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Susquehanna, Unit 1 - Technical Specifications Bases Manual
	ML15317A009
Person / Time
Site:	Susquehanna
Issue date:	11/05/2015
From:	Gerlach R M; Susquehanna
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	Download: ML15317A009 (31)
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Nov. 05, 2015 Page 1 of 2 MANUAL HARD COPY DISTRIBUTION DOCUMENT TRANSMITTAL 2015-44473 USER INFORMATION:

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TO: GERLACH*ROSEY N 11/05/2015 LOCATION:

USNRC FROM: NUCLEAR RECORDS DOCUMENT CONTROL CENTER (NUCSA-2)THE FOLLOWING CHANJGES HAVE OCCURRED TO THE HARDCOPY OR ELECTRONIC MANUAL ASSIGNED TO YOU. HARDCOPY USERS MUST ENSURE THE DOCUMENTS PROVIDED MATCH THE INFORMATION ON THIS TRANSMITTAL.

WHEN REPLACING THIS MATERIAL IN YOUR HARDCOPY MANUAL, ENSURE THE UPDATE DOCUMENT ID IS THE SAME DOCUMENT ID YOU'RE REMOVING FROM YOUR MANUAL. TOOLS FROM THE HUMAN PERFORMANCE TOOL BAG SHOULD BE UTILIZED TO ELIMINATE THE CHANCE OF ERRORS.ATTENTION: "REPLACE" directions do not affect the Table of Contents, Therefore no T0C will be issued with the updated material.TSBI -TECHNICAL SPECIFICATION BASES UNIT 1 MANUAL REMOVE MANUAL TABLE OF CONTENTS ADD TABLE OF CONTENTS CATEGORY:

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SSES MANUAL Manual Name: TSBI Manual Title: TECHNICAL SPECIFICATION BASES UNIT 1 MANUAL Table Of Contents Issue Date: 11/04/2015 Procedure Name Rev TEXT LOES 121 Title: LIST OF EFFECTIVE SECTIONS Issue Date 11/04/2 015 Change ID Change Number TEXT TOC Title: TABLE OF CONTENTS 23 07/02/2014 TEXT 2.1.1 6 Title: SAFETY LIMITS (SLS) REACTOR TEXT 2.1.2 1 Title: SAFETY LIMITS (SLS) REACTOR 01/22 /2 015 CORE SLS 10/ 04/2 007 COOLANT SYSTEM (RCS) PRESSURE S TEXT 3.0 3 08/20/2009 Title: LIMITING CONDITION FOR OPERATION (LCO) APPLICABILITY TEXT 3.1.1 Title: REACTIVITY TEXT 3.1.2 Title: REACTIVITY TEXT 3.1.3 Title: REACTIVITY TEXT 3.1.4 Title: REACTIVITY TEXT 3.1.5 Title: REACTIVITY TEXT 3.1.6 Title: REACTIVITY 1 04/18/2006 CONTROL SYSTEMS SHUTDOWN MARGIN (SDM)0 11/15/2002 CONTROL SYSTEMS REACTIVITY ANOMALIES 2 01/19/2009 CONTROL SYSTEMS CONTROL ROD OPERABILITY 4 01/30/2009 CONTROL SYSTEMS CONTROL ROD SCRAM TIMES 1 07/06/2005 CONTROL SYSTEMS CONTROL ROD SCRAM ACCUMULATORS 3 02/24/2014 CONTROL SYSTEMS ROD PATTERN CONTROL Pagel of 8 Report Date: 11/05/15 Page ! of Report Date: 11/05/15 SSES MANUA Manual Name: TSBI Manual Title: TECHNICAL SPECIFICATION BASES UNIT 1 MANUAL TEXT 3.1.7 3 04/23/2008 Title: REACTIVITY CONTROL SYSTEMS STANDBY LIQUID CONTROL (SLC) SYSTEM TEXT 3.1.8 3 05/06/2009 Title: REACTIVITY CONTROL SYSTEMS SCRAM DISCHARGE VOLUME (SDV) VENT AND DRAIN VALVES TEXT 3.2.1 2 04/23/2008 Title: POWER DISTRIBUTION LIMITS AVERAGE PLANAR LINEAR HEAT GENERATION RATE (APLHGR)TEXT 3.2.2 3 05/06/2009 Title: POWER DISTRIBUTION LIMITS MINIMUM CRITICAL POWER RATIO (MCPR)TEXT 3.2.3 2 04/23/2008 Title: POWER DISTRIBUTION LIMITS LINEAR HEAT GENERATION RATE (LHGR)TEXT 3.3.1.1 6 02/24/2014 Title: INSTRUMENTATION REACTOR PROTECTION SYSTEM (RPS) INSTRUMENTATION TEXT 3.3.1.2 2 01/19/2009 Title: INSTRUMENTATION SOURCE RANGE MONITOR (SRM) INSTRUMENTATION TEXT 3.3.2.1 Title: INSTRUMENTATION TEXT 3.3.2.2 Title: INSTRUMENTATION 4 02/24/2014 CONTROL ROD BLOCK INSTRUMENTATION 2 04/05/2010 FEEDWATER MAIN TURBINE HIGH WATER LEVEL TRIP INSTRUMENTATION TEXT 3.3.3.1 9 02/28/2013 Title: INSTRUMENTATION POST ACCIDENT MONITORING (PAM) INSTRUMENTATION TEXT 3.3.3.2 Title: INSTRUMENTATION 1 04/18/2005 REMOTE SHUTDOWN SYSTEM TEXT 3.3.4.1 2 02/24/2014 Title: INSTRUMENTATION END OF CYCLE RECIRCULATION PUMP TRIP (EOC-RPT)

