 3Pages TS / B 3.3-22 through TS / B 3.3-27 2Page TS / B 3.3-28 3Page TS / B 3.3-29 4Pages TS / B 3.3-30 and TS / B 3.3-31 3Pages TS / B 3.3-32 and TS / B 3.3-33 4Page TS / B 3.3-34 2Pages TS / B 3.3-34a and TS / B 3.3-34b 1Pages TS / B 3.3.34c and TS / B 3.3-34d 0Page TS / B 3.3-34e 1Pages TS / B 3.3-34f through TS / B 3.3-34i 0Pages TS / B 3.3-35 and TS / B 3.3-36 2Pages TS / B 3.3-37 and TS / B 3.3-38 1SUSQUEHANNA -UNIT 2 TS/B LOES-2 Revision 120SUSQUEHANNA -UNIT 2TS / B LOES-2Revision 120 SUSQUEHANNA STEAM ELECTRIC STATIONLIST OF EFFECTIVE SECTIONS (TECHNICAL SPECIFICATIONS BASES)Section Title RevisionPage TS / B 3.3-39 2Pages TS / B 3.3-40 through TS / B 3.3-43 1Pages TS / B 3.3-44 through TS / B 3.3-54 3Pages TS / B 3.3-54a through TS I B 3.3-54d 0Page TS / B 3.3.54e 1Page TS / B 3.3-55 2Page TS / B 3.3-56 0Page 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 5Page 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 2Pages TS I B 3.3-75a through TS / B 3.3-75c 6Pages TS / B 3.3-76 and TS / B 3.3-77 0Page TS / B 3.3-78 1Pages TS / B 3.3-79 through TS / B 3.3-81 0Page TS / B 3.3-82 1Page TS / B 3.3-83 0Pages TS / B 3.3-84 and TS / B 3.3-85 1Page TS / B 3.3-86 0Page TS / B 3.3-87 1Page TS / B 3.3-88 0Page TS / B 3.3-89 1Pages TS / B 3.3-90 and TS / B 3.3-91 0Pages TS / B 3.3-92 through TS / B 3.3-103 1Page TS / B 3.3-104 3Pages TS / B 3.3-105 and TS / B 3.3-106 1Page TS / B 3.3-107 2Page TS / B 3.3-108 1Page TS / B 3.3-109 2Pages TS / B 3.3-110 through TS/ B 3.3-112 1Page TS / B 3.3-113 2SUSQUEHANNA -UNIT 2 TS/B LOES-3 Revision 120SUSQUEHANNA -UNIT 2TS / B LOES-3Revision 120 SUSQUEHANNA STEAM ELECTRIC STATIONLIST OF EFFECTIVE SECTIONS (TECHNICAL SPECIFICATIONS BASES)Section Title RevisionPage TS / B 3.3-114 1Page TS / B 3.3-115 2Page TS / B 3.3-116 3Pages TS / B 3.3-117 and TS / B 3.3-118 2Page TS / B 3.3-119 1Page TS / B 3.3-120 2Pages TS / B 3.3-121 and TS / B 3.3-122 3Page TS / B 3.3-123 1Page TS / B 3.3-124 2Page TS / B 3.3-124a 0Page TS / B 3.3-125 1Page TS / B 3.3-126 2Page TS / B 3.3-127 3Page TS / B 3.3-128 2Pages TS / B 3.3-129 through TS / B 3.3-131 1Page TS / B 3.3-132 2Pages TS / B 3.3-133 and TS / B 3.3-134 1Pages TS / B 3.3-135 through TS / B 3.3-137 0Page TS / B 3.3-138 1Pages TS / B 3.3-139 through TS / B 3.3-146 0Pages B 3.3-147 through 8 3.3-149 0Page TS / B 3.3-150 1Pages TS / B 3.3-151 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 1Pages TS / B 3.3-163 through TS / B 3.3-166 2Pages TS / B 3.3-167 and TS / B 3.3-168 1Pages TS / 8 3.3-169 and TS / B 3.3-170 3Pages TS / B 3.3-171 through TS/ B 3.3-174 1Page TS / B 3.3-174a 1Pages TS/ 83.3-175 through TSIB 3.3-177 1Page TS / 8 3.3-178 2Page TS / 8 3.3-179 3Page TS / B 3.3-179a 2Page TS / B 3.3-180 1Page TS / B 3.3-181 3Page TS / B 3.3-182 1Page TS / 8 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 / 8 3.3-192 0SUSQUEHANNA -UNIT 2 TS/B LOES-4 Revision 120SUSQUEHANNA -UNIT 2TS / B LOES-4Revision 120 SUSQUEHANNA STEAM ELECTRIC STATIONLIST OF EFFECTIVE SECTIONS (TECHNICAL SPECIFICATIONS BASES)Section Title RevisionPage 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 3.3-205 0Page TS / B 3.3-206 1Pages B 3.3-207 through B 3.3-209 0Page TS / B 3.3-210 1Page TS / B 3.3-211 2Pages TS / B 3.3-212 and TS / B 3.3-213 1Pages B 3.3-214 through B 3.3-220 0B 3.4 REACTOR COOLANT SYSTEM BASESPages TS / B 3.4-1 and TS / B 3.4-2 2Pages TS / B 3.4-3 through TS / B 3.4-5 4Pages TS / B 3.4-6 through TS / B 3.4-9 3Page TS / B 3.4-10 1Pages TS / B 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 3.4-23 0Pages TS / B 3.4-24 through TS / B 3.4-27 0Page TS / B 3.4-28 1Page TS / B 3.4-29 3Page 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 / B 3.4-34a 0Pages TS / B 3.4-35 and TS / B 3.4-36 1Page TS / B 3.4-37 2Page 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 3.4.4-46 1Pages TS / B 3.4.4-47 and TS / B 3.4.4-48 0Page TS / B 3.4-49 3Pages TS / B 3.4-50 through TS / B 3.4-52 2Page TS / B 3.4-53 1Pages TS / B 3.4-54 through TS / B 3.4-57 2Pages TS / B 3.4-58 through TS / B 3.4-60 1SUSQUEHANNA -UNIT 2 TSIB LOES-5 Revision 120SUSQUEHANNA -UNIT 2TS / B LOES-5Revision 120 SUSQUEHANNA STEAM ELECTRIC STATIONLIST OF EFFECTIVE SECTIONS (TECHNICAL SPECIFICATIONS BASES)Section Title RevisionB 3.5 ECCS AND RCIC BASESPages TS / B 3.5-1 and TS / B 3.5-2 1Pages TS / B 3.5-3 and TS / B 3.5-4 2Page TS / B 3.5-5 3Page TS / B 3.5-6 2Pages TS / B 3.5-7 through TS / B 3.5-10 1Pages TS / B 3.5-11 and TS / B 3.5-12 2Pages TS / B 3.5-13 and TS / B 3.5-14 1Pages TS / B 3.5-15 and TS / B.3.5-16 2Page TS / B 3.5-17 3Pages TS / B 3.5-18 through TS / B 3.5-23 1Page B 3.5-24 0Page TS / B 3.5-25 1Pages TS / B 3.5-26 and TS / B 3.5-27 2Page TS / B 3.5-28 0Page TS / B 3.5-29 through TS / B 3.5-31 1B 3.6 CONTAINMENT SYSTEMS BASESPage TS / B 3.6-1 2Page TS / B 3.6-1a 4Page TS / B 3.6-2 4Page TS / 8 3.6-3 3Page TS / B 3.6-4 4Page TS / B 3.6-5 3Page TS / B 3.6-6 4Page TS / 8 3.6-6a 4Page TS / B 3.6-6b 3Page TS / B 3.6-6c 0Page 8 3.6-7 0Page TS / 3.6-8 1Pages B 3.6-9 through 8 3.6-14 0Page TS / 8 3.6-15 4Page TS / 8 3.6-15a 0Page TS / B 3.6-15b 3Pages TS / 8 3.6-16 and TS / 8 3.6-17 3Page TS / B 3.6-17a 1Pages TS / 8 3.6-18 and TS / B 3.6-19 1Page TS / B 3.6-20 2Page TS / 8 3.6-21 3SUSQUEHANNA -UNIT 2 TS/BLOES-6 Revision 120SUSQUEHANNA -UNIT 2TS / B LOES-6Revision 120 SUSQUEHANNA STEAM ELECTRIC STATIONLIST OF EFFECTIVE SECTIONS (TECHNICAL SPECIFICATIONS BASES)Section Title RevisionPages TS / B 3.6-21a and TS / B 3.6-21 b 0Pages TS / B 3.6-22 and TS / B 3.6-23 2Pages TS / B 3.6-24 and TS / B 3.6-25 1Pages TS / B 3.6-26 and TS / B 3.6-27 3Page TS / B 3.6-28 7Page TS / B 3.6-29 5Page TS / B 3.6-29a 0Page TS / B 3.6-30 2Page TS / B 3.6-31 3Pages TS / B 3.6-32 and TS / B 3.6-33 2Page TS / B 3.6-34 1Pages TS / B 3.6-35 and TS / B 3.6-36 3Page TS / B 3.6-37 2Page TS / B 3.6-38 3Page TS / B 3.6-39 7Page TS / B 3.6-39a 0Page TS / B 3.6-40 1Pages B 3.6-41 and B 3.6-42 0Pages TS / B 3.6-43 and TS / B 3.6-44 1Page TS / B 3.6-45 2Pages TS / B 3.6-46 through TS / B 3.6-50 1Page TS / B 3.6-51 2Pages TS / B 3.6-52 through TS / B 3.6-55 0Pages TS / B 3.6-56 and TS / B 3.6-57 2Pages B 3.6-58 through B 3.6-62 0Pages TS / B 3.6-63 and TS / B 3.6-64 1Pages B 3.6-65 through B 3.6-68 0Pages TS / B 3.6-69 through TS / B 3.6-71 1Page TS / B 3.6-72 2Pages TS / B 3.6-73 and TS / B 3.6-74 1Pages B 3.6-75 and B 3.6-76 0Page TS / B 3.6-77 1Pages B 3.6-78 and B 3.6-79 0Page TS / B 3.6-80 1Pages TS / B 3.6-81 and TS / B 3.6-82 0Page TS / B 3.6-83 4Page TS / B 3.6-84 2Page TS / B 3.6-85 4Pages TS / B 3.6-86 and TS / B 3.6-87 2Page TS / B 3.6-87a 2Page TS / B 3.6-88 6Page TS / B 3.6-89 3Page TS / B 3.6-89a 0SUSQUEHANNA- UNIT 2 TS/B LOES-7 Revision 120SUSQUEHANNA -UNIT 2TS / B LOES-7Revision 120 SUSQUEHANNA STEAM ELECTRIC STATIONLIST OF EFFECTIVE SECTIONS (TECHNICAL SPECIFICATIONS BASES)Section Title RevisionPages TS / B 3.6-90 and TS / B 3.6-91 3Page TS / B 3.6-92 2Pages TS / B 3.6-93 through TS / B 3.6-95 1Page TS / B 3.6-96 2Page TS / B 3.6-97 1Page TS / B 3.6-98 2Page TS / B 3.6-99 7Page TS / B 3.6-99a 6Page TS / B 3.6-99b 4Page TS / B 3.6-99c 0Pages TS / B 3.6-100 and TS / B 3.6-101 1Pages TS / B 3.6-102 and TS / B 3.6-103 2Page TS / B 3.6-104 3Page TS / B 3.6-105 2Page TS / B 3.6-106 3B 3.7 PLANT SYSTEMS BASESPage 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 2Page TS / B 3.7-6 4Page TS / B 3.7-6a 3Page TS / B 3.7-6b 2Page TS / B 3.7-6c 3Page TS / B 3.7-7 3Page TS / B 3.7-8 2Pages B 3.7-9 through B 3.7-11 0Pages 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 3.7-24 1Pages TS / B 3.7-25 and TS / B 3.7-26 0Page TS / B 3.7-27 4Pages TS / B 3.7-28 and TS / B 3.7-29 3Pages TS / B 3.7-30 and 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 0SUSQUEHANNA -UNIT 2 TS/B LOES-8 Revision 120SUSQUEHANNA -UNIT 2TS / B LOES-8Revision 120 SUSQUEHANNA STEAM ELECTRIC STATIONLIST OF EFFECTIVE SECTIONS (TECHNICAL SPECIFICATIONS BASES)Section Title RevisionB 3.8 ELECTRICAL POWER SYSTEMS BASESPage TS / B 3.8-1 1Pages B 3.8-2 and B 3.8-3 0Page TS / B 3.8-4 1Pages TS / B 3.8-4a and TS / B 3.8-4b 0Pages TS / B 3.8-5 and TS / B 3.8-6 3Page TS / B 3.8-6a 1Pages B 3.8-7 and B 3.8-8 0Page TS / B 3.8-9 2Pages TS / B 3.8-10 and TS / B 3.8-11 1Pages B 3.8-12 through B 3.8-18 0Page TS / B 3.8-19 1Pages B 3.8-20 through B 3.8-22 0Page TS / B 3.8-23 1Page B 3.8-24 0Pages TS / B 3.8-25 and TS / B 3.8-26 1Pages B 3.8-27 through B 3.8-30 0Page TS / B 3.8-31 1Pages TS / B 3.8-32 through TS / B 3.8-35 0Page TS / B 3.8-36 1Page TS / B 3.8-37 0Page TS / B 3.8-38 1Pages B 3.8-39 through B 3.8-46 0Page TS / B 3.8-47 3Pages TS / B 3.8-48 through TS / B 3.8-50 0Pages TS / B 3.8-51 and TS / B 3.8-52 3Page TS / B 3.8-53 1Page TS / B 3.8-54 0Page TS / B 3.8-55 1Pages TS / B 3.8-56 through TS / B 3.8-59 2Pages TS / B 3.8-60 through TS / B 3.8-64 3Page TS / B 3.8-65 4Page TS / B 3.8-66 5Pages TS / B 3.8-67 and TS / B 3.8-68 4Page TS / B 3.8-69 5Pages TS / B 3.8-70 through TS / B 3.8-83 1Pages TS / B 3.8-83A through TS / B 3.8-83D 0Pages B 3.8-84 through B 3.8-85 0Page TS / B 3.8-86 1Page TS / B 3.8-87 2Pages TS / B 3.8-88 and TS / B 3.8-89 1Page TS / B 3.8-90 2Pages TS / B 3.8-91 through TS / B 3.8-93 1Pages B 3.8-94 through B 3.8-99 0SUSQUEHANNA -UNIT 2 TS/BLOES-9 Revision 120SUSQUEHANNA -UNIT 2TS / B LOES-9Revision 120 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 3.9-2 1Page TS / B 3.9-2a 1Pages TS!/ B 3.9-3 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 3.10-32 0Page TS / B 3.10-33 2Page B 3.10-34 0Page TS / B 3.10-35 1Pages B 3.10-36 and B 3.10-37 0Page TS / B 3.10-38 1Page TS / B 3.10-39 2TSB2 Text LOES.doc 4/1512014SUSQUEHANNA -UNIT 2 TS / B LOES-lO Revision 120SUSQUEHANNA -UNIT 2TS / B LOES-1 0Revision 120 PPL Rev. 10Secondary ContainmentB 3.6.4.1B 3.6 CONTAINMENT SYSTEMSB 3.6.4.1 Secondary ContainmentBASESBACKGROUNDThe 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 secondarycontainment 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 structure 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 III, each of which must beOPERABLE depending on plant status and the alignment of thesecondary containment boundary. Specifically, the Unit 1 secondarycontainment boundary can be modified to exclude Zone I1. Similarly, theUnit 2 secondary containment boundary can be modified to exclude ZoneI. Secondary containment may consist of only Zone III when in MODE 4 or5 during CORE ALTERATIONS, or during handling of irradiated fuel withinthe Zone III secondary containment boundary.(continued)SUSQUEHANNA -UNIT 2TS / B 3.6-83Revision 4 PPL Rev. 10Secondary ContainmentB 3.6.4.1BASESBACKGROUND(continued)To prevent ground level exfiltration while allowing the secondarycontainment to be designed as a conventional structure, the secondarycontainment 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, "SecondaryContainment 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).APPLICABLESAFETYANALYSESThere are two principal accidents for which credit is taken for secondarycontainment 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 those leakage paths and associatedleakage 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 componentslocated 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 containmentboundary 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).SUSQUEHANNA -UNIT 2TS / B 3.6-84Revision 2 PPL Rev. 10Secondary ContainmentB 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 0.00111 hours 6.613757e-6 weeks 1.522e-6 months . The 4 hour4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months 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 (requiringsecondary containment OPERABILITY) occurring during periods wheresecondary containment is inoperable is minimal.A temporary (one-time) Completion Time is connected to the CompletionTime Requirements above (4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months ) with an "OR" connector. TheTemporary Completion Time is 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months and applies to the replacement ofthe Reactor Building Recirculating Fan Damper Motors. The TemporaryCompletion Time of 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months 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 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 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)SUSQUEHANNA -UNIT 2TS / B 3.6-85Revision 4 PPL Rev. 10Secondary ContainmentB 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 containmentis 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 3.6.4.1.1REQUIREMENTSThis SR ensures that the secondary containment boundary is sufficientlyleak tight to preclude exfiltration under expected wind conditions.Expected wind conditions are defined as sustained wind speeds of lessthan or equal to 16 mph at the 60m meteorological tower or less than orequal to 11 mph at the 1 Om meteorological tower if the 60m tower windspeed is not available. Changes in indicated reactor building differentialpressure observed during periods of short-term wind speed gusts abovethese sustained speeds do not by themselves impact secondarycontainment integrity. However, if secondary containment integrity isknown to be compromised, the LCO must be entered regardless of windspeed.(continued)SUSQUEHANNA -UNIT 2TS / B 3.6-86Revision 2 PPL Rev. 10Secondary ContainmentB 3.6.4.1BASESSURVEILLANCE SR 3.6.4.1.1 (continued)REQUIREMENTSThe 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months Frequency of this SR was developed based on operatingexperience 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 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 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 3.6.4.1.3Verifying 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 mayhave multiple inner or multiple outer doors. The intent is to maintain thesecondary containment barrier intact, which is achieved by maintainingthe 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)SUSQUEHANNA -UNIT 2TS / B 3.6-87Revision 2 PPL Rev. 10Secondary ContainmentB 3.6.4.1BASESSURVEILLANCEREQUIREMENTSSR 3.6.4.1.2 and SR 3.6.4.1.3 (continued)When an access opening between secondary containment zones is beingused for exit and entry, then at least one door (where two doors areprovided) must remain closed. The access openings between secondarycontainment zones which are not provided with two doors areadministratively controlled to maintain secondary containment integrityduring exit and entry. This Surveillance is modified by a Note that allowsaccess openings with a single door (i.e., no airlock) within the secondarycontainment boundary (i.e., between required secondary containmentzones) to be opened for entry and exit. Opening of an access door forentry and exit allows sufficient administrative control by individualpersonnel making the entries and exits to assure the secondarycontainment 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)SUSQUEHANNA -UNIT 2TS / B 3.6-87aRevision 2 PPL Rev. 10Secondary ContainmentB 3.6.4.1BASESSURVEILLANCEREQUIREMENTS(continued)SR 3.6.4.1.4 and SR 3.6.4.1.5The 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 containmentthat is less than the pressure external to the secondary containmentboundary. This is confirmed by demonstrating that one SGT subsystemwill 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 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months at less than orequal to the maximum flow rate permitted for the secondary containmentconfiguration that is operable. The 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months test period allows secondarycontainment 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 3.6.4.1.5TEST CONFIGURATION ACCEPTANCE CRITERIA) ACCEPTANCE CRITERIA)Group 1Zones I, II and III (Unit 1 _ 300 Seconds _ 5400 CFMRailroad Bay aligned to (Zones 1, 11, and Ill) (From Zones 1, 11, and Ill)Secondary Containment).Zones II and III (Unit 1 _ 300 Seconds < 4000 CFMRailroad Bay aligned to (Zones II and Ill) (From Zones II and Ill)Zone Ill).Group 2Zones 1, 11 and III (Unit 1 < 300 Seconds < 5300 CFMRailroad Bay not aligned (Zones 1, 11, and Ill) (From Zones 1, 11, and Ill)to SecondaryContainment).Zones II and III (Unit 1 < 300 Seconds < 3900 CFMRailroad Bay not aligned (Zones II and Ill) (From Zones II and III)to SecondaryContainment).Only one of the above listed configurations needs to be tested to confirm secondarycontainment OPERABILITY.