INSTRUMENTATION W Page 2. of .~ Report Date: 11/05/15 Page of 8 Report Date: 11/05/15 SSES MANTJAL Manual Name: TSB1* aulTitle:

TECHNICA SPECIFICATION BASES UNIT 1 MNA TEXT 3.3.4.2 0 11/15/2002 Title: INSTRUMENTATION ANTICIPATED TRANSIENT WITHOUT SCRAM RECIRCULATION PUMP TRIP (ATWS-RPT)

INSTRUMENTATION TEXT 3.3.5.1 3 08/20/2009 Title: INSTRUMENTATION EMERGENCY CORE COOLING SYSTEM (ECCS) INSTRUMENTATION TEXT 3.3.5.2 0 11/15/2002 Title: INSTRUMENTATION REACTOR CORE ISOLATION COOLING CRCIC) SYSTEM INSTRUMENTATION TEXT 3.3.6.1 7 03/31/2014 Title: INSTRUMENTATION PRIMARY CONTAINMENT ISOLATION INSTRUMENTATION TEXT 3.3.6.2 4 09/01/2010 Title: INSTRUMENTATION SECONDARY CONTAINMENT ISOLATION INSTRUMENTATION TEXT 3.3.7.1 Title: INSTRUMENTATION INSTRUMENTATION 2 10/27/2008 CONTROL ROOM EMERGENCY OUTSIDE AIR SUPPLY (CREOAS) SYSTEM TEXT 3.3.8.1 2 12/17/2007 Title: INSTRUMENTATION LOSS OF POWER (LOP) INSTRUMENTATION TEXT 3.3.8.2 0 11/15/2002 Title: INSTRUMENTATION REACTOR PROTECTION SYSTEM (RPS) ELECTRIC POWER MONITORING TEXT 3.4.1 Title: REACTOR COOLANT TEXT 3.4.2 Title: REACTOR COOLANT TEXT 3.4.3 Title: REACTOR COOLANT 4 04/27/2010 SYSTEM (RCS) RECIRCULATION LOOPS OPERATING 3 10/23/2013 SYSTEM (RCS) JET PUMPS 3 01/13/2012 SYSTEM RCS SAFETY RELIEF VALVES S/RVS TEXT 3.4.4 0 11/15/2002 Title: REACTOR COOLANT SYSTEM (RCS) RCS OPERATIONAL LEAKAGE Page 3 of 8 Report Date: 11/05/15 Page A of 8 Report Date: 11/05/15 SSES MANqUAL Manual Name: TSBI SManual Title: TECHNICAL SPECIFICATION BASES UNIT 1 MANUAL TEXT 3.4.5 1 01/16/2006 Title: REACTOR COOLANT SYSTEM CRCS) RCS PRESSURE ISOLATION VALVE (PIV) LEAKAGE TEXT 3.4.6 Title: REACTOR COOLANT 4 SYSTEM (RCS)02/19/2 014 RCS LEAKAGE DETECTION INSTRUMENTATION TEXT 3.4.7 2 10/04/2007 Title: REACTOR COOLANT SYSTEM (RCS) RCS SPECIFIC ACTIVITY TEXT 3.4.8 Title: REACTOR COOLANT-HOT SHUTDOWN TEXT 3.4.9 Title: REACTOR COOLANT-COLD SHUTDOWN TEXT 3.4.10 Title: REACTOR COOLANT TEXT 3.4.11 Title: REACTOR COOLANT TEXT 3.5.1 2 SYSTEM (RCS)03/28/2013 RESIDUAL HEAT REMOVAL (RHR) SHUTDOWN COOLING SYSTEM 1 03/28/2013 SYSTEM (RCS) RESIDUAL HEAT REMOVAL (RER) SHUTDOWN COOLING SYSTEM 0 4 11/04/2015 SYSTEM (RCS) RCS PRESSURE AND TEMPERATURE (P/T) LIMITS 0 11/15/2002 