(continued)SUSQUEHANNA -UNIT 2TS / B 3.6-88Revision 6 PPL Rev. 10Secondary ContainmentB 3.6.4.1BASESSURVEILLANCE SR 3.6.4.1.4 and SR 3.6.4.1.5 (continued)REQUIREMENTSA 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 configurationis tested every 60 months. The 60 month Frequency is acceptablebecause operating experience has shown that these components usuallypass the Surveillance and all active components are tested morefrequently. Therefore, these tests are used to ensure secondarycontainment 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 performedwith the Unit 1 Railroad Bay aligned in the most limiting configuration.More specifically, secondary containment drawdown testing will beperformed with the Unit 1 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.Note that aligning the Railroad Bay to either Zone I or III is acceptablesince either zone is part of secondary containment when 3 zone testing isperformed. When a Zone II & III test is performed with the Unit 1 RailroadBay aligned to Secondary Containment, it must be aligned to Zone IIIsince aligning to Zone I will not allow communication with the isolatedzones. The most limiting Unit 1 Railroad Bay alignment shall beestablished each Surveillance period (60 month). Subsequent drawdowntesting during the same Surveillance period only requires testing of theUnit 1 Railroad Bay in the most limiting configuration. For example, Zone1, 11, and III Surveillance testing is performed with the Unit 1 Railroad Bayaligned both as a No Zone with the Railroad Bay door open and as ZoneI1l. If the Surveillance testing determined the most limiting configurationoccurs with the Unit 1 Railroad Bay aligned as Zone III, then subsequentZone II and III drawdown testing during the same Surveillance period onlyneeds to be performed with the Unit 1 Railroad Bay aligned as Zone Il1.(continued)SUSQUEHANNA -UNIT 2TS / B 3.6-89Revision 3 PPL Rev. 10Secondary ContainmentB 3.6.4.1BASESSURVEILLANCEREQUIREMENTSSR 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).(continued)SUSQUEHANNA -UNIT 2TS / B 3.6-89aRevision 0 PPL Rev. 9SCIVsB 3.6.4.2B 3.6 CONTAINMENT SYSTEMSB 3.6.4.2 Secondary Containment Isolation Valves (SCIVs)BASESBACKGROUNDThe function of the SCIVs, in combination with other accident mitigationsystems, is to limit fission product release during and following postulatedDesign Basis Accidents (DBAs) (Ref. 1). Secondary containment isolationwithin the time limits specified for those isolation valves designed to closeautomatically ensures that fission products that leak from primarycontainment into secondary containment following a DBA, or that arereleased during certain operations when primary containment is not requiredto be OPERABLE or take place outside primary containment, aremaintained within the secondary containment boundary.The OPERABILITY requirements for SCIVs help ensure that an adequatesecondary containment boundary is maintained during and after an accidentby minimizing potential paths to the environment. These isolation devicesconsist of either passive devices or active (automatic) devices. Manualvalves or dampers, de-activated automatic valves or dampers secured intheir closed position (including check valves with flow through the valvesecured), and blind flanges are considered passive devices.Automatic SCIVs close on a secondary containment isolation signal toestablish a boundary for untreated radioactive material within secondarycontainment following a DBA or other accidents.Other non-sealed penetrations which cross a secondary containmentboundary are isolated by the use of valves in the closed position or blindflanges.APPLICABLESAFETYANALYSESThe SCIVs must be OPERABLE to ensure the secondary containmentbarrier to fission product releases is established. The principal accidents forwhich the secondary containment boundary is required are a loss of coolantaccident (Ref. 1) and a fuel handling accident inside secondary containment(Ref. 2). The secondary containment performs no active function inresponse to either of these limiting events, but the boundary(continued)SUSQUEHANNA -UNIT 2TS / B 3.6-90Revision 3 PPL Rev. 9SCIVsB 3.6.4.2BASESAPPLICABLE established by SCIVs is required to ensure that leakage from the primarySAFETY containment is processed by the Standby Gas Treatment (SGT) SystemANALYSES before being released to the environment.(continued)Maintaining SCIVs OPERABLE with isolation times within limits ensures thatfission products will remain trapped inside secondary containment so thatthey can be treated by the SGT System prior to discharge to theenvironment.SCIVs satisfy Criterion 3 of the NRC Policy Statement (Ref. 3).LCO SCIVs that form a part of the secondary containment boundary are requiredto be OPERABLE. Depending on the configuration of the secondarycontainment only specific SCIVs are required. The SCIV safety function isrelated to control of offsite radiation releases resulting from DBAs.The automatic isolation valves are considered OPERABLE when theirisolation times are within limits and the valves actuate on an automaticisolation signal. The valves covered by this LCO, along with theirassociated stroke times, are listed in Table B 3.6.4.2-1.The normally closed isolation valves or blind flanges are consideredOPERABLE when manual valves are closed or open in accordance withappropriate administrative controls, automatic SCIVs are deactivated andsecured in their closed position, or blind flanges are in place. These passiveisolation valves or devices are listed in Table B3.6.4.2-2. Penetrationsclosed with sealants are considered part of the secondary containmentboundary and are not considered penetration flow paths.Certain plant piping systems (e.g., Service Water, RHR Service Water,Emergency Service Water, Feedwater, etc.) penetrate the secondarycontainment boundary. The intact piping within secondary containmentprovides a passive barrier which maintains secondary containmentrequirements. When the SDHR and temporary chiller system piping isconnected and full of water, the piping forms the secondary containmentboundary and the passive devices in TS Bases Table B3.6.4.2-2 are nolonger required for these systems since the piping forms the barrier. Duringcertain plant evolutions, piping systems may be drained and breachedwithin secondary containment. During the pipe breach, system isolationvalves can be used to provide secondary containment isolation. Theisolation valve alignment will be controlled when the piping system isbreached.(continued)SUSQUEHANNA -UNIT 2TS / B 3.6-91Revision 3 PPL Rev. 9SClVsB 3.6.4.2BASES (continued)APPLICABILITY In MODES 1,2, and 3, a DBA could lead to a fission product release to theprimary containment that leaks to the secondary containment. Therefore,the OPERABILITY of SCIVs is required.In MODES 4 and 5, the probability and consequences of these events arereduced due to pressure and temperature limitations in these MODES.Therefore, maintaining SCIVs OPERABLE is not required in MODE 4 or 5,except for other situations under which significant radioactive releases canbe postulated, 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.Moving irradiated fuel assemblies in the secondary containment may alsooccur in MODES 1, 2, and 3.ACTIONS The ACTIONS are modified by three Notes. The first Note allowspenetration flow paths to be unisolated intermittently under administrativecontrols. These controls consist of stationing a dedicated operator, who isin continuous communication with the control room, at the controls of theisolation device. In this way, the penetration can be rapidly isolated when aneed for secondary containment isolation is indicated.The second Note provides clarification that for the purpose of this LCOseparate Condition entry is allowed for each penetration flow path. This isacceptable, since the Required Actions for each Condition provideappropriate compensatory actions for each inoperable SCIV. Complyingwith the Required Actions may allow for continued operation, andsubsequent inoperable SCIVs are governed by subsequent Condition entryand application of associated Required Actions.The third Note ensures appropriate remedial actions are taken, if necessary,if the affected system(s) are rendered inoperable by an inoperable SCIV.A.1 and A.2In the event that there are one or more required penetration flow paths withone required SCIV inoperable, the affected penetration flow path(s) must beisolated. The method of isolation must include the use of at least oneisolation barder that cannot be adversely affected by a single active failure.Isolation barriers that meet this criterion are a closed and de-activatedautomatic SCIV, a closed manual valve, and a blind flange. Forpenetrations isolated in(continued)SUSQUEHANNA -UNIT 2TS / B 3.6-92Revision 2 PPL Rev. 9SCIVsB 3.6.4.2BASESACTIONS A.1 and A.2 (continued)accordance with Required Action A. 1, the device used to isolate thepenetration should be the closest available device to secondarycontainment. The Required Action must be completed within the 8 hourCompletion Time. The specified time period is reasonable considering thetime required to isolate the penetration, and the probability of a DBA, whichrequires the SCIVs to close, occurring during this short time is very low.For affected penetrations that have been isolated in accordance withRequired Action A. 1, the affected penetration must be verified to be isolatedon a periodic basis. This is necessary to ensure that secondarycontainment penetrations required to be isolated following an accident, butno longer capable of being automatically isolated, will be in the isolationposition should an event occur. The Completion Time of once per 31 daysis appropriate because the valves are operated under administrativecontrols and the probability of their misalignment is low. This RequiredAction does not require any testing or device manipulation. Rather, itinvolves verification that the affected penetration remains isolated.Condition A is modified by a Note indicating that this Condition is onlyapplicable to those penetration flow paths with two SCIVs. For penetrationflow paths with one SCIV, Condition C provides the appropriate RequiredActions.Required Action A.2 is modified by a Note that applies to devices located inhigh radiation areas and allows them to be verified closed by use ofadministrative controls. Allowing verification by administrative controls isconsidered acceptable, since access to these areas is typically restricted.Therefore, the probability of misalignment, once they have been verified tobe in the proper position, is low.B. IWith two SCIVs in one or more penetration flow paths inoperable, theaffected penetration flow path must be isolated within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months . The methodof isolation must(continued)SUSQUEHANNA -UNIT 2TS / B 3.6-93Revision 1 PPL Rev. 9SCIVsB 3.6.4.2BASESACTIONS B.1 (continued)include the use of at least one isolation barrier that cannot be adverselyaffected by a single active failure. Isolation barriers that meet this criterionare a closed and de-activated automatic valve, a closed manual valve, anda blind flange. The 4 hour4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months Completion Time is reasonable considering thetime required to isolate the penetration and the probability of a DBA, whichrequires the SCIVs to close, occurring during this short time, is very low.The Condition has been modified by a Note stating that Condition B is onlyapplicable to penetration flow paths with two isolation valves. Forpenetration flow paths with one SCIV, Condition C provides the appropriateRequired Actions.C.1 and C.2With one or more required penetration flow paths with one required SCIVinoperable, the inoperable valve must be restored to OPERABLE status orthe affected penetration flow path must be isolated. The method of isolationmust include the use of at least one isolation barrier that cannot beadversely affected by a single active failure. Isolation barriers that meet thiscriterion are a closed and de-activated automatic valve, a closed manualvalve, and a blind flange. A check valve may not be used to isolate theaffected penetration. Required Action C.1 must be completed within the4 hour Completion Time. The Completion Time of 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months is reasonableconsidering the relative stability of the system (hence, reliability) to act as apenetration isolation boundary and the relative importance of supportingsecondary containment OPERABILITY during MODES 1, 2, and 3.In the event the affected penetration flow path is isolated in accordance withRequired Action C.1, the affected penetration must be verified to be isolatedon a periodic basis. This is necessary to ensure that secondarycontainment penetrations required to be isolated following an accident areisolated.The Completion Time of once per 31 days for verifying each affectedpenetration is isolated is appropriate because the(continued)SUSQUEHANNA -UNIT 2TS / B 3.6-94Revision 1 PPL Rev. 9SCIVsB 3.6.4.2BASESACTIONS C.1 and C.2 (continued)valves are operated under administrative controls and the probability of theirmisalignment is low.Condition C is modified by a Note indicating that this Condition is onlyapplicable to penetration flow paths with only one SCIV. For penetrationflow paths with two SCIVs, Conditions A and B provide the appropriateRequired Actions.Required Action C.2 is modified by a Note that applies to valves and blindflanges located in high radiation areas and allows them to be verified by useof administrative means. Allowing verification by administrative means isconsidered acceptable, since access to these areas is typically restricted.Therefore, the probability of misalignment of these valves, once they havebeen verified to be in the proper position, is low.D.1 and D.2If any Required Action and associated Completion Time cannot be met, theplant must be brought to a MODE in which the LCO does not apply. Toachieve this status, the plant must be brought to at least MODE 3 within12 hours and to MODE 4 within 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months . The allowed Completion Timesare reasonable, based on operating experience, to reach the required plantconditions from full power conditions in an orderly manner and withoutchallenging plant systems.E.1, E.2, and E.3If any Required Action and associated Completion Time are not met, theplant must be placed in a condition in which the LCO does not apply. Ifapplicable, CORE ALTERATIONS and the movement of irradiated fuelassemblies in the secondary containment must be immediately suspended.Suspension of these activities shall not preclude completion of movement ofa component to a safe position. Also, if applicable, actions must beimmediately initiated to suspend OPDRVs in order to minimize theprobability of a vessel draindown and the subsequent potential for fissionproduct release. Actions must continue until OPDRVs are suspended.