SYSTEM (RCS) REACTOR STEAM DOME PRESSURE 4 07/16/2014 Title: EMERGENCY CORE COOLING SYSTEMS (ECCS) AND REACTOR SYSTEM ECCS -OPERATING TEXT 3.5.2 0 11/15/2002 Title: EMERGENCY CORE COOLING SYSTEMS (ECCS) AND REACTOR SYSTEM ECCS -SHUTDOWN TEXT 3.5.3 3 02/24/2014 Title: EMERGENCY CORE COOLING SYSTEMS (ECCS) AND REACTOR SYSTEM RCIC SYSTEM CORE ISOLATION COOLING (RCIC)CORE ISOLATION COOLING CRCIC)CORE ISOLATION COOLING (RCIC)TEXT 3.6.1.1 Title: PRIMARY CONTAINMENT 5 02/24/2014 TEXT 3.6.1.2 1 04/23/2008 Title: CONTAINMENT SYSTEMS PRIMARY CONTAINMENT AIR LOCK Page4 of 8 Report Date: 11/05/15 Page of Report Date: 11/05/15 SSES MANUALJM Manual Name: TSB1 Manual Title: TECHNICAL SPECIFICATION BASES UNIT 1 MANUAL TEXT 3.6.1.3 Title: CONTAINMENT TEXT 3.6.1.4 Title: CONTAINMENT TEXT 3.6.1.5 Title: CONTAINMENT TEXT 3.6.1.6 Title: CONTAINMENT TEXT 3.6.2.1 Title: CONTAINMENT TEXT 3.6.2.2 Title: CONTAINMENT TEXT 3.6.2.3 Title: CONTAINMENT TEXT 3.6.2.4 Title: CONTAINMENT TEXT 3.6.3.1 Title: CONTAINMENT TEXT 3.6.3.2 Title: CONTAINMENT TEXT 3.6.3.3 Title: CONTAINMENT TEXT 3.6.4.1 Title: CONTAINMENT 11 07/02/2014 SYSTEMS PRIMARY CONTAINMENT ISOLATION VALVES (PCIVS)1 04/23/2008 SYSTEMS CONTAINMENT PRESSURE 1 10/05/2005 SYSTEMS DRYWELL AIR TEMPERATURE 0 11/15/2002 SYSTEMS SUPPRESSION CHANBER-TO-DRYWELL VACUUM BREAKERS 2 04/23/2008 SYSTEMS SUPPRESSION POOL AVERAGE TEMPERATURE 0 11/15/2002 SYSTEMS SUPPRESSION POOL WATER. LEVEL 1 01/16/2006 SYSTEMS RESIDUAL HEAT REMOVAL (RER) SUPPRESSION POOL COOLING 0 11/15/2002 SYSTEMS RESIDUAL HEAT REMOVAL (RHR) SUPPRESSION POOL SPRAY 2 06/13/2006 SYSTEMS PRIMARY CONTAINMENT HYDROGEN RECOMBINERS 1 04/18/2005 SYSTEMS DRYWELL AIR FLOW SYSTEM 1 02/28/2013 SYSTEMS PRIMARY CONTAINMENT OXYGEN CONCENTRATION 11 11/06/2014 SYSTEMS SECONDARY CONTAINMENT Page~ of 8 Report Date: 11/05/15 Page 5 of Report Date: 11/05/15 SSES MANUJAL Manual Name:- TSB1 Title: TECHNICAL SPECIFICATION BASES UNIT 1 MANUAL TEXT 3.6.4.2 9 04/25/2014 Title: CONTAINMENT SYSTEMS SECONDARY CONTAINMENT ISOLATION VALVES (SCIVS)TEXT 3.6.4.3 4 09/21/2006 Title: CONTAINMENT SYSTEMS STANDBY GAS TREATMENT (SGT) SYSTEM TEXT 3.7.1 Title: PLANT SYSTEMS ULTIMATE HEAT 4 04/05/2010 RESIDUAL HEAT REMOVAL SERVICEWATER_