(continued)SUSQUEHANNA -UNIT 2TS / B 3.6-95Revision 1 PPL Rev. 9SCIVsB 3.6.4.2BASESACTIONS E.1, E.2, and E.3 (continued)Required Action E.A has been modified by a Note stating that LCO 3.0.3is not applicable. If moving irradiated fuel assemblies while in MODE 4or 5, LCO 3.0.3 would not specify any action. If moving fuel while inMODE 1, 2, or 3, the fuel movement is independent of reactor operations.Therefore, in either case, inability to suspend movement of irradiated fuelassemblies would not be a sufficient reason to require a reactorshutdown.SURVEILLANCEREQUIREMENTSSR 3.6.4.2.1This SR verifies that each secondary containment manual isolation valveand blind flange that is required to be closed during accident conditions isclosed. The SR helps to ensure that post accident leakage of radioactivefluids or gases outside of the secondary containment boundary is withindesign limits. This SR does not require any testing or valve manipulation.Rather, it involves verification (typically visual) that those required SCIVsin secondary containment that are capable of being mispositioned are inthe correct position.Since these SCIVs are readily accessible to personnel during normaloperation and verification of their position is relatively easy, the 31 dayFrequency was chosen to provide added assurance that the SCIVs are inthe correct positions.Two Notes have been added to this SR. The first Note applies to valvesand blind flanges located in high radiation areas and allows them to beverified by use of administrative controls. Allowing verification byadministrative controls is considered acceptable, since access to theseareas is typically restricted during MODES 1, 2, and 3 for ALARAreasons. Therefore, the probability of misalignment of these SCIVs, oncethey have been verified to be in the proper position, is low.A second Note has been included to clarify that SCIVs that are openunder administrative controls are not required to meet the SR during thetime the SCIVs are open.(continued)ISUSQUEHANNA -UNIT 2TS / B 3.6-96Revision 2 PPL Rev. 9SCIVsB 3.6.4.2BASESSURVEILLANCEREQUIREMENTS(continued)SR 3.6.4.2.2SCIVs with maximum isolation times specified in Table B 3.6.2.4-1 aretested every 92 days to verify that the isolation time is within limits todemonstrate OPERABILITY. Automatic SCIVs without maximum isolationtimes specified in Table B 3.6.4.2-1 are tested under the requirements ofSR 3.6.4.2.3. The isolation time test ensures that the SCIV will isolate ina time period less than or equal to that assumed in the safety analyses.SR 3.6.4.2.3Verifying that each automatic required SCIV closes on a secondarycontainment isolation signal is required to prevent leakage of radioactivematerial from secondary containment following a DBA or other accidents.This SR ensures that each automatic SCIV will actuate to the isolationposition on a secondary containment isolation signal. The LOGICSYSTEM FUNCTIONAL TEST in SR 3.3.6.2.5 overlaps this SR to providecomplete testing of the safety function. The 24 month Frequency isbased on the need to perform this Surveillance under the conditions thatapply during a plant outage and the potential for an unplanned transient ifthe Surveillance were performed with the reactor at power. Operatingexperience has shown these components usually pass the Surveillancewhen performed at the 24 month Frequency. Therefore, the Frequencywas concluded to be acceptable from a reliability standpoint.REFERENCES 1. FSAR, Section 6.2.2. FSAR, Section 15.3. Final Policy Statement on Technical Specifications Improvements,July 22, 1993 (58 FR 39132).SUSQUEHANNA -UNIT 2TS / B 3.6-97Revision 1 PPL Rev. 9SCIVsB 3.6.4.2Table B 3.6.4.2-1Secondary Containment Ventilation SystemAutomatic Isolation Dampers(Page 1 of 1)Reactor MaximumBuilding Valve Number Valve Description Type of Valve IsolationBlne i TimeZone I(Seconds)I HD-17586 A&B Supply System Dampers Automatic Isolation Damper 10.0I HD-1 7524 A&B Filtered Exhaust System Dampers Automatic Isolation Damper 10.0I HD-17576A&B Unfiltered Exhaust System Automatic Isolation Damper 10.0II HD-27586 A&B Supply System Dampers Automatic Isolation Damper 10.0II HD-27524 A&B Filtered Exhaust System Dampers Automatic Isolation Damper 10.0II HD-27576 A&B Unfiltered Exhaust System Automatic Isolation Damper 10.0Ill HD-17564 A&B Supply System Dampers Automatic Isolation Damper 14.0Ill HD-17514A&B Filtered Exhaust System Dampers Automatic Isolation Damper 6.5III HD-1 7502 A&B Unfiltered Exhaust System Automatic Isolation Damper 6.0Ill HD-27564 A&B Supply System Dampers Automatic Isolation Damper 14.0III HD-27514 A&B Filtered Exhaust System Dampers Automatic Isolation Damper 6.5Ill HD-27502 A&B Unfiltered Exhaust System Automatic Isolation Damper 6.0N/A HD-17534A Zone 3 Airlock 1-606 Automatic Isolation Damper N/AN/A HD-17534B Zone 3 Airlock 1-611 Automatic Isolation Damper N/AN/A HD-17534D Zone 3 Airlock 1-803 Automatic Isolation Damper N/AN/A HD-17534E Zone 3 Airlock 1-805 Automatic Isolation Damper N/AN/A HD-17534F Zone 3 Airlock 1-617 Automatic Isolation Damper N/AN/A HD-17534H Zone 3 Airlock 1-618 Automatic Isolation Damper N/AN/A HD-27534A Zone 3 Airlock 11-606 Automatic Isolation Damper N/AN/A HD-27534D Zone 3 Airlock 11-803 Automatic Isolation Damper N/AN/A HD-27534E Zone 3 Airlock 11-805 Automatic Isolation Damper N/AN/A HD-27534G Zone 3 Airlock C-806 Automatic Isolation Damper N/AN/A HD-27534H Zone 3 Airlock 11-618 Automatic Isolation Damper N/AN/A HD-275341 Zone 3 Airlock 11-609 Automatic Isolation Damper N/ASUSQUEHANNA- UNIT 2TS / B 3.6-98Revision 2 PPL Rev. 9SCIVsB 3.6.4.2Table B 3.6.4.2-2Secondary Containment Ventilation SystemPassive Isolation Valves or Devices(Page 1 of 4)Device Number Device Description Area/Elev. Required Position / NotesX-29-2-44 SDHR System to Fuel Pool Cooling Yard/670 Blind Flanged / Note 1X-29-2-45 SDHR System to Fuel Pool Cooling Yard/670 Blind Flanged / Note 1110176 SDHR Supply Drain Vlv 29/670 Closed Manual Iso Valve I Note 1110186 SDHR Discharge Drain VIv 29/670 Closed Manual Iso Valve / Note 1110180 SDHR Supply Vent Vlv 29/749 Closed Manual Iso Valve / Note 1110181 SDHR Discharge Fill Vlv 27/749 Closed Manual Iso Valve / Note 1110182 SDH R Discharge Vent VIv 27/749 Closed Manual Iso Valve / Note 1110187 SDHR Supply Fill Vlv 29/749 Closed Manual Iso Valve / Note 1210186 SDHR Supply Drain Vlv 33/749 Closed Manual Iso Valve / Note 1210187 SDHR Supply Vent Vlv 33/749 Closed Manual Iso Valve / Note 1210191 SDHR Discharge Vent Vlv 30/749 Closed Manual Iso Valve I Note 1210192 SDHR Discharge Drain VIv 30/749 Closed Manual Iso Valve / Note 1210193 SDH R Discharge Vent VIv 33/749 Closed Manual Iso Valve / Note 1X-29-2-46 Temporary Chiller to RBCW Yard/670 Blind Flanged / Note 2X-29-2-47 Temporary Chiller to RBCW Yard/670 Blind Flanged / Note 2X-29-5-95 Temporary Chiller to Unit I RBCW 29/749 Blind Flanged I Note 2X-29-5-96 Temporary Chiller to Unit 1 RBCW 29/749 Blind Flanged / Note 2X-29-5-91 Temporary Chiller to Unit 2 RBCW 33/749 Blind Flanged / Note 2X-29-5-92 Temporary Chiller to Unit 2 RBCW 33/749 Blind Flanged / Note 2187388 RBCW Temp Chiller Discharge Iso Vlv 29/670 Closed Manual Iso Valve / Note 2187389 RBCW Temp Chiller Supply Iso Vlv 29/670 Closed Manual Iso Valve / Note 2187390 RBCW Temp Chiller Supply Drain Vlv 29/670 Closed Manual Iso Valve / Note 2187391 RBCW Temp Chiller Discharge Drain Vlv 29/670 Closed Manual iso Valve / Note 2X-28-2-3000 Utility Penetration to Unit 1 East Stairwell Yard/670 Blind Flanged / Note 3X-29-2-48 Utility Penetration to Unit 1 RR Bay Yard/670 Capped / Note 5X-33-2-3000 Utility Penetration to Unit 2 East Stairwell Yard/670 Blind Flanged / Note 4X-28-2-3000 Utility Penetration to Unit 1 East Stairwell 28/670 Blind Flanged / Note 3X-29-2-48 Utility Penetration to Unit 1 RR Bay 29/670 Capped / Note 5X-33-2-3000 Utility Penetration to Unit 2 East Stairwell 33/670 Blind Flanged / Note 4X-29-3-54 Utility Penetration to Unit 1 RBCCW Hx Area 27/683 Blind Flanged / Note 6X-29-3-55 Utility Penetration to Unit 1 RBCCW Hx Area 27/683 Blind Flanged / Note 6X-29-5-97 Utility Penetration from Unit 1 RR Bay to Unit 2 Elev. 33/749 CappedX-29-5-97________749X-27-6-42 Diamond Plate Cover over Floor Penetration 271779' InstalledX-27-6-92 Instrument Tubing Stubs 27/779' CappedX-29-7-4 1" Spare Conduit Threaded Plug 29/818' InstalledX-30-6-72 Instrument Tubing Stubs 30/779' CappedX-30-6-1002 Stairwell #214 Rupture Disc 30/779' Installed IntactX-30-6-1003 Airlock 11-609 Rupture Disc 30/-79' Installed IntactX-25-6-1 008 Airlock 1-606 Rupture Disc 25/779' Installed IntactX-29-4-Dl -B Penetration at Door 4330 29/719' Blind Flange InstalledX-29-4-D1-A Penetration at Door 4330 29/719' Blind Flange InstalledX-29-4-D1 -B Penetration at Door 404 33/719' Blind Flange InstalledX-29-4-D1 -A Penetration at Door 404 33/719' Blind Flange InstalledSUSQUEHANNA- UNIT 2TS / B 3.6-99Revision 7 PPL Rev. 9SCIVsB 3.6.4.2Table B 3.6.4.2-2Secondary Containment Ventilation SystemPassive Isolation Valves or Devices(Page 2 of 4)Device Number Device Description Area/Elev. Required Position / NotesHD17534C Airlock 1-707 Blind Flange 28/799' Blind Flange InstalledHD27534C Airlock 11-707 Blind Flange 33/799' Blind Flange InstalledXD-1 7513 Isolation damper for Railroad Bay Zone III HVAC 29/799' Position is dependent on RailroadSupply Bay alignmentXD-1 7514 Isolation damper for Railroad Bay Zone III HVAC 29/719' Position is dependent on RailroadExhaust Bay alignmentXD-1 2301 PASS Air Flow Damper 11/729' Closed DamperXD-22301 PASS Air Flow Damper 22/729' Closed Damper161827 HPCI Blowout Steam Vent Drain Valve 25/645' Closed Manual Iso Valve / Note 3161828 RCIC Blowout Steam Vent Drain Valve 281645' Closed Manual Iso Valve / Note 3161829 'A' RHR Blowout Steam Vent Drain Valve 29/645' Closed Manual Iso Valve / Note 3161830 'B' RHR Blowout Steam Vent Drain Valve 28/645' Closed Manual Iso Valve / Note 3261820 RCIC Blowout Steam Vent Drain Valve 33/645' Closed Manual Iso Valve / Note 4261821 'A' RHR Blowout Steam Vent Drain Valve 34/645' Closed Manual Iso Valve / Note 4261822 'B' RHR Blowout Steam Vent Drain Valve 331645' Closed Manual Iso Valve / Note 42LRWI810L Zone III Floor Drain 34-818 Plugged / Note 72LRWI810M Zone III Floor Drain 34-818 Plugged I Note 72LRWI81ON Zone III Floor Drain 34-818 Plugged / Note 72LRWI810R Zone Ill Floor Drain 34-818 Plugged / Note 72LRWI810S Zone III Floor Drain 34-818 Plugged / Note 72LRWI703A Zone II Floor Drain 34-799 Plugged / Note 72LRWI615A Zone II Floor Drain 34-779 Plugged / Note 72LRWI100A Zone II Floor Drain 34-670 Plugged / Note 72LRWI100B Zone II Floor Drain 34-670 Plugged / Note 72LRWI100C Zone II Floor Drain 34-670 Plugged / Note 72LRWI100D Zone II Floor Drain 34-670 Plugged / Note 72LRWI100E Zone II Floor Drain 34-670 Plugged / Note 72LRWI100F Zone II Floor Drain 34-670 Plugged / Note 72LRWI100G Zone II Floor Drain 34-670 Plugged / Note 7SUSQUEHANNA -UNIT 2TS / B 3.6-99aRevision 6 PPL Rev. 9SCIVsB 3.6.4.2Table B 3.6.4.2-2Secondary Containment Ventilation SystemPassive Isolation Valves or Devices(Page 3 of 4)Device Number Device Description Area/Elev. Required Position / Notes1 LRWI81 OU Zone III Floor Drain 29-818 Plugged / Note 71LRWI1810V Zone III Floor Drain 29-818 Plugged / Note 71 LRWI181OW Zone III Floor Drain 29-818 Plugged I Note 71 LRWI81 OX Zone III Floor Drain 29-818 Plugged / Note 71LRWI81OY Zone III Floor Drain 29-818 Plugged / Note 71 LRWI81OZ Zone III Floor Drain 29-818 Plugged / Note 71LRWI81OFF Zone III Floor Drain 29-818 Plugged / Note 71 LRWI81OGG Zone III Floor Drain 29-818 Plugged / Note 71LRWI810HH Zone III Floor Drain 29-818 Plugged / Note 71 LRWI81OJJ Zone III Floor Drain 29-818 Plugged / Note 71 LRWI81OKK Zone III Floor Drain 29-818 Plugged / Note 71 LRW1615A Zone I, Zone III, or No Zone Floor Drain 29-779 Plugged ! Note 71LRWI100A Zone I, Zone II, or No Zone Floor Drain 29-670 Plugged I Note 71LRWI100B Zone I, Zone 11, or No Zone Floor Drain 29-670 Plugged / Note 71LRWII00C Zone I, Zone I1, or No Zone Floor Drain 29-670 Plugged / Note 71LRWI1OOD Zone I, Zone Ill, or No Zone Floor Drain 29-670 Plugged / Note 71LRWI100E Zone I, Zone Ill, or No Zone Floor Drain 29-670 Plugged / Note 71LRWI10OF Zone I, Zone III, or No Zone Floor Drain 29-670 Plugged / Note 71LRWI100G Zone I, Zone III, or No Zone Floor Drain 29-670 Plugged / Note 7SUSQUEHANNA -UNIT 2TS / B 3.6-99bRevision 4 PPL Rev. 9SCIVsB 3.6.4.2Table B 3.6.4.2-2Secondary Containment Ventilation SystemPassive Isolation Valves or Devices(Page 4 of 4)Note 1: The two blind flanges on the SDHR penetrations (blind flanges for device number X-29-2-44 and X-29-2-45) and all the closedmanual valves for the SDHR system (110176,110186,110180,110181,110182,110187, 210186, 210187, 210191, 210192, 210193)can each be considered as a separate secondary containment isolation device for the SDHR penetrations. If one or both of the blindflanges is removed and all the above identified manual valves for the SDHR system are closed, the appropriate LCO should be enteredfor one inoperable SCIV in a penetration flow path with two SCIVs. With the blind flange removed, the manual valves could be openedintermittently under administrative controls per the Technical Specification Note. When both SDHR blind flanges are installed, opening ofthe manual valves for the SDHR system will be controlled to prevent cross connecting ventilation zones. When the manual valves for theSDHR system are open in this condition, the appropriate LCO should be entered for one inoperable SCIV in a penetration flow path withtwo SCIVs. When the SDHR system piping is connected and full of water, the piping forms the secondary containment boundary and theabove listed SCIVs in Table B3.6.4.2-2 are no longer required for this system since the piping forms the barrier.Note 2: Due to the multiple alignments of the RBCW temporary chiller, different devices will perform the SCiV function depending on theRBCW configuration. There are three devices/equipment that can perform the SCIV function for the RBCW temporary chiller supplypenetration. The first SCIV for the RBCW temporary chiller supply penetration is the installed blind flange on penetration X-29-2-47. Thesecond SCIV for the RBCW temporary chiller supply penetration is isolation valve 187389. The third SCIV for the temporary RBCWchiller supply penetration is closed drain valve 187390 and an installed blind flange on penetrations X-29-5-92 and/or X-29-5-96. Sincethere are effectively three SCIVs, any two can be used to define the SCIV for the penetration. Removal of one of the two required SCIVsrequires entry into the appropriate LCO for one inoperable SCIV in a penetration flow path with two SCIVs. Opening of drain valve187390 and operation of blank flanges X-29-5-96 and X-29-5-92 will be controlled to prevent cross connecting ventilation zones. Thesethree SCIVs prevent air inleakage into secondary containment. The isolation of the penetration per the Technical Specificationrequirement is to assure that one of the above SCIVs is closed so that there is no air inleakage into secondary containment.There are three devices/equipment that can perform the SCIV function for the RBCW temporary chiller return penetration. The first SCIVfor the RBCW temporary chiller return penetration is the installed blind flange on penetration X-29-2-46. The second SCIV for theRBCW temporary chiller return penetration is isolation valve 187388. The third SCIV for the temporary RBCW chiller return penetrationis closed drain valve 187391 and an installed blind flange on penetrations X-29-5-91 and/or X-29-5-95. Since there are effectively threeSCIVs, any two can be used to define the SCIV for the penetration. Removal of one of the two required SCIVs requires entry into theappropriate LCO for one inoperable SCIV in a penetration flow path with two SCIVs. Opening of drain valve 187391 and operation ofblank flanges X-29-5-91 and X-29-5-95 will be controlled to prevent cross connecting ventilation zones. These three SCIVs prevent airinleakage into secondary containment. The isolation of the penetration per the Technical Specification requirement is to assure that oneof the above SCIVs is closed so that there is no air inleakage into secondary containment.When the RBCW temporary chiller piping is connected and full of water, the piping inside secondary containment forms the secondarycontainment boundary and the above listed SCIVs in Table B3.6.4.2-2 are no longer required for this system.Note 3: These penetrations connect Secondary Containment Zone I to a No-Zone. When Secondary Containment Zone I is isolatedfrom the recirculation plenum, the above listed SCIVs in Table B3.6.4.2-2 are no longer required.Note 4: These penetrations connect Secondary Containment Zone II to a No-Zone. When Secondary Containment Zone II is isolatedfrom the recirculation plenum, the above listed SCIVs in Table B3.6.4.2-2 are no longer required.Note 5: These penetrations connect the Railroad Bay to a No-Zone. When the Railroad Bay is a No-Zone, the above listed SCIVs inTable B3.6.4.2-2 are no longer required.Note 6: These penetrations connect Secondary Containment Zone I to the Railroad Bay. The above listed SCIVs in Table B3.6.4.2-2 arenot required if the Railroad Bay is a No-Zone and Zone I is isolated from the recirculation plenum OR if the Railroad Bay is aligned toZone I.Note 7: Due to drain header containing multiple floor drains in different ventilation zones, drain plugs were installed in all of the drainheader floor drains. To provide the passive Secondary Containment boundary, only drain plugs in one ventilation zone are required to beinstalled.SUSQUEHANNA -UNIT 2TS / B 3.6-99cRevision 0

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+{{#Wiki_filter:Apr. 26, 2014Page1 of 2MANUAL HARD COPY DISTRIBUTIONDOCUMENT TRANSMITTAL2014-19096USER INFORMATION:GERLACH*ROSEY MEMPL#:028401 CA#: 0363Address: NUCSA2Phone#: 254-3194TRANSMITTAL INFORMATION:TO: GERLACH*ROSEY M 04/26/2014LOCATION: 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.TSB2 -TECHNICAL SPECIFICATIONS BASES UNIT 2 MANUALREMOVE MANUAL TABLE OF CONTENTS DATE: 03/31/2014ADD MANUAL TABLE OF CONTENTS DATE: 04/25/2014CATEGORY: DOCUMENTS TYPE: TSB2co Apr. 26, 2014Page2 of 2ID: TEXT 3.6.4.1ADD: REV: 10REMOVE: REV:9CATEGORY: DOCUMENTSID: TEXT 3.6.4.2ADD: REV: 9REMOVE: REV:8TYPE: TSB2CATEGORY:ID: TEXTREMOVE:DOCUMENTSLOESREV:119TYPE: TSB2ADD: REV: 120CATEGORY:ID : TEXTSREMOVE :DOCUMENTSTOCREV:20TYPE: TSB2ADD: REV: 21ANY 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 ACKNOWLEDGECOMPLETE IN YOUR NIMS INBOX UPON COMPLETION OF UPDATES. FOR ELECTRONIC MANUALUSERS, ELECTRONICALLY REVIEW THE APPROPRIATE DOCUMENTS AND ACKNOWLEDGE COMPLETE INYOUR NIMS INBOX.
+SSES MANUJALManual Name: TSB2Manual Title: TECHNICAL SPECIFICATIONS BASES UNIT 2 MANUALTable Of ContentsIssue Date: 04/25/2014Procedure Name RevTEXT LOES 120Title: LIST OF EFFECTIVE SECTIONSIssue Date04/25/2014Change ID Change NumberTEXT TOCTitle: TABLE OF CONTENTS21 04/25/2014TEXT 2.1.1 4Title: SAFETY LIMITS (SLS) REACTORTEXT 2.1.2 1Title: SAFETY LIMITS (SLS) REACTOR05/06/2009CORE SLS10/04/2007COOLANT SYSTEM (RCS) PRESSURE SLTEXT 3.0 3 08/20/2009Title: LIMITING CONDITION FOR OPERATION (LCO) APPLICABILITYTEXT 3. 1.1Title: REACTIVITYTEXT 3.1.2Title: REACTIVITYTEXT 3.1.3Title: REACTIVITYTEXT 3.1.4Title: REACTIVITYTEXT 3.1.5Title: REACTIVITYTEXT 3.1.6Title: REACTIVITY1 03/24/2005CONTROL SYSTEMS SHUTDOWN MARGIN (SDM)0 11/18/2002CONTROL SYSTEMS REACTIVITY ANOMALIES2 01/19/2009CONTROL SYSTEMS CONTROL ROD OPERABILITY4 01/30/2009CONTROL SYSTEMS CONTROL ROD SCRAM TIMES1CONTROL SYSTEMS07/06/2005CONTROL ROD SCRAM ACCUMULATORS3 02/24/2014CONTROL SYSTEMS ROD PATTERN CONTROLPagel of 8 Report Date: 04/25/14Page 1 of .8Report Date: 04/25/14 SSES MANTA-LManual Name: TSB2Manual Title: TECHNICAL SPECIFICATIONS BASES UNIT 2 MANUALTEXT 3.1.7Title: REACTIVITY CONTROLTEXT 3.1.8Title: REACTIVITY CONTROL3 10/04/2007SYSTEMS STANDBY LIQUID CONTROL3 05/06/2009SYSTEMS SCRAM DISCHARGE VOLUME(SLC) SYSTEM(SDV) VENT AND DRAIN VALVESTEXT 3.2.1 4 05/06/2009Title: POWER DISTRIBUTION LIMITS AVERAGE PLANAR LINEAR HEAT GENERATION RATE (APLHGR)TEXT 3. 2.2Title: POWER DISTRIBUTIONTEXT 3.2.3Title: POWER DISTRIBUTION3 05/06/2009LIMITS MINIMUM CRITICAL POWER RATIO (MCPR)2 05/06/2009LIMITS LINEAR HEAT GENERATION RATE LHGRTEXT 3.3.1.1 5 02/24/2014Title: INSTRUMENTATION REACTOR PROTECTION SYSTEM (RPS) INSTRUMENTATIONTEXT 3.3.1.2 2 01/19/2009Title: INSTRUMENTATION SOURCE RANGE MONITOR (SRM) INSTRUMENTATIONTEXT 3.3.2.1Title: INSTRUMENTATION3 02/24/2014CONTROL ROD BLOCK INSTRUMENTATIONTEXT 3.3.2.2 2 02/22/2012Title: INSTRUMENTATION FEEDWATER -MAIN TURBINE HIGH WATER LEVEL TRIP INSTRUMENTATIONTEXT 3.3.3.1 8 02/28/2013Title: INSTRUMENTATION POST ACCIDENT MONITORING (PAM) INSTRUMENTATIONTEXT 3.3.3.2 1 04/18/2005Title: INSTRUMENTATION REMOTE SHUTDOWN SYSTEMTEXT 3.3.4.1 1 05/06/2009Title: INSTRUMENTATION END OF CYCLE RECIRCULATION PUMP TRIP (EOC-RPT) INSTRUMENTATIONPage 2 of 8Report Date: 04/25/14 SSES MANUJALManual Name: TSB2Manual Title: TECHNICAL SPECIFICATIONS BASES UNIT 2 MANUALTEXT 3.3.4.2 0 11/18/2002Title: INSTRUMENTATION ANTICIPATED TRANSIENT WITHOUT SCRAM RECIRCULATION PUMP TRIP(ATWS-RPT) INSTRUMENTATIONTEXT 3.3.5.1 5 02/24/2014Title: INSTRUMENTATION EMERGENCY CORE COOLING SYSTEM (ECCS) INSTRUMENTATIONTEXT 3.3.5.2 0 11/18/2002Title: INSTRUMENTATION REACTOR CORE ISOLATION COOLING (RCIC) SYSTEM INSTRUMENTATIONTEXT 3.3.6.1 7 03/31/2014Title: INSTRUMENTATION PRIMARY CONTAINMENT ISOLATION INSTRUMENTATIONTEXT 3.3.6.2 4 09/01/2010Title: INSTRUMENTATION SECONDARY CONTAINMENT ISOLATION INSTRUMENTATIONTEXT 3.3.7.1Title: INSTRUMENTATIONINSTRUMENTATION2 10/27/2008CONTROL ROOM EMERGENCY OUTSIDE AIR SUPPLY (CREOAS) SYSTEMTEXT 3.3.8.1 3 12/17/2007Title: INSTRUMENTATION LOSS OF POWER (LOP) INSTRUMENTATIONTEXT 3.3.8.2 0 11/18/2002Title: INSTRUMENTATION REACTOR PROTECTION SYSTEM (RPS) ELECTRIC POWER MONITORINGTEXT 3.4.1 4 07/20/2010Title: REACTOR COOLANT SYSTEM (RCS) RECIRCULATION LOOPS OPERATINGTEXT 3.4.2 3 10/23/2013Title: REACTOR COOLANT SYSTEM (RCS) JET PUMPSTEXT 3.4.3 3 01/13/2012Title: REACTOR COOLANT SYSTEM (RCS) SAFETY/RELIEF VALVES (S/RVS)TEXT 3.4.4 0 11/18/2002Title: REACTOR COOLANT SYSTEM (RCS) RCS OPERATIONAL LEAKAGEPage 3 of 8Report Date: 04/25/14
+.qSE~q MANT.TAI.Manual Name: TSB2Manual Title: TECHNICAL SPECIFICATIONS BASES UNIT 2 MANUALTEXT 3.4.5 3 03/10/2010Title: REACTOR COOLANT SYSTEM (RCS) RCS PRESSURE ISOLATION VALVE (PIV) LEAKAGETEXT 3.4.6 4 02/19/2014Title: REACTOR COOLANT SYSTEM (RCS) RCS LEAKAGE DETECTION INSTRUMENTATIONTEXT 3.4.7 2 10/04/2007Title: REACTOR COOLANT SYSTEM (RCS) RCS SPECIFIC ACTIVITYTEXT 3.4.8Title: REACTOR COOLANT-HOT SHUTDOWNTEXT 3.4.9Title: REACTOR COOLANT-COLD SHUTDOWN2SYSTEM (RCS)1SYSTEM (RCS)03/28/2013RESIDUAL HEAT REMOVAL (RHR) SHUTDOWN COOLING SYSTEM03/28/2013RESIDUAL HEAT REMOVAL (RHR) SHUTDOWN COOLING SYSTEM0TEXT 3.4.10 3 05/06/2009Title: REACTOR COOLANT SYSTEM (RCS) RCS PRESSURE AND TEMPERATURE (P/T) LIMITSTEXT 3.4.11 0 11/18/2002Title: REACTOR COOLANT SYSTEM (RCS) REACTOR STEAM DOME PRESSURETEXT 3.5.13 01/16/2006Title: EMERGENCY CORE COOLING SYSTEMS (ECCS) AND REACTOR CORE ISOLATIONSYSTEM ECCS -OPERATINGTEXT 3.5.2 1 02/24/2014Title: EMERGENCY CORE COOLING SYSTEMS (ECCS) AND REACTOR CORE ISOLATIONSYSTEM ECCS -SHUTDOWNTEXT 3.5.3 3 02/24/2014Title: EMERGENCY CORE COOLING SYSTEMS (ECCS) AND REACTOR CORE ISOLATIONSYSTEM RCIC SYSTEMCOOLING (RCIC)COOLING (RCIC)COOLING (RCIC)TEXT 3.6.1.1Title: PRIMARY CONTAINMENT5 02/24/2014TEXT 3.6.1.2 1 05/06/2009Title: CONTAINMENT SYSTEMS PRIMARY CONTAINMENT AIR LOCKPage4 of 8 Report Date: 04/25/14Page 4 of 8Report Date: 04/25/14 SSES MANUAL.Manual Name: TSB2Manual Title: TECHNICAL SPECIFICATIONS BASES UNIT 2 MANUALTEXT 3.6.1.3Title: CONTAINMENTTEXT 3.6.1.4Title: CONTAINMENTTEXT 3.6.1.5Title: CONTAINMENTTEXT 3.6.1.6Title: CONTAINMENTTEXT 3.6.2.1Title: CONTAINMENTTEXT 3.6.2.2Title: CONTAINMENTTEXT 3.6.2.3Title: CONTAINMENTTEXT 3.6.2.4Title: CONTAINMENTTEXT 3.6.3.1Title: CONTAINMENTTEXT 3.6.3.2Title: CONTAINMENTTEXT 3.6.3.3Title: CONTAINMENTTEXT 3.6.4.1Title: CONTAINMENT13 02/24/2014SYSTEMS PRIMARY CONTAINMENT ISOLATION VALVES (PCIVS)1 05/06/2009SYSTEMS CONTAINMENT PRESSURE1 10/05/2005SYSTEMS DRYWELL AIR TEMPERATURE0 11/18/2002SYSTEMS SUPPRESSION CHAMBER-TO-DRYWELL VACUUM BREAKERS2 12/17/2007SYSTEMS SUPPRESSION POOL AVERAGE TEMPERATURE0 11/18/2002SYSTEMS SUPPRESSION POOL WATER LEVEL1 01/16/2006SYSTEMS RESIDUAL HEAT REMOVAL (RHR) SUPPRESSION POOL COOLING0 11/18/2002SYSTEMS RESIDUAL HEAT REMOVAL (RHR) SUPPRESSION POOL SPRAY2 06/13/2006SYSTEMS PRIMARY CONTAINMENT HYDROGEN RECOMBINERS1 04/18/2005SYSTEMS DRYWELL AIR FLOW SYSTEM1 02/28/2013SYSTEMS PRIMARY CONTAINMENT OXYGEN CONCENTRATION10 04/25/2014SYSTEMS SECONDARY CONTAINMENTPages of 8 Report Date: 04/25/14Page 5 of 8Report Date: 04/25/14 SSES MANUALManual Name: TSB2Manual Title: TECHNICAL SPECIFICATIONS BASES UNIT 2 MANUALTEXT 3.6.4.2 9 04/25/2014Title: CONTAINMENT SYSTEMS SECONDARY CONTAINMENT ISOLATION VALVES (SCIVS)TEXT 3.6.4.3 4 09/21/2006Title: CONTAINMENT SYSTEMS STANDBY GAS TREATMENT (SGT) SYSTEMTEXT 3. 7.1Title: PLANT SYSTEMSULTIMATE HEAT5 04/27/2012RESIDUAL HEAT REMOVAL SERVICE WATER (RHRSW) SYSTEM AND THESINK (UHS)TEXT 3.7.2Title: PLANTTEXT 3.7.3Title: PLANTTEXT 3. 7. 4Title: PLANTTEXT 3.7.5Title: PLANTTEXT 3. 7. 6Title: PLANTTEXT 3.7.7Title: PLANTTEXT 3.7. 8Title: MAINETEXT 3.8. 12 05/02/2008SYSTEMS EMERGENCY SERVICE WATER (ESW) SYSTEM1 01/08/2010SYSTEMS CONTROL ROOM EMERGENCY OUTSIDE AIR SUPPLY (CREOAS) SYSTEM0 11/18/2002SYSTEMS CONTROL ROOM FLOOR COOLING SYSTEM1 10/04/2007SYSTEMS MAIN CONDENSER OFFGAS3 01/25/2011SYSTEMS MAIN TURBINE BYPASS SYSTEM1 10/04/2007SYSTEMS SPENT FUEL STORAGE POOL WATER LEVEL0 05/06/2009TURBINE PRESSURE REGULATION SYSTEM9 02/24/2014Title: ELECTRICAL POWER SYSTEMS AC SOURCES -OPERATINGTEXT 3.8.2 0 11/18/2002Title: ELECTRICAL POWER SYSTEMS AC SOURCES -SHUTDOWNPages of 8 Report Date: 04/25/14Page jk of 8Report Date: 04/25/14 SSES MANUALManual Name: TSB2Manual Title: TECHNICAL SPECIFICATIONS BASES UNIT 2 MANUALTEXT 3.8.3Title: ELECTRICALTEXT 3.8.4Title: ELECTRICALTEXT 3.8.5Title: ELECTRICALTEXT 3.8.6Title: ELECTRICALTEXT 3.8.7Title: ELECTRICALTEXT 3.8.8Title: ELECTRICAL4POWER SYSTEMS10/23/2013DIESEL FUEL OIL LUBE OILAND STARTING AIR3 01/19/2009POWER SYSTEMS DC SOURCES -OPERATING1POWER SYSTEMS1POWER SYSTEMS4POWER SYSTEMS12/14/2006DC SOURCES -SHUTDOWN12/14/2006BATTERY CELL PARAMETERS10/05/2005DISTRIBUTION SYSTEMS -OPERATING0 11/18/2002POWER SYSTEMS DISTRIBUTION SYSTEMS -SHUTDOWNTEXT 3.9.1Title: REFUELINGTEXT 3.9.2Title: REFUELINGTEXT 3.9.3Title: REFUELINGTEXT 3.9.4Title: REFUELINGTEXT 3.9.5Title: REFUELINGOPERATIONSOPERATIONSOPERATIONSOPERATIONSOPERATIONS0 11/18/2002REFUELING EQUIPMENT INTERLOCKS1 09/01/2010REFUEL POSITION ONE-ROD-OUT INTERLOCK0 11/18/2002CONTROL ROD POSITION0 11/18/2002CONTROL ROD POSITION INDICATION0 11/18/2002CONTROL ROD OPERABILITY -REFUELINGTEXT 3.9.61 10/04/2007Title: REFUELING OPERATIONS REACTOR PRESSURE VESSEL (RPV) WATER LEVELPage2 of 8 Report Date: 04/25/14Page 7 of .8Report Date: 04/25/14 SSES MANUALManual Name: TSB2Manual Title: TECHNICAL SPECIFICATIONS BASES UNIT 2 MANUALTEXT 3.9.7 0 11/18/2002Title: REFUELING OPERATIONS RESIDUAL HEAT REMOVAL (RHR) -HIGH WATER LEVELTEXT 3.9.8 0 11/18/2002Title: 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: SPECIALOPERATIONSOPERATIONSOPERATIONSOPERATIONSOPERATIONSOPERATIONSOPERATIONSOPERATIONS1 01/23/2008INSERVICE LEAK AND HYDROSTATIC TESTING OPERATION0 11/18/2002REACTOR MODE SWITCH INTERLOCK TESTING0 11/18/2002SINGLE CONTROL ROD WITHDRAWAL -HOT SHUTDOWN0 11/18/2002SINGLE CONTROL ROD WITHDRAWAL -COLD SHUTDOWN0 11/18/2002SINGLE CONTROL ROD DRIVE (CRD) REMOVAL -REFUELING0 11/18/2002MULTIPLE CONTROL ROD WITHDRAWAL -REFUELING1 03/24/2005CONTROL ROD TESTING -OPERATING2 04/09/2007SHUTDOWN MARGIN (SDM) TEST -REFUELINGPage8 of 8 Report Date: 04/25/14Page 8 of 8Report Date: 04/25/14 TABLE OF CONTENTS (TECHNICAL SPECIFICATIONS BASES)B2.0 SA FETY LIM ITS (SLs) ............................................................................ TS/B2.0-1B2.1.1 Reactor C ore SLs ..................................................................... TS/B2.0-1B2.1.2 Reactor Coolant System (RCS) Pressure SL ........................... TS/B2.0-6B3.0 LIMITING CONDITION FOR OPERATION (LCO) APPLICABILITY ........ TS/B3.0-1B3.0 SURVEILLANCE REQUIREMENT (SR) APPLICABILITY .......... TS/B3.0-10B3.1 REACTIVITY CONTROL SYSTEMS .................................................... B3.1-1B3.1.1 Shutdow n M argin (SDM ) ................................................................ B3.1-1B3.1.2 Reactivity A nom alies ...................................................................... B3.1-8B3.1.3 Control Rod OPERABILITY ...................................................... TS/B3.1-13B3.1.4 Control Rod Scram Times ........................................................ TS/B3.1-22B3.1.5 Control Rod Scram Accumulators ............................................ TS/B3.1-29B3.1.6 Rod Pattern Control .................................................................. TS/B3.1-34B3.1.7 Standby Liquid Control (SLC) System ...................................... TS/B3.1-39B3.1.8 Scram Discharge Volume (SDV) Vent and Drain Valves .......... TS/B3.1-47B3.2 POWER DISTRIBUTION LIMITS ................................................... TS/B3.2-1B3.2.1 Average Planar Linear Heat Generation Rate (APLHGR) ........ TS/B3.2-1B3.2.2 Minimum Critical Power Ratio (MCPR) ..................................... TS/B3.2-5B3.2.3 Linear Heat Generation Rate (LHGR) ....................................... TS/B3.2-10B3.3 INSTRUM ENTATIO N ..................................................................... TS/B 3.3-1B3.3.1.1 Reactor Protection System (RPS) Instrumentation ................... TS/B3.3-1B3.3.1.2 Source Range Monitor (SRM) Instrumentation ......................... TS/B3.3-35B3.3.2.1 Control Rod Block Instrumentation ........................................... TS/B3.3-44B3.3.2.2 Feedwater -Main Turbine High Water Level TripInstrum entation ................................................................... TS/B3 .3-55B3.3.3.1 Post Accident Monitoring (PAM) Instrumentation ..................... TS/B3.3-64B3.3.3.2 Remote Shutdown System ....................................................... TS/B3.3-76B3.3.4.1 End of Cycle Recirculation Pump Trip (EOC-RPT)Instrum entation ................................................................... T S/B 3.3-81B3.3.4.2 Anticipated Transient Without Scram RecirculationPump Trip (ATWS-RPT) Instrumentation .............................. TS/B3.3-92B3.3.5.1 Emergency Core Cooling System (ECCS)Instrum entation ................................................................... TS/B3.3-1 01B3.3.5.2 Reactor Core Isolation Cooling (RCIC) SystemInstrum entation ......................................................................... B 3.3-135B3.3.6.1 Primary Containment Isolation Instrumentation .............................. B3.3-147B3.3.6.2 Secondary Containment Isolation Instrumentation ................... TS/B3.3-180B3.3.7.1 Control Room Emergency Outside Air Supply (CREOAS)System Instrumentation ...................................................... TS/B3.3-192(continued)SUSQUEHANNA -UNIT 2TS / B TOC -1Revision 21 TABLE OF CONTENTS (TECHNICAL SPECIFICATIONS BASES)B3.3 INSTRUMENTATION (continued)B3.3.8.1 Loss of Power (LOP) Instrumentation ....................................... TS/B3.3-206B3.3.8.2 Reactor Protection System (RPS) Electric PowerM onito ring ................................................................................ B 3 .3-2 14B3.4 REACTOR COOLANT SYSTEM (RCS) ......................................... TS/B3.4-1B3.4.1 Recirculation Loops Operating ................................................. TS/B3.4-1B3.4.2 Jet P um ps ................................................................................ T S/B3.4-10B3.4.3 Safety/Relief Valves (S/RVs) ........................................................... B3.4-15B3.4.4 RCS Operational LEAKAGE ..................................................... TS/B3.4-19B3.4.5 RCS Pressure Isolation Valve (PIV) Leakage ........................... TS/B3.4-24B3.4.6 RCS Leakage Detection Instrumentation .................................. TS/B3.4-30B3.4.7 RCS Specific Activity ................................................................ TS/B3.4-35B3.4.8 Residual Heat Removal (RHR) Shutdown CoolingSystem -Hot Shutdown ........................................................... B3.4-39B3.4.9 Residual Heat Removal (RHR) Shutdown CoolingSystem -Cold Shutdown ................................................... TS/B3.4-44B3.4.10 RCS Pressure and Temperature (P/T) Limits ........................... TS/B3.4-49B3.4.11 Reactor Steam Dome Pressure TS/B3.4-58B3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) AND REACTORCORE ISOLATION COOLING (RCIC) SYSTEM ............................ TS/B3.5-1B3.5.1 ECCS -Operating ................................................................... TS/B3.5-1B3.5.2 ECCS -Shutdown ................................................................... TS/B3.5-19B3.5.3 RCIC System ........................................................................... TS/B3.5-25B3.6 CONTAINMENT SYSTEMS ........................................................... TS/B3.6-1B3.6. 1.1 Primary Containment ................................................................ TS/B3.6-1B3.6.1.2 Primary Containment Air Lock ........................................................ B3.6-7B3.6.1.3 Primary Containment Isolation Valves (PCIVs) ......................... TS/B3.6-15B3.6.1.4 Containment Pressure .............................................................. TS/B3.6-40B3.6.1.5 Drywell Air Temperature ........................................................... TS/B3.6-43B3.6.1.6 Suppression Chamber-to-Drywell Vacuum Breakers ................ TS/B3.6-46B3.6.2.1 Suppression Pool Average Temperature .................................. TS/B3.6-52B3.6.2.2 Suppression Pool Water Level ....................................................... B3.6-58B3.6.2.3 Residual Heat Removal (RHR) Suppression PoolC o o ling ...................................................................................... B 3 .6 -6 1B3.6.2.4 Residual Heat Removal (RHR) Suppression Pool Spray ................ B3.6-65B3.6.3.1 N ot U sed ................................................................................. TS/B3.6-69B3.6.3.2 Drywell Air Flow System ................................................................. B3.6-75B3.6.3.3 Primary Containment Oxygen Concentration ............................ TS/B3.6-80B3.6.4.1 Secondary Containment ........................................................... TS/B3.6-83B3.6.4.2 Secondary Containment Isolation Valves (SCIVs) .................... TS/B3.6-90B3.6.4.3 Standby Gas Treatment (SGT) System .................................... TS/B3.6-100(continued)SUSQUEHANNA -UNIT 2TS / B TOC -2Revision 21 TABLE OF CONTENTS (TECHNICAL SPECIFICATIONS BASES)B3.7 PLANT SYSTEMS ......................................................................... TS/B3.7-1B3.7.1 Residual Heat Removal Service Water (RHRSW) Systemand the Ultimate Heat Sink (UHS) ...................................... TS/B3.7-1B3.7.2 Emergency Service Water (ESW) System ................................ TS/B3.7-7B3.7.3 Control Room Emergency Outside Air Supply(CREOAS) System ............................................................. TS/B3.7-12B3.7.4 Control Room Floor Cooling System ........................................ TS/B3.7-19B3.7.5 Main Condenser Offgas ........................................................... TS/B3.7-24B3.7.6 Main Turbine Bypass System ................................................... TS/B3.7-27B3.7.7 Spent Fuel Storage Pool Water Level ...................................... TS/B3.7-31B3.7.8 Main Turbine Pressure Regulation System .............................. TS/B3.7-34B3.8 ELECTRICAL POWER SYSTEM ................................................... TS/B3.8-1B3.8.1 AC Sources -Operating .......................................................... TS/B3.8-1B3.8.2 AC Sources -Shutdown ................................................................ B3.8-39B3.8.3 Diesel Fuel Oil, Lube Oil, and Starting Air ................................ TSIB3.8-47B3.8.4 DC Sources -Operating .......................................................... TS/B3.8-56B3.8.5 DC Sources -Shutdown .......................................................... TS/B3.8-70B3.8.6 Battery Cell Parameters ........................................................... TS/B3.8-77B3.8.7 Distribution Systems -Operating ................................................... B3.8-84B3.8.8 Distribution Systems -Shutdown ................................................... B3.8-94B3.9 REFUELING OPERATIONS .......................................................... TS/B3.9-1B3.9.1 Refueling Equipment Interlocks ................................................ TS/B3.9-1B3.9.2 Refuel Position One-Rod-Out Interlock ..................................... TS/B3.9-5B3.9.3 C ontrol Rod Position ...................................................................... B3.9-9B3.9.4 Control Rod Position Indication ...................................................... B3.9-12B3.9.5 Control Rod OPERABILITY- Refueling ......................................... B3.9-16B3.9.6 Reactor Pressure Vessel (RPV) Water Level ........................... TS/B3.9-19B3.9.7 Residual Heat Removal (RHR) -High Water Level ........................ B3.9-22B3.9.8 Residual Heat Removal (RHR) -Low Water Level ......................... B3.9-26B3.10 SPECIAL OPERATIONS ............................................................... TS/B3.10-1B3.10.1 Inservice Leak and Hydrostatic Testing Operation ................... TS/B3.10-1B3.10.2 Reactor Mode Switch Interlock Testing .......................................... B3.10-6B3.10.3 Single Control Rod Withdrawal -Hot Shutdown ............................. B3.10-11B3.10.4 Single Control Rod Withdrawal -Cold Shutdown ........................... B3.10-16B3.10.5 Single Control Rod Drive (CRD) Removal -Refueling ................... B3.10-21B3.10.6 Multiple Control Rod Withdrawal -Refueling .................................. B3.10-26B3.10.7 Control Rod Testing -Operating .................................................... B3.10-30B3.10.8 SHUTDOWN MARGIN (SDM) Test- Refueling ............................. B3.10-34TSB2 TOC.doc4/17/2014SUSQUEHANNA -UNIT 2 TS / B TOC -3 Revision 21SUSQUEHANNA -UNIT 2TS / B TOC -3Revision 21 SUSQUEHANNA STEAM ELECTRIC STATIONLIST OF EFFECTIVE SECTIONS (TECHNICAL SPECIFICATIONS BASES)Section Title RevisionTOC Table of Contents 21B 2.0 SAFETY LIMITS BASESPage TS / B 2.0-1 1Pages TS / B 2.0-2 and TS / B 2.0-3 4Page TS / B 2.0-4 6Pages TS / B 2.0-5 through TS / B 2.0-8 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 Page 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 3.1-12 0Page TS / B 3.1-13 0Page TS / B 3.1-14 1Page TS / B 3.1-15 0Page TS / B 3.1-16 1Pages TS / B 3.1-17 through TS / 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 TS / B 3.1-30 through TS / B 3.1-33 0Pages TS / B 3.1.34 through TS/ B 3.1-36 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 0Page TS / B 3.1-41 1Page TS / B 3.1-42 2SUSQUEHANNA -UNIT 2 TS/B LOES-1 Revision 120SUSQUEHANNA -UNIT 2TS / B] LOES-1Revision 120 SUSQUEHANNA STEAM ELECTRIC STATIONLIST OF EFFECTIVE SECTIONS (TECHNICAL SPECIFICATIONS BASES)Section Title RevisionPages TS / B 3.1-43 1Page TS / B 3.1-44 0Page TS / B 3.1-45 3Page 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 BASESPages TS / B 3.2-1 and TS / B 3.2-2 2Page TS / B 3.2-3 4Page TS / B 3.2-4 1Page TS / B 3.2-5 3Page TS / B 3.2-6 4Page TS / B 3.2-7 3Pages TS / B 3.2-8 and TS / B 3.2-9 4Pages TS / B 3.2-10 through TS / B 3.2-12 2Page TS / B 3.2-13 1B 3.3 INSTRUMENTATIONPages 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 3.3-8 4Pages TS / B 3.3-9 through TS /B 3.3-13 3Page TS / B 3.3-14 4Pages TS / B 3.3-15 and TS / B 3.3-16 2Pages TS / B 3.3-17 through TS / B 3.3-21 3Pages TS / B 3.3-22 through TS / B 3.3-27 2Page TS / B 3.3-28 3Page TS / B 3.3-29 4Pages TS / B 3.3-30 and TS / B 3.3-31 3Pages TS / B 3.3-32 and TS / B 3.3-33 4Page TS / B 3.3-34 2Pages TS / B 3.3-34a and TS / B 3.3-34b 1Pages TS / B 3.3.34c and TS / B 3.3-34d 0Page TS / B 3.3-34e 1Pages TS / B 3.3-34f through TS / B 3.3-34i 0Pages TS / B 3.3-35 and TS / B 3.3-36 2Pages TS / B 3.3-37 and TS / B 3.3-38 1SUSQUEHANNA -UNIT 2 TS/B LOES-2 Revision 120SUSQUEHANNA -UNIT 2TS / B LOES-2Revision 120 SUSQUEHANNA STEAM ELECTRIC STATIONLIST OF EFFECTIVE SECTIONS (TECHNICAL SPECIFICATIONS BASES)Section Title RevisionPage TS / B 3.3-39 2Pages TS / B 3.3-40 through TS / B 3.3-43 1Pages TS / B 3.3-44 through TS / B 3.3-54 3Pages TS / B 3.3-54a through TS I B 3.3-54d 0Page TS / B 3.3.54e 1Page TS / B 3.3-55 2Page TS / B 3.3-56 0Page 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 5Page 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 2Pages TS I B 3.3-75a through TS / B 3.3-75c 6Pages TS / B 3.3-76 and TS / B 3.3-77 0Page TS / B 3.3-78 1Pages TS / B 3.3-79 through TS / B 3.3-81 0Page TS / B 3.3-82 1Page TS / B 3.3-83 0Pages TS / B 3.3-84 and TS / B 3.3-85 1Page TS / B 3.3-86 0Page TS / B 3.3-87 1Page TS / B 3.3-88 0Page TS / B 3.3-89 1Pages TS / B 3.3-90 and TS / B 3.3-91 0Pages TS / B 3.3-92 through TS / B 3.3-103 1Page TS / B 3.3-104 3Pages TS / B 3.3-105 and TS / B 3.3-106 1Page TS / B 3.3-107 2Page TS / B 3.3-108 1Page TS / B 3.3-109 2Pages TS / B 3.3-110 through TS/ B 3.3-112 1Page TS / B 3.3-113 2SUSQUEHANNA -UNIT 2 TS/B LOES-3 Revision 120SUSQUEHANNA -UNIT 2TS / B LOES-3Revision 120 SUSQUEHANNA STEAM ELECTRIC STATIONLIST OF EFFECTIVE SECTIONS (TECHNICAL SPECIFICATIONS BASES)Section Title RevisionPage TS / B 3.3-114 1Page TS / B 3.3-115 2Page TS / B 3.3-116 3Pages TS / B 3.3-117 and TS / B 3.3-118 2Page TS / B 3.3-119 1Page TS / B 3.3-120 2Pages TS / B 3.3-121 and TS / B 3.3-122 3Page TS / B 3.3-123 1Page TS / B 3.3-124 2Page TS / B 3.3-124a 0Page TS / B 3.3-125 1Page TS / B 3.3-126 2Page TS / B 3.3-127 3Page TS / B 3.3-128 2Pages TS / B 3.3-129 through TS / B 3.3-131 1Page TS / B 3.3-132 2Pages TS / B 3.3-133 and TS / B 3.3-134 1Pages TS / B 3.3-135 through TS / B 3.3-137 0Page TS / B 3.3-138 1Pages TS / B 3.3-139 through TS / B 3.3-146 0Pages B 3.3-147 through 8 3.3-149 0Page TS / B 3.3-150 1Pages TS / B 3.3-151 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 1Pages TS / B 3.3-163 through TS / B 3.3-166 2Pages TS / B 3.3-167 and TS / B 3.3-168 1Pages TS / 8 3.3-169 and TS / B 3.3-170 3Pages TS / B 3.3-171 through TS/ B 3.3-174 1Page TS / B 3.3-174a 1Pages TS/ 83.3-175 through TSIB 3.3-177 1Page TS / 8 3.3-178 2Page TS / 8 3.3-179 3Page TS / B 3.3-179a 2Page TS / B 3.3-180 1Page TS / B 3.3-181 3Page TS / B 3.3-182 1Page TS / 8 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 / 8 3.3-192 0SUSQUEHANNA -UNIT 2 TS/B LOES-4 Revision 120SUSQUEHANNA -UNIT 2TS / B LOES-4Revision 120 SUSQUEHANNA STEAM ELECTRIC STATIONLIST OF EFFECTIVE SECTIONS (TECHNICAL SPECIFICATIONS BASES)Section Title RevisionPage 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 3.3-205 0Page TS / B 3.3-206 1Pages B 3.3-207 through B 3.3-209 0Page TS / B 3.3-210 1Page TS / B 3.3-211 2Pages TS / B 3.3-212 and TS / B 3.3-213 1Pages B 3.3-214 through B 3.3-220 0B 3.4 REACTOR COOLANT SYSTEM BASESPages TS / B 3.4-1 and TS / B 3.4-2 2Pages TS / B 3.4-3 through TS / B 3.4-5 4Pages TS / B 3.4-6 through TS / B 3.4-9 3Page TS / B 3.4-10 1Pages TS / B 