CRHRSW) SYSTEM AND THE SINK (UES)TEXT 3.7.2 Title: PLANT 2 02/11/2009 SYSTEMS EMERGENCY SERVICE WATER (ESW) SYSTEM TEXT 3.7.3 Title: PLANT SYSTEMS 1 01/08/2010 CONTROL ROOM EMERGENCY OUTSIDE AIR SUPPLY (CREOAS) SYSTEM TEXT 3.7.4 Title: PLANT TEXT 3.7.5 Title: PLANT TEXT 3.7.6 Title: PLANT TEXT 3.7.7 Title: PLANT 0 11/15/2002 SYSTEMS CONTROL ROOM FLOOR COOLING SYSTEM 1 10/04/2007 SYSTEMS MAIN CONDENSER OFFGAS 2 04/23/2008 SYSTEMS MAIN TURBINE BYPASS SYSTEM 1 10/04/2007 SYSTEMS SPENT FUEL STORAGE POOL WATER LEVEL TEXT 3.7.8 Title: PLANT SYSTEMS 0 04/23/2008 TEXT 3.8.1 7 02/24/2014 Title: ELECTRICAL POWER SYSTEMS AC SOURCES -OPERATING-TEXT 3.8.2 0 11/15/2002 S- Title: ELECTRICAL POWER SYSTEMS AC SOURCES -SHUTDOWN Page6 of 8 Report Date: 11/05/15 Page 6 of Report Date: 11/05/15 SSE~S MANUAL.Manual Name : TSBI Manual Title: TECHNICAL SPECIFICATION BASES UNIT 1 MANUAL TEXT 3.8.3 Title: ELECTRICAL TEXT 3.8.4 Title : ELECTRICAL TEXT 3.8.5__Title: ELECTRICAL TEXT 3.8.6 Title: ELECTRICAL TEXT 3.8.7 Title:- ELECTRICAL TEXT 3.8.8 Title: ELECTRICAL TEXT 3.9.1 Title: REFUELING C TEXT 3.9.2 Title: REFUELING C TEXT 3.9.3 Title: REFUELING C TEXT 3.9.4 Title: REFUELING C TEXT 3.9.5 Title: REFUELING C TEXT 3.9.6 Title: REFUELING C POWER SYSTIJ POWER SYST POWER SYST POWER SYST POWER SYST POWER SYSI)PERATIONS)PERATIONS)PERATIONS)PERATIONS)PERATIONS)PERATIONS 4 10/23/2013DIESEL FUEL OIL, LUBE OIL, AND STARTING AIR 3 01/19/2009

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

?EMS DC SOURCES -SHUTDOWN 1 12/14/2006 PEMS BATTERY CELL PARAMVETERS 1 10/05/2005

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

?ENS DISTRIBUTION SYSTEMS -SHUTDOWN 0 11/15/2002 REFUELING EQUIPMENT INTERLOCKS 1 09/01/2010 REFUEL POSITION ONE-ROD-OUT INTERLOCK 0 11/15/2002 CONTROL ROD POSITION 0 11/15/2002 CONTROL ROD POSITION INDICATION 0 11/15/2002 CONTROL ROD OPERABILITY

-REFUELING 1 10/04/2007 REACTOR PRESSURE VESSEL (RPV) WATER LEVEL Page 2 of 8 Report Date: 11/05/15 Page of 8 Report Date: 11/05/15 MANUITAL Manual Name:s TSBI Title: TECHNICAL SPECIFICATION BASES UNIT 1 MANUAL TEXT 3.9.7 0 11/15/2002 Title: REFUELING OPERATIONS RESIDUAL HEAT REMOVAL (RHR) -HIGH WATER LEVEL TEXT 3.9.8 0 11/15/2002 Title: REFUELING OPERATIONS RESIDUAL HEAT REMOVAL (RER) -LOW WATER LEVEL TEXT 3.10.1 Title: SPECIAL TEXT 3.10.2 Title: SPECIAL TEXT 3.10.3 Title: SPECIAL TEXT 3.10.4 Title: SPECIAL TEXT 3.10.5 Title: SPECIAL TEXT 3.10.6 Title: SPECIAL TEXT 3.10.7 Title: SPECIAL TEXT 3.10.8 Title: SPECIAL OPERATIONS OPERATIONS OPERATIONS OPERATIONS OPERATIONS OPERATIONS OPERATIONS OPERATIONS 1 01/23/2008 INSERVICE LEAK AND HYDROSTATIC TESTING OPERATION 0 11/15/2002 REACTOR MODE SWITCH INTERLOCK TESTING 0 11/15/2002 SINGLE CONTROL ROD WITHDRAWAL

-HOT SHUTDOWN 0 11/15/2002 SINGLE CONTROL ROD WITHDRAWAL

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

-REFUELING 1 04/18/2006 CONTROL ROD TESTING -OPERATING 1 04/12/2006 SHUTDOWN MARGIN (SDM) TEST -REFUELING S Page8 of 8 Report Date: 11/05/15 Page 8 of 8 Report Date: 11/05/15 SUSQUEHANNA STEAM ELECTRIC STATION LIST OF EFFECTIVE SECTIONS (TECHNICAL SPECIFICATIONS BASES)Section Title Revision TOC Table of Contents 23 B 2.0 SAFETY LIMITS BASES Page TS / B2.0-1 1 Page TS /B 2.0-2 3 Page TS /8B2.0-3 6 Page TS /B 2.0-4 4 Page"S / B 2.0-5 6 Page TS / B 2.0-6 1 Pages TS / B 2.0-7 through TS / B 2.0-9 1 B 3.0 LCO AND SR APPLICABILITY BASES Page TS / B3.0-1 Pages TS / B 3.0-2 through TS/IB 3.0-4 0 .....Pages TS / B 3.0-5 through TS / B 3.0-7 Page TS / B3.0-8 3 Pages TS / B 3.0-9 through TS I B 3.0-11 2 Page TS / B 3.0-11a 0 Page TS /B 3.0-12I Pages TS / B 3.0-13 through TS I2 Pages TS /B3.0-16 and TS 0 B 3.1 REACTIVITY CONTROL BAy Pages B83.1-1 trug 0 Page TS / B 3.1-5A 1 PagesTS /Ba3.1 d .72 Pages B3.1-8 t 3.Page 3. 20ghB 3.1-19 0 20 and TS / B 3.1-21 1 Pa 03.1-23I 3.1-240 Pa TS / B 3.1-25 through TS /8B3.1-27 1TS B 31-282 ,= TS/ B 31-29I Pages B 3.1-30 through B 3.1-33 0 Pages TS I B 3.3-34 through TS I B 3.3-36 1 Page TS /8B3.1-37 2 Page TS I B 3.1-38 3 Pages TS /8B3.1-39 and TS /8B3.1-40 2 Page TS I B 3.1-40a 0 Pages TS /B 3.1-41 and TS / B3.1-42 2 SUSQUEHANNA