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 3.4-23 0Pages TS / B 3.4-24 through TS / B 3.4-27 0Page TS / B 3.4-28 1Page TS / B 3.4-29 3Page 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 / B 3.4-34a 0Pages TS / B 3.4-35 and TS / B 3.4-36 1Page TS / B 3.4-37 2Page 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 3.4.4-46 1Pages TS / B 3.4.4-47 and TS / B 3.4.4-48 0Page TS / B 3.4-49 3Pages TS / B 3.4-50 through TS / B 3.4-52 2Page TS / B 3.4-53 1Pages TS / B 3.4-54 through TS / B 3.4-57 2Pages TS / B 3.4-58 through TS / B 3.4-60 1SUSQUEHANNA -UNIT 2 TSIB LOES-5 Revision 120SUSQUEHANNA -UNIT 2TS / B LOES-5Revision 120 SUSQUEHANNA STEAM ELECTRIC STATIONLIST OF EFFECTIVE SECTIONS (TECHNICAL SPECIFICATIONS BASES)Section Title RevisionB 3.5 ECCS AND RCIC BASESPages TS / B 3.5-1 and TS / B 3.5-2 1Pages TS / B 3.5-3 and TS / B 3.5-4 2Page TS / B 3.5-5 3Page TS / B 3.5-6 2Pages TS / B 3.5-7 through TS / B 3.5-10 1Pages TS / B 3.5-11 and TS / B 3.5-12 2Pages TS / B 3.5-13 and TS / B 3.5-14 1Pages TS / B 3.5-15 and TS / B.3.5-16 2Page TS / B 3.5-17 3Pages TS / B 3.5-18 through TS / B 3.5-23 1Page B 3.5-24 0Page TS / B 3.5-25 1Pages TS / B 3.5-26 and TS / B 3.5-27 2Page TS / B 3.5-28 0Page TS / B 3.5-29 through TS / B 3.5-31 1B 3.6 CONTAINMENT SYSTEMS BASESPage TS / B 3.6-1 2Page TS / B 3.6-1a 4Page TS / B 3.6-2 4Page TS / 8 3.6-3 3Page TS / B 3.6-4 4Page TS / B 3.6-5 3Page TS / B 3.6-6 4Page TS / 8 3.6-6a 4Page TS / B 3.6-6b 3Page TS / B 3.6-6c 0Page 8 3.6-7 0Page TS / 3.6-8 1Pages B 3.6-9 through 8 3.6-14 0Page TS / 8 3.6-15 4Page TS / 8 3.6-15a 0Page TS / B 3.6-15b 3Pages TS / 8 3.6-16 and TS / 8 3.6-17 3Page TS / B 3.6-17a 1Pages TS / 8 3.6-18 and TS / B 3.6-19 1Page TS / B 3.6-20 2Page TS / 8 3.6-21 3SUSQUEHANNA -UNIT 2 TS/BLOES-6 Revision 120SUSQUEHANNA -UNIT 2TS / B LOES-6Revision 120 SUSQUEHANNA STEAM ELECTRIC STATIONLIST OF EFFECTIVE SECTIONS (TECHNICAL SPECIFICATIONS BASES)Section Title RevisionPages TS / B 3.6-21a and TS / B 3.6-21 b 0Pages TS / B 3.6-22 and TS / B 3.6-23 2Pages TS / B 3.6-24 and TS / B 3.6-25 1Pages TS / B 3.6-26 and TS / B 3.6-27 3Page TS / B 3.6-28 7Page TS / B 3.6-29 5Page TS / B 3.6-29a 0Page TS / B 3.6-30 2Page TS / B 3.6-31 3Pages TS / B 3.6-32 and TS / B 3.6-33 2Page TS / B 3.6-34 1Pages TS / B 3.6-35 and TS / B 3.6-36 3Page TS / B 3.6-37 2Page TS / B 3.6-38 3Page TS / B 3.6-39 7Page TS / B 3.6-39a 0Page TS / B 3.6-40 1Pages B 3.6-41 and B 3.6-42 0Pages TS / B 3.6-43 and TS / B 3.6-44 1Page TS / B 3.6-45 2Pages TS / B 3.6-46 through TS / B 3.6-50 1Page TS / B 3.6-51 2Pages TS / B 3.6-52 through TS / B 3.6-55 0Pages TS / B 3.6-56 and TS / B 3.6-57 2Pages B 3.6-58 through B 3.6-62 0Pages TS / B 3.6-63 and TS / B 3.6-64 1Pages B 3.6-65 through B 3.6-68 0Pages TS / B 3.6-69 through TS / B 3.6-71 1Page TS / B 3.6-72 2Pages TS / B 3.6-73 and TS / B 3.6-74 1Pages B 3.6-75 and B 3.6-76 0Page TS / B 3.6-77 1Pages B 3.6-78 and B 3.6-79 0Page TS / B 3.6-80 1Pages TS / B 3.6-81 and TS / B 3.6-82 0Page TS / B 3.6-83 4Page TS / B 3.6-84 2Page TS / B 3.6-85 4Pages TS / B 3.6-86 and TS / B 3.6-87 2Page TS / B 3.6-87a 2Page TS / B 3.6-88 6Page TS / B 3.6-89 3Page TS / B 3.6-89a 0SUSQUEHANNA- UNIT 2 TS/B LOES-7 Revision 120SUSQUEHANNA -UNIT 2TS / B LOES-7Revision 120 SUSQUEHANNA STEAM ELECTRIC STATIONLIST OF EFFECTIVE SECTIONS (TECHNICAL SPECIFICATIONS BASES)Section Title RevisionPages TS / B 3.6-90 and TS / B 3.6-91 3Page TS / B 3.6-92 2Pages TS / B 3.6-93 through TS / B 3.6-95 1Page TS / B 3.6-96 2Page TS / B 3.6-97 1Page TS / B 3.6-98 2Page TS / B 3.6-99 7Page TS / B 3.6-99a 6Page TS / B 3.6-99b 4Page TS / B 3.6-99c 0Pages TS / B 3.6-100 and TS / B 3.6-101 1Pages TS / B 3.6-102 and TS / B 3.6-103 2Page TS / B 3.6-104 3Page TS / B 3.6-105 2Page TS / B 3.6-106 3B 3.7 PLANT SYSTEMS BASESPage 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 2Page TS / B 3.7-6 4Page TS / B 3.7-6a 3Page TS / B 3.7-6b 2Page TS / B 3.7-6c 3Page TS / B 3.7-7 3Page TS / B 3.7-8 2Pages B 3.7-9 through B 3.7-11 0Pages 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 3.7-24 1Pages TS / B 3.7-25 and TS / B 3.7-26 0Page TS / B 3.7-27 4Pages TS / B 3.7-28 and TS / B 3.7-29 3Pages TS / B 3.7-30 and 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 0SUSQUEHANNA -UNIT 2 TS/B LOES-8 Revision 120SUSQUEHANNA -UNIT 2TS / B LOES-8Revision 120 SUSQUEHANNA STEAM ELECTRIC STATIONLIST OF EFFECTIVE SECTIONS (TECHNICAL SPECIFICATIONS BASES)Section Title RevisionB 3.8 ELECTRICAL POWER SYSTEMS BASESPage TS / B 3.8-1 1Pages B 3.8-2 and B 3.8-3 0Page TS / B 3.8-4 1Pages TS / B 3.8-4a and TS / B 3.8-4b 0Pages TS / B 3.8-5 and TS / B 3.8-6 3Page TS / B 3.8-6a 1Pages B 3.8-7 and B 3.8-8 0Page TS / B 3.8-9 2Pages TS / B 3.8-10 and TS / B 3.8-11 1Pages B 3.8-12 through B 3.8-18 0Page TS / B 3.8-19 1Pages B 3.8-20 through B 3.8-22 0Page TS / B 3.8-23 1Page B 3.8-24 0Pages TS / B 3.8-25 and TS / B 3.8-26 1Pages B 3.8-27 through B 3.8-30 0Page TS / B 3.8-31 1Pages TS / B 3.8-32 through TS / B 3.8-35 0Page TS / B 3.8-36 1Page TS / B 3.8-37 0Page TS / B 3.8-38 1Pages B 3.8-39 through B 3.8-46 0Page TS / B 3.8-47 3Pages TS / B 3.8-48 through TS / B 3.8-50 0Pages TS / B 3.8-51 and TS / B 3.8-52 3Page TS / B 3.8-53 1Page TS / B 3.8-54 0Page TS / B 3.8-55 1Pages TS / B 3.8-56 through TS / B 3.8-59 2Pages TS / B 3.8-60 through TS / B 3.8-64 3Page TS / B 3.8-65 4Page TS / B 3.8-66 5Pages TS / B 3.8-67 and TS / B 3.8-68 4Page TS / B 3.8-69 5Pages TS / B 3.8-70 through TS / B 3.8-83 1Pages TS / B 3.8-83A through TS / B 3.8-83D 0Pages B 3.8-84 through B 3.8-85 0Page TS / B 3.8-86 1Page TS / B 3.8-87 2Pages TS / B 3.8-88 and TS / B 3.8-89 1Page TS / B 3.8-90 2Pages TS / B 3.8-91 through TS / B 3.8-93 1Pages B 3.8-94 through B 3.8-99 0SUSQUEHANNA -UNIT 2 TS/BLOES-9 Revision 120SUSQUEHANNA -UNIT 2TS / B LOES-9Revision 120 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 3.9-2 1Page TS / B 3.9-2a 1Pages TS!/ B 3.9-3 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 3.10-32 0Page TS / B 3.10-33 2Page B 3.10-34 0Page TS / B 3.10-35 1Pages B 3.10-36 and B 3.10-37 0Page TS / B 3.10-38 1Page TS / B 3.10-39 2TSB2 Text LOES.doc 4/1512014SUSQUEHANNA -UNIT 2 TS / B LOES-lO Revision 120SUSQUEHANNA -UNIT 2TS / B LOES-1 0Revision 120 PPL Rev. 10Secondary ContainmentB 3.6.4.1B 3.6 CONTAINMENT SYSTEMSB 3.6.4.1 Secondary ContainmentBASESBACKGROUNDThe 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 secondarycontainment 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 structure 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 III, each of which must beOPERABLE depending on plant status and the alignment of thesecondary containment boundary. Specifically, the Unit 1 secondarycontainment boundary can be modified to exclude Zone I1. Similarly, theUnit 2 secondary containment boundary can be modified to exclude ZoneI. Secondary containment may consist of only Zone III when in MODE 4 or5 during CORE ALTERATIONS, or during handling of irradiated fuel withinthe Zone III secondary containment boundary.(continued)SUSQUEHANNA -UNIT 2TS / B 3.6-83Revision 4 PPL Rev. 10Secondary ContainmentB 3.6.4.1BASESBACKGROUND(continued)To prevent ground level exfiltration while allowing the secondarycontainment to be designed as a conventional structure, the secondarycontainment 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, "SecondaryContainment 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).APPLICABLESAFETYANALYSESThere are two principal accidents for which credit is taken for secondarycontainment 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 those leakage paths and associatedleakage 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 componentslocated 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 containmentboundary 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).SUSQUEHANNA -UNIT 2TS / B 3.6-84Revision 2 PPL Rev. 10Secondary ContainmentB 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 hours. The 4 hour 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 (requiringsecondary containment OPERABILITY) occurring during periods wheresecondary containment is inoperable is minimal.A temporary (one-time) Completion Time is connected to the CompletionTime Requirements above (4 hours) with an "OR" connector. TheTemporary Completion Time is 48 hours and applies to the replacement ofthe Reactor Building Recirculating Fan Damper Motors. The TemporaryCompletion Time of 48 hours 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 hours 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)SUSQUEHANNA -UNIT 2TS / B 3.6-85Revision 4 PPL Rev. 10Secondary ContainmentB 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 containmentis 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 3.6.4.1.1REQUIREMENTSThis SR ensures that the secondary containment boundary is sufficientlyleak tight to preclude exfiltration under expected wind conditions.Expected wind conditions are defined as sustained wind speeds of lessthan or equal to 16 mph at the 60m meteorological tower or less than orequal to 11 mph at the 1 Om meteorological tower if the 60m tower windspeed is not available. Changes in indicated reactor building differentialpressure observed during periods of short-term wind speed gusts abovethese sustained speeds do not by themselves impact secondarycontainment integrity. However, if secondary containment integrity isknown to be compromised, the LCO must be entered regardless of windspeed.(continued)SUSQUEHANNA -UNIT 2TS / B 3.6-86Revision 2 PPL Rev. 10Secondary ContainmentB 3.6.4.1BASESSURVEILLANCE SR 3.6.4.1.1 (continued)REQUIREMENTSThe 24 hour Frequency of this SR was developed based on operatingexperience related to secondary containment vacuum variations during theapplicable MODES and the low probability of a DBA occurring betweensurveillances.Furthermore, the 24 hour 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 3.6.4.1.3Verifying 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 mayhave multiple inner or multiple outer doors. The intent is to maintain thesecondary containment barrier intact, which is achieved by maintainingthe 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)SUSQUEHANNA -UNIT 2TS / B 3.6-87Revision 2 PPL Rev. 10Secondary ContainmentB 3.6.4.1BASESSURVEILLANCEREQUIREMENTSSR 3.6.4.1.2 and SR 3.6.4.1.3 (continued)When an access opening between secondary containment zones is beingused for exit and entry, then at least one door (where two doors areprovided) must remain closed. The access openings between secondarycontainment zones which are not provided with two doors areadministratively controlled to maintain secondary containment integrityduring exit and entry. This Surveillance is modified by a Note that allowsaccess openings with a single door (i.e., no airlock) within the secondarycontainment boundary (i.e., between required secondary containmentzones) to be opened for entry and exit. Opening of an access door forentry and exit allows sufficient administrative control by individualpersonnel making the entries and exits to assure the secondarycontainment 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)SUSQUEHANNA -UNIT 2TS / B 3.6-87aRevision 2 PPL Rev. 10Secondary ContainmentB 3.6.4.1BASESSURVEILLANCEREQUIREMENTS(continued)SR 3.6.4.1.4 and SR 3.6.4.1.5The 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 containmentthat is less than the pressure external to the secondary containmentboundary. This is confirmed by demonstrating that one SGT subsystemwill 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 hour at less than orequal to the maximum flow rate permitted for the secondary containmentconfiguration that is operable. The 1 hour test period allows secondarycontainment 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 3.6.4.1.5TEST CONFIGURATION ACCEPTANCE CRITERIA) ACCEPTANCE CRITERIA)Group 1Zones I, II and III (Unit 1 _ 300 Seconds _ 5400 CFMRailroad Bay aligned to (Zones 1, 11, and Ill) (From Zones 1, 11, and Ill)Secondary Containment).Zones II and III (Unit 1 _ 300 Seconds < 4000 CFMRailroad Bay aligned to (Zones II and Ill) (From Zones II and Ill)Zone Ill).Group 2Zones 1, 11 and III (Unit 1 < 300 Seconds < 5300 CFMRailroad Bay not aligned (Zones 1, 11, and Ill) (From Zones 1, 11, and Ill)to SecondaryContainment).Zones II and III (Unit 1 < 300 Seconds < 3900 CFMRailroad Bay not aligned (Zones II and Ill) (From Zones II and III)to SecondaryContainment).Only one of the above listed configurations needs to be tested to confirm secondarycontainment OPERABILITY.(continued)SUSQUEHANNA -UNIT 2TS / B 3.6-88Revision 6 PPL Rev. 10Secondary ContainmentB 3.6.4.1BASESSURVEILLANCE SR 3.6.4.1.4 and SR 3.6.4.1.5 (continued)REQUIREMENTSA 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 configurationis tested every 60 months. The 60 month Frequency is acceptablebecause operating experience has shown that these components usuallypass the Surveillance and all active components are tested morefrequently. Therefore, these tests are used to ensure secondarycontainment 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 performedwith the Unit 1 Railroad Bay aligned in the most limiting configuration.More specifically, secondary containment drawdown testing will beperformed with the Unit 1 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.Note that aligning the Railroad Bay to either Zone I or III is acceptablesince either zone is part of secondary containment when 3 zone testing isperformed. When a Zone II & III test is performed with the Unit 1 RailroadBay aligned to Secondary Containment, it must be aligned to Zone IIIsince aligning to Zone I will not allow communication with the isolatedzones. The most limiting Unit 1 Railroad Bay alignment shall beestablished each Surveillance period (60 month). Subsequent drawdowntesting during the same Surveillance period only requires testing of theUnit 1 Railroad Bay in the most limiting configuration. For example, Zone1, 11, and III Surveillance testing is performed with the Unit 1 Railroad Bayaligned both as a No Zone with the Railroad Bay door open and as ZoneI1l. If the Surveillance testing determined the most limiting configurationoccurs with the Unit 1 Railroad Bay aligned as Zone III, then subsequentZone II and III drawdown testing during the same Surveillance period onlyneeds to be performed with the Unit 1 Railroad Bay aligned as Zone Il1.(continued)SUSQUEHANNA -UNIT 2TS / B 3.6-89Revision 3 PPL Rev. 10Secondary ContainmentB 3.6.4.1BASESSURVEILLANCEREQUIREMENTSSR 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).(continued)SUSQUEHANNA -UNIT 2TS / B 3.6-89aRevision 0 PPL Rev. 9SCIVsB 3.6.4.2B 3.6 CONTAINMENT SYSTEMSB 3.6.4.2 Secondary Containment Isolation Valves (SCIVs)BASESBACKGROUNDThe function of the SCIVs, in combination with other accident mitigationsystems, is to limit fission product release during and following postulatedDesign Basis Accidents (DBAs) (Ref. 1). Secondary containment isolationwithin the time limits specified for those isolation valves designed to closeautomatically ensures that fission products that leak from primarycontainment into secondary containment following a DBA, or that arereleased during certain operations when primary containment is not requiredto be OPERABLE or take place outside primary containment, aremaintained within the secondary containment boundary.The OPERABILITY requirements for SCIVs help ensure that an adequatesecondary containment boundary is maintained during and after an accidentby minimizing potential paths to the environment. These isolation devicesconsist of either passive devices or active (automatic) devices. Manualvalves or dampers, de-activated automatic valves or dampers secured intheir closed position (including check valves with flow through the valvesecured), and blind flanges are considered passive devices.Automatic SCIVs close on a secondary containment isolation signal toestablish a boundary for untreated radioactive material within secondarycontainment following a DBA or other accidents.Other non-sealed penetrations which cross a secondary containmentboundary are isolated by the use of valves in the closed position or blindflanges.APPLICABLESAFETYANALYSESThe SCIVs must be OPERABLE to ensure the secondary containmentbarrier to fission product releases is established. The principal accidents forwhich the secondary containment boundary is required are a loss of coolantaccident (Ref. 1) and a fuel handling accident inside secondary containment(Ref. 2). The secondary containment performs no active function inresponse to either of these limiting events, but the boundary(continued)SUSQUEHANNA -UNIT 2TS / B 3.6-90Revision 3 PPL Rev. 9SCIVsB 3.6.4.2BASESAPPLICABLE established by SCIVs is required to ensure that leakage from the primarySAFETY containment is processed by the Standby Gas Treatment (SGT) SystemANALYSES before being released to the environment.(continued)Maintaining SCIVs OPERABLE with isolation times within limits ensures thatfission products will remain trapped inside secondary containment so thatthey can be treated by the SGT System prior to discharge to theenvironment.SCIVs satisfy Criterion 3 of the NRC Policy Statement (Ref. 3).LCO SCIVs that form a part of the secondary containment boundary are requiredto be OPERABLE. Depending on the configuration of the secondarycontainment only specific SCIVs are required. The SCIV safety function isrelated to control of offsite radiation releases resulting from DBAs.The automatic isolation valves are considered OPERABLE when theirisolation times are within limits and the valves actuate on an automaticisolation signal. The valves covered by this LCO, along with theirassociated stroke times, are listed in Table B 3.6.4.2-1.The normally closed isolation valves or blind flanges are consideredOPERABLE when manual valves are closed or open in accordance withappropriate administrative controls, automatic SCIVs are deactivated andsecured in their closed position, or blind flanges are in place. These passiveisolation valves or devices are listed in Table B3.6.4.2-2. Penetrationsclosed with sealants are considered part of the secondary containmentboundary and are not considered penetration flow paths.Certain plant piping systems (e.g., Service Water, RHR Service Water,Emergency Service Water, Feedwater, etc.) penetrate the secondarycontainment boundary. The intact piping within secondary containmentprovides a passive barrier which maintains secondary containmentrequirements. When the SDHR and temporary chiller system piping isconnected and full of water, the piping forms the secondary containmentboundary and the passive devices in TS Bases Table B3.6.4.2-2 are nolonger required for these systems since the piping forms the barrier. Duringcertain plant evolutions, piping systems may be drained and breachedwithin secondary containment. During the pipe breach, system isolationvalves can be used to provide secondary containment isolation. Theisolation valve alignment will be controlled when the piping system isbreached.(continued)SUSQUEHANNA -UNIT 2TS / B 3.6-91Revision 3 PPL Rev. 9SClVsB 3.6.4.2BASES (continued)APPLICABILITY In MODES 1,2, and 3, a DBA could lead to a fission product release to theprimary containment that leaks to the secondary containment. Therefore,the OPERABILITY of SCIVs is required.In MODES 4 and 5, the probability and consequences of these events arereduced due to pressure and temperature limitations in these MODES.Therefore, maintaining SCIVs OPERABLE is not required in MODE 4 or 5,except for other situations under which significant radioactive releases canbe postulated, 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.Moving irradiated fuel assemblies in the secondary containment may alsooccur in MODES 1, 2, and 3.ACTIONS The ACTIONS are modified by three Notes. The first Note allowspenetration flow paths to be unisolated intermittently under administrativecontrols. These controls consist of stationing a dedicated operator, who isin continuous communication with the control room, at the controls of theisolation device. In this way, the penetration can be rapidly isolated when aneed for secondary containment isolation is indicated.The second Note provides clarification that for the purpose of this LCOseparate Condition entry is allowed for each penetration flow path. This isacceptable, since the Required Actions for each Condition provideappropriate compensatory actions for each inoperable SCIV. Complyingwith the Required Actions may allow for continued operation, andsubsequent inoperable SCIVs are governed by subsequent Condition entryand application of associated Required Actions.The third Note ensures appropriate remedial actions are taken, if necessary,if the affected system(s) are rendered inoperable by an inoperable SCIV.A.1 and A.2In the event that there are one or more required penetration flow paths withone required SCIV inoperable, the affected penetration flow path(s) must beisolated. The method of isolation must include the use of at least oneisolation barder that cannot be adversely affected by a single active failure.Isolation barriers that meet this criterion are a closed and de-activatedautomatic SCIV, a closed manual valve, and a blind flange. Forpenetrations isolated in(continued)SUSQUEHANNA -UNIT 2TS / B 3.6-92Revision 2 PPL Rev. 9SCIVsB 3.6.4.2BASESACTIONS A.1 and A.2 (continued)accordance with Required Action A. 1, the device used to isolate thepenetration should be the closest available device to secondarycontainment. The Required Action must be completed within the 8 hourCompletion Time. The specified time period is reasonable considering thetime required to isolate the penetration, and the probability of a DBA, whichrequires the SCIVs to close, occurring during this short time is very low.For affected penetrations that have been isolated in accordance withRequired Action A. 1, the affected penetration must be verified to be isolatedon a periodic basis. This is necessary to ensure that secondarycontainment penetrations required to be isolated following an accident, butno longer capable of being automatically isolated, will be in the isolationposition should an event occur. The Completion Time of once per 31 daysis appropriate because the valves are operated under administrativecontrols and the probability of their misalignment is low. This RequiredAction does not require any testing or device manipulation. Rather, itinvolves verification that the affected penetration remains isolated.Condition A is modified by a Note indicating that this Condition is onlyapplicable to those penetration flow paths with two SCIVs. For penetrationflow paths with one SCIV, Condition C provides the appropriate RequiredActions.Required Action A.2 is modified by a Note that applies to devices located inhigh radiation areas and allows them to be verified closed by use ofadministrative controls. Allowing verification by administrative controls isconsidered acceptable, since access to these areas is typically restricted.Therefore, the probability of misalignment, once they have been verified tobe in the proper position, is low.B. IWith two SCIVs in one or more penetration flow paths inoperable, theaffected penetration flow path must be isolated within 4 hours. The methodof isolation must(continued)SUSQUEHANNA -UNIT 2TS / B 3.6-93Revision 1 PPL Rev. 9SCIVsB 3.6.4.2BASESACTIONS B.1 (continued)include the use of at least one isolation barrier that cannot be adverselyaffected by a single active failure. Isolation barriers that meet this criterionare a closed and de-activated automatic valve, a closed manual valve, anda blind flange. The 4 hour Completion Time is reasonable considering thetime required to isolate the penetration and the probability of a DBA, whichrequires the SCIVs to close, occurring during this short time, is very low.The Condition has been modified by a Note stating that Condition B is onlyapplicable to penetration flow paths with two isolation valves. Forpenetration flow paths with one SCIV, Condition C provides the appropriateRequired Actions.C.1 and C.2With one or more required penetration flow paths with one required SCIVinoperable, the inoperable valve must be restored to OPERABLE status orthe affected penetration flow path must be isolated. The method of isolationmust include the use of at least one isolation barrier that cannot beadversely affected by a single active failure. Isolation barriers that meet thiscriterion are a closed and de-activated automatic valve, a closed manualvalve, and a blind flange. A check valve may not be used to isolate theaffected penetration. Required Action C.1 must be completed within the4 hour Completion Time. The Completion Time of 4 hours is reasonableconsidering the relative stability of the system (hence, reliability) to act as apenetration isolation boundary and the relative importance of supportingsecondary containment OPERABILITY during MODES 1, 2, and 3.In the event the affected penetration flow path is isolated in accordance withRequired Action C.1, the affected penetration must be verified to be isolatedon a periodic basis. This is necessary to ensure that secondarycontainment penetrations required to be isolated following an accident areisolated.The Completion Time of once per 31 days for verifying each affectedpenetration is isolated is appropriate because the(continued)SUSQUEHANNA -UNIT 2TS / B 3.6-94Revision 1 PPL Rev. 9SCIVsB 3.6.4.2BASESACTIONS C.1 and C.2 (continued)valves are operated under administrative controls and the probability of theirmisalignment is low.Condition C is modified by a Note indicating that this Condition is onlyapplicable to penetration flow paths with only one SCIV. For penetrationflow paths with two SCIVs, Conditions A and B provide the appropriateRequired Actions.Required Action C.2 is modified by a Note that applies to valves and blindflanges located in high radiation areas and allows them to be verified by useof administrative means. Allowing verification by administrative means isconsidered acceptable, since access to these areas is typically restricted.Therefore, the probability of misalignment of these valves, once they havebeen verified to be in the proper position, is low.D.1 and D.2If any Required Action and associated Completion Time cannot be met, theplant must be brought to a MODE in which the LCO does not apply. Toachieve this status, the plant must be brought to at least MODE 3 within12 hours and to MODE 4 within 36 hours. The allowed Completion Timesare reasonable, based on operating experience, to reach the required plantconditions from full power conditions in an orderly manner and withoutchallenging plant systems.E.1, E.2, and E.3If any Required Action and associated Completion Time are not met, theplant must be placed in a condition in which the LCO does not apply. Ifapplicable, CORE ALTERATIONS and the movement of irradiated fuelassemblies in the secondary containment must be immediately suspended.Suspension of these activities shall not preclude completion of movement ofa component to a safe position. Also, if applicable, actions must beimmediately initiated to suspend OPDRVs in order to minimize theprobability of a vessel draindown and the subsequent potential for fissionproduct release. Actions must continue until OPDRVs are suspended.(continued)SUSQUEHANNA -UNIT 2TS / B 3.6-95Revision 1 PPL Rev. 9SCIVsB 3.6.4.2BASESACTIONS E.1, E.2, and E.3 (continued)Required Action E.A has been modified by a Note stating that LCO 3.0.3is not applicable. If moving irradiated fuel assemblies while in MODE 4or 5, LCO 3.0.3 would not specify any action. If moving fuel while inMODE 1, 2, or 3, the fuel movement is independent of reactor operations.Therefore, in either case, inability to suspend movement of irradiated fuelassemblies would not be a sufficient reason to require a reactorshutdown.SURVEILLANCEREQUIREMENTSSR 3.6.4.2.1This SR verifies that each secondary containment manual isolation valveand blind flange that is required to be closed during accident conditions isclosed. The SR helps to ensure that post accident leakage of radioactivefluids or gases outside of the secondary containment boundary is withindesign limits. This SR does not require any testing or valve manipulation.Rather, it involves verification (typically visual) that those required SCIVsin secondary containment that are capable of being mispositioned are inthe correct position.Since these SCIVs are readily accessible to personnel during normaloperation and verification of their position is relatively easy, the 31 dayFrequency was chosen to provide added assurance that the SCIVs are inthe correct positions.Two Notes have been added to this SR. The first Note applies to valvesand blind flanges located in high radiation areas and allows them to beverified by use of administrative controls. Allowing verification byadministrative controls is considered acceptable, since access to theseareas is typically restricted during MODES 1, 2, and 3 for ALARAreasons. Therefore, the probability of misalignment of these SCIVs, oncethey have been verified to be in the proper position, is low.A second Note has been included to clarify that SCIVs that are openunder administrative controls are not required to meet the SR during thetime the SCIVs are open.(continued)ISUSQUEHANNA -UNIT 2TS / B 3.6-96Revision 2 PPL Rev. 9SCIVsB 3.6.4.2BASESSURVEILLANCEREQUIREMENTS(continued)SR 3.6.4.2.2SCIVs with maximum isolation times specified in Table B 3.6.2.4-1 aretested every 92 days to verify that the isolation time is within limits todemonstrate OPERABILITY. Automatic SCIVs without maximum isolationtimes specified in Table B 3.6.4.2-1 are tested under the requirements ofSR 3.6.4.2.3. The isolation time test ensures that the SCIV will isolate ina time period less than or equal to that assumed in the safety analyses.SR 3.6.4.2.3Verifying that each automatic required SCIV closes on a secondarycontainment isolation signal is required to prevent leakage of radioactivematerial from secondary containment following a DBA or other accidents.This SR ensures that each automatic SCIV will actuate to the isolationposition on a secondary containment isolation signal. The LOGICSYSTEM FUNCTIONAL TEST in SR 3.3.6.2.5 overlaps this SR to providecomplete testing of the safety function. The 24 month Frequency isbased on the need to perform this Surveillance under the conditions thatapply during a plant outage and the potential for an unplanned transient ifthe Surveillance were performed with the reactor at power. Operatingexperience has shown these components usually pass the Surveillancewhen performed at the 24 month Frequency. Therefore, the Frequencywas concluded to be acceptable from a reliability standpoint.REFERENCES 1. FSAR, Section 6.2.2. FSAR, Section 15.3. Final Policy Statement on Technical Specifications Improvements,July 22, 1993 (58 FR 39132).SUSQUEHANNA -UNIT 2TS / B 3.6-97Revision 1 PPL Rev. 9SCIVsB 3.6.4.2Table B 3.6.4.2-1Secondary Containment Ventilation SystemAutomatic Isolation Dampers(Page 1 of 1)Reactor MaximumBuilding Valve Number Valve Description Type of Valve IsolationBlne i TimeZone I(Seconds)I HD-17586 A&B Supply System Dampers Automatic Isolation Damper 10.0I HD-1 7524 A&B Filtered Exhaust System Dampers Automatic Isolation Damper 10.0I HD-17576A&B Unfiltered Exhaust System Automatic Isolation Damper 10.0II HD-27586 A&B Supply System Dampers Automatic Isolation Damper 10.0II HD-27524 A&B Filtered Exhaust System Dampers Automatic Isolation Damper 10.0II HD-27576 A&B Unfiltered Exhaust System Automatic Isolation Damper 10.0Ill HD-17564 A&B Supply System Dampers Automatic Isolation Damper 14.0Ill HD-17514A&B Filtered Exhaust System Dampers Automatic Isolation Damper 6.5III HD-1 7502 A&B Unfiltered Exhaust System Automatic Isolation Damper 6.0Ill HD-27564 A&B Supply System Dampers Automatic Isolation Damper 14.0III HD-27514 A&B Filtered Exhaust System Dampers Automatic Isolation Damper 6.5Ill HD-27502 A&B Unfiltered Exhaust System Automatic Isolation Damper 6.0N/A HD-17534A Zone 3 Airlock 1-606 Automatic Isolation Damper N/AN/A HD-17534B Zone 3 Airlock 1-611 Automatic Isolation Damper N/AN/A HD-17534D Zone 3 Airlock 1-803 Automatic Isolation Damper N/AN/A HD-17534E Zone 3 Airlock 1-805 Automatic Isolation Damper N/AN/A HD-17534F Zone 3 Airlock 1-617 Automatic Isolation Damper N/AN/A HD-17534H Zone 3 Airlock 1-618 Automatic Isolation Damper N/AN/A HD-27534A Zone 3 Airlock 11-606 Automatic Isolation Damper N/AN/A HD-27534D Zone 3 Airlock 11-803 Automatic Isolation Damper N/AN/A HD-27534E Zone 3 Airlock 11-805 Automatic Isolation Damper N/AN/A HD-27534G Zone 3 Airlock C-806 Automatic Isolation Damper N/AN/A HD-27534H Zone 3 Airlock 11-618 Automatic Isolation Damper N/AN/A HD-275341 Zone 3 Airlock 11-609 Automatic Isolation Damper N/ASUSQUEHANNA- UNIT 2TS / B 3.6-98Revision 2 PPL Rev. 9SCIVsB 3.6.4.2Table B 3.6.4.2-2Secondary Containment Ventilation SystemPassive Isolation Valves or Devices(Page 1 of 4)Device Number Device Description Area/Elev. Required Position / NotesX-29-2-44 SDHR System to Fuel Pool Cooling Yard/670 Blind Flanged / Note 1X-29-2-45 SDHR System to Fuel Pool Cooling Yard/670 Blind Flanged / Note 1110176 SDHR Supply Drain Vlv 29/670 Closed Manual Iso Valve I Note 1110186 SDHR Discharge Drain VIv 29/670 Closed Manual Iso Valve / Note 1110180 SDHR Supply Vent Vlv 29/749 Closed Manual Iso Valve / Note 1110181 SDHR Discharge Fill Vlv 27/749 Closed Manual Iso Valve / Note 1110182 SDH R Discharge Vent VIv 27/749 Closed Manual Iso Valve / Note 1110187 SDHR Supply Fill Vlv 29/749 Closed Manual Iso Valve / Note 1210186 SDHR Supply Drain Vlv 33/749 Closed Manual Iso Valve / Note 1210187 SDHR Supply Vent Vlv 33/749 Closed Manual Iso Valve / Note 1210191 SDHR Discharge Vent Vlv 30/749 Closed Manual Iso Valve I Note 1210192 SDHR Discharge Drain VIv 30/749 Closed Manual Iso Valve / Note 1210193 SDH R Discharge Vent VIv 33/749 Closed Manual Iso Valve / Note 1X-29-2-46 Temporary Chiller to RBCW Yard/670 Blind Flanged / Note 2X-29-2-47 Temporary Chiller to RBCW Yard/670 Blind Flanged / Note 2X-29-5-95 Temporary Chiller to Unit I RBCW 29/749 Blind Flanged I Note 2X-29-5-96 Temporary Chiller to Unit 1 RBCW 29/749 Blind Flanged / Note 2X-29-5-91 Temporary Chiller to Unit 2 RBCW 33/749 Blind Flanged / Note 2X-29-5-92 Temporary Chiller to Unit 2 RBCW 33/749 Blind Flanged / Note 2187388 RBCW Temp Chiller Discharge Iso Vlv 29/670 Closed Manual Iso Valve / Note 2187389 RBCW Temp Chiller Supply Iso Vlv 29/670 Closed Manual Iso Valve / Note 2187390 RBCW Temp Chiller Supply Drain Vlv 29/670 Closed Manual Iso Valve / Note 2187391 RBCW Temp Chiller Discharge Drain Vlv 29/670 Closed Manual iso Valve / Note 2X-28-2-3000 Utility Penetration to Unit 1 East Stairwell Yard/670 Blind Flanged / Note 3X-29-2-48 Utility Penetration to Unit 1 RR Bay Yard/670 Capped / Note 5X-33-2-3000 Utility Penetration to Unit 2 East Stairwell Yard/670 Blind Flanged / Note 4X-28-2-3000 Utility Penetration to Unit 1 East Stairwell 28/670 Blind Flanged / Note 3X-29-2-48 Utility Penetration to Unit 1 RR Bay 29/670 Capped / Note 5X-33-2-3000 Utility Penetration to Unit 2 East Stairwell 33/670 Blind Flanged / Note 4X-29-3-54 Utility Penetration to Unit 1 RBCCW Hx Area 27/683 Blind Flanged / Note 6X-29-3-55 Utility Penetration to Unit 1 RBCCW Hx Area 27/683 Blind Flanged / Note 6X-29-5-97 Utility Penetration from Unit 1 RR Bay to Unit 2 Elev. 33/749 CappedX-29-5-97________749X-27-6-42 Diamond Plate Cover over Floor Penetration 271779' InstalledX-27-6-92 Instrument Tubing Stubs 27/779' CappedX-29-7-4 1" Spare Conduit Threaded Plug 29/818' InstalledX-30-6-72 Instrument Tubing Stubs 30/779' CappedX-30-6-1002 Stairwell #214 Rupture Disc 30/779' Installed IntactX-30-6-1003 Airlock 11-609 Rupture Disc 30/-79' Installed IntactX-25-6-1 008 Airlock 1-606 Rupture Disc 25/779' Installed IntactX-29-4-Dl -B Penetration at Door 4330 29/719' Blind Flange InstalledX-29-4-D1-A Penetration at Door 4330 29/719' Blind Flange InstalledX-29-4-D1 -B Penetration at Door 404 33/719' Blind Flange InstalledX-29-4-D1 -A Penetration at Door 404 33/719' Blind Flange InstalledSUSQUEHANNA- UNIT 2TS / B 3.6-99Revision 7 PPL Rev. 9SCIVsB 3.6.4.2Table B 3.6.4.2-2Secondary Containment Ventilation SystemPassive Isolation Valves or Devices(Page 2 of 4)Device Number Device Description Area/Elev. Required Position / NotesHD17534C Airlock 1-707 Blind Flange 28/799' Blind Flange InstalledHD27534C Airlock 11-707 Blind Flange 33/799' Blind Flange InstalledXD-1 7513 Isolation damper for Railroad Bay Zone III HVAC 29/799' Position is dependent on RailroadSupply Bay alignmentXD-1 7514 Isolation damper for Railroad Bay Zone III HVAC 29/719' Position is dependent on RailroadExhaust Bay alignmentXD-1 2301 PASS Air Flow Damper 11/729' Closed DamperXD-22301 PASS Air Flow Damper 22/729' Closed Damper161827 HPCI Blowout Steam Vent Drain Valve 25/645' Closed Manual Iso Valve / Note 3161828 RCIC Blowout Steam Vent Drain Valve 281645' Closed Manual Iso Valve / Note 3161829 'A' RHR Blowout Steam Vent Drain Valve 29/645' Closed Manual Iso Valve / Note 3161830 'B' RHR Blowout Steam Vent Drain Valve 28/645' Closed Manual Iso Valve / Note 3261820 RCIC Blowout Steam Vent Drain Valve 33/645' Closed Manual Iso Valve / Note 4261821 'A' RHR Blowout Steam Vent Drain Valve 34/645' Closed Manual Iso Valve / Note 4261822 'B' RHR Blowout Steam Vent Drain Valve 331645' Closed Manual Iso Valve / Note 42LRWI810L Zone III Floor Drain 34-818 Plugged / Note 72LRWI810M Zone III Floor Drain 34-818 Plugged I Note 72LRWI81ON Zone III Floor Drain 34-818 Plugged / Note 72LRWI810R Zone Ill Floor Drain 34-818 Plugged / Note 72LRWI810S Zone III Floor Drain 34-818 Plugged / Note 72LRWI703A Zone II Floor Drain 34-799 Plugged / Note 72LRWI615A Zone II Floor Drain 34-779 Plugged / Note 72LRWI100A Zone II Floor Drain 34-670 Plugged / Note 72LRWI100B Zone II Floor Drain 34-670 Plugged / Note 72LRWI100C Zone II Floor Drain 34-670 Plugged / Note 72LRWI100D Zone II Floor Drain 34-670 Plugged / Note 72LRWI100E Zone II Floor Drain 34-670 Plugged / Note 72LRWI100F Zone II Floor Drain 34-670 Plugged / Note 72LRWI100G Zone II Floor Drain 34-670 Plugged / Note 7SUSQUEHANNA -UNIT 2TS / B 3.6-99aRevision 6 PPL Rev. 9SCIVsB 3.6.4.2Table B 3.6.4.2-2Secondary Containment Ventilation SystemPassive Isolation Valves or Devices(Page 3 of 4)Device Number Device Description Area/Elev. Required Position / Notes1 LRWI81 OU Zone III Floor Drain 29-818 Plugged / Note 71LRWI1810V Zone III Floor Drain 29-818 Plugged / Note 71 LRWI181OW Zone III Floor Drain 29-818 Plugged I Note 71 LRWI81 OX Zone III Floor Drain 29-818 Plugged / Note 71LRWI81OY Zone III Floor Drain 29-818 Plugged / Note 71 LRWI81OZ Zone III Floor Drain 29-818 Plugged / Note 71LRWI81OFF Zone III Floor Drain 29-818 Plugged / Note 71 LRWI81OGG Zone III Floor Drain 29-818 Plugged / Note 71LRWI810HH Zone III Floor Drain 29-818 Plugged / Note 71 LRWI81OJJ Zone III Floor Drain 29-818 Plugged / Note 71 LRWI81OKK Zone III Floor Drain 29-818 Plugged / Note 71 LRW1615A Zone I, Zone III, or No Zone Floor Drain 29-779 Plugged ! Note 71LRWI100A Zone I, Zone II, or No Zone Floor Drain 29-670 Plugged I Note 71LRWI100B Zone I, Zone 11, or No Zone Floor Drain 29-670 Plugged / Note 71LRWII00C Zone I, Zone I1, or No Zone Floor Drain 29-670 Plugged / Note 71LRWI1OOD Zone I, Zone Ill, or No Zone Floor Drain 29-670 Plugged / Note 71LRWI100E Zone I, Zone Ill, or No Zone Floor Drain 29-670 Plugged / Note 71LRWI10OF Zone I, Zone III, or No Zone Floor Drain 29-670 Plugged / Note 71LRWI100G Zone I, Zone III, or No Zone Floor Drain 29-670 Plugged / Note 7SUSQUEHANNA -UNIT 2TS / B 3.6-99bRevision 4 PPL Rev. 9SCIVsB 3.6.4.2Table B 3.6.4.2-2Secondary Containment Ventilation SystemPassive Isolation Valves or Devices(Page 4 of 4)Note 1: The two blind flanges on the SDHR penetrations (blind flanges for device number X-29-2-44 and X-29-2-45) and all the closedmanual valves for the SDHR system (110176,110186,110180,110181,110182,110187, 210186, 210187, 210191, 210192, 210193)can each be considered as a separate secondary containment isolation device for the SDHR penetrations. If one or both of the blindflanges is removed and all the above identified manual valves for the SDHR system are closed, the appropriate LCO should be enteredfor one inoperable SCIV in a penetration flow path with two SCIVs. With the blind flange removed, the manual valves could be openedintermittently under administrative controls per the Technical Specification Note. When both SDHR blind flanges are installed, opening ofthe manual valves for the SDHR system will be controlled to prevent cross connecting ventilation zones. When the manual valves for theSDHR system are open in this condition, the appropriate LCO should be entered for one inoperable SCIV in a penetration flow path withtwo SCIVs. When the SDHR system piping is connected and full of water, the piping forms the secondary containment boundary and theabove listed SCIVs in Table B3.6.4.2-2 are no longer required for this system since the piping forms the barrier.Note 2: Due to the multiple alignments of the RBCW temporary chiller, different devices will perform the SCiV function depending on theRBCW configuration. There are three devices/equipment that can perform the SCIV function for the RBCW temporary chiller supplypenetration. The first SCIV for the RBCW temporary chiller supply penetration is the installed blind flange on penetration X-29-2-47. Thesecond SCIV for the RBCW temporary chiller supply penetration is isolation valve 187389. The third SCIV for the temporary RBCWchiller supply penetration is closed drain valve 187390 and an installed blind flange on penetrations X-29-5-92 and/or X-29-5-96. Sincethere are effectively three SCIVs, any two can be used to define the SCIV for the penetration. Removal of one of the two required SCIVsrequires entry into the appropriate LCO for one inoperable SCIV in a penetration flow path with two SCIVs. Opening of drain valve187390 and operation of blank flanges X-29-5-96 and X-29-5-92 will be controlled to prevent cross connecting ventilation zones. Thesethree SCIVs prevent air inleakage into secondary containment. The isolation of the penetration per the Technical Specificationrequirement is to assure that one of the above SCIVs is closed so that there is no air inleakage into secondary containment.There are three devices/equipment that can perform the SCIV function for the RBCW temporary chiller return penetration. The first SCIVfor the RBCW temporary chiller return penetration is the installed blind flange on penetration X-29-2-46. The second SCIV for theRBCW temporary chiller return penetration is isolation valve 187388. The third SCIV for the temporary RBCW chiller return penetrationis closed drain valve 187391 and an installed blind flange on penetrations X-29-5-91 and/or X-29-5-95. Since there are effectively threeSCIVs, any two can be used to define the SCIV for the penetration. Removal of one of the two required SCIVs requires entry into theappropriate LCO for one inoperable SCIV in a penetration flow path with two SCIVs. Opening of drain valve 187391 and operation ofblank flanges X-29-5-91 and X-29-5-95 will be controlled to prevent cross connecting ventilation zones. These three SCIVs prevent airinleakage into secondary containment. The isolation of the penetration per the Technical Specification requirement is to assure that oneof the above SCIVs is closed so that there is no air inleakage into secondary containment.When the RBCW temporary chiller piping is connected and full of water, the piping inside secondary containment forms the secondarycontainment boundary and the above listed SCIVs in Table B3.6.4.2-2 are no longer required for this system.Note 3: These penetrations connect Secondary Containment Zone I to a No-Zone. When Secondary Containment Zone I is isolatedfrom the recirculation plenum, the above listed SCIVs in Table B3.6.4.2-2 are no longer required.Note 4: These penetrations connect Secondary Containment Zone II to a No-Zone. When Secondary Containment Zone II is isolatedfrom the recirculation plenum, the above listed SCIVs in Table B3.6.4.2-2 are no longer required.Note 5: These penetrations connect the Railroad Bay to a No-Zone. When the Railroad Bay is a No-Zone, the above listed SCIVs inTable B3.6.4.2-2 are no longer required.Note 6: These penetrations connect Secondary Containment Zone I to the Railroad Bay. The above listed SCIVs in Table B3.6.4.2-2 arenot required if the Railroad Bay is a No-Zone and Zone I is isolated from the recirculation plenum OR if the Railroad Bay is aligned toZone I.Note 7: Due to drain header containing multiple floor drains in different ventilation zones, drain plugs were installed in all of the drainheader floor drains. To provide the passive Secondary Containment boundary, only drain plugs in one ventilation zone are required to beinstalled.SUSQUEHANNA -UNIT 2TS / B 3.6-99cRevision 0}}

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