-UNIT 1 TSIB LOES-1 Revision 121 SUSQUEHANNA

-UNIT 1 TS / B LOES-1 Revision 121 SUSQUEHANNA STEAM ELECTRIC STATION LIST OF EFFECTIVE SECTIONS (TECHNICAL SPECIFICATIONS BASES)Section Title Revision Page TS I B 3.1.43 1 Page TS / B 3.1-44 0 Page TS I B 3.1-45 3 Pages TS I B 3.1-46 through TS I B 3.1-49 1 Page TS I B 3.1-50 0 Page TS / B 3.1-51 3 B 3.2 POWER DISTRIBUTION LIMITS BASES Page TS I B 3.2-1 2 Pages TS I B 3.2-2 and TS / B 3.2-33 Pages TS / B 3.2-4 and TS I B 3.2-5 2*Page TSI/B 3.2-6 3_ ageB3.2-7

.. ......_1__Pages TS / B 3.2-8 and TS I B 3.2-9 3 Page TS / B 3.2.10 2 Page TS / B 3.2-11 3 Page TS I B 3.2-12 1 Page TS / B 3.2-13 2 B 3.3 INSTRUMENTATION Pages TS / B 3.3-1 through TS I B 3.3-4 1 Page TS I B 3.3-5 2 Page TS / B 3.3-6 I Page TS / B 3.3-7 3 Page TS I B 3.3-7a I Page TS / B 3.3-8 5 Pages TS I B 3.3-9 through TS / B 3.3-12 3 Pages TS I B 3.3-12a I Pages TS / B 3.3-12b and TS I B 3.3-12c 0 Page TS I B 3.3-13 1 Page TS / B 3.3-14 3 Pages TS / B 3.3-15 and TS / B 3.3-16 1 Pages TS / B 3.3-17 and TS / B 3.3-18 4 Page TS / B 3.3-19 1 Pages TS I B 3.3-20 through TS I B 3.3-22 2 Page TS / B 3.3-22a 0 Pages TS / B 3.3-23 and TS I B 3.3-24 2 Pages TS I B 3.3-24a and TS / B 3.3-24b 0 Page TS / B 3.3-25 3 Page TS / B 3.3-26 2 Page TS / B 3.3-27 1 Page TS / B 3.3-28 3 Page TSI/B 3.3-29 4 Page TS I B 3.3-30 3 Page TS / B 3.3-30a 0 SUSQUEHANNA-UNIT1 TS / B LOES-2 Revision 121 SUSQUEHANNA STEAM ELECTRIC STATION LIST OF EFFECTIVE SECTIONS (TECHNICAL SPECIFICATIONS BASES)Section Title Revision Page TS / B 3.3-31 4 Page TS / B 3.3-32 5 Pages TS / B 3.3-32a 0 Page TS / B 3.3-32b 1 Page TS / B 3.3-33 5 Page TS I B 3.3-33a 0 Page TS / B 3.3-34 1 Pages TS / B 3.3-35 and TS / B 3.3-36 2 Pages TS / B 3.3-37 and TS / B 3.3-38 1 Page TSI/B 3.3-39 2 Pages TS I B 3.3-40 through TS I B 3.3-43 1 Page TSI/B 3.3-44 4 Pages TS I B 3.3_-4a and TS/_ B 3.3-44b -0 Page TS / B 3.3-45 3 Pages TS / B 3.3-45a and TS I B 3.3-45b 0 Page TS / B3.3-46 3 Pages TS / B 3.3-47 2 Pages TS I B 3.3-48 through TS / B 3.3-51 3 Pages TS I B 3.3-52 and TS / B 3.3-53 2 Page TS / B 3-3-53a 0 Page TS / B 3.3-54 5 Page TS / B 3.3-55 2 Pages TS I B 3.3-56 and TS / B 3.3-57 1 Page TS I B 3.3-58 0 Page TS I B 3.3-59 1 Page TS / B 3.3-60 0 Page TS / B 3.3-61 1 Pages TS / B 3.3-62 and TS / B 3.3-63 0 Pages TS / B 3.3-64 and TS / B 3.3-65 2 Page TS / B 3.3-66 4 Page TS / B 3.3-67 3 Page TS / B 3.3-68 4 Page TS / B 3.3-69 5 Pages TS / B 3.3-70 4 Page TS / B3.3-71 3 Pages TS I B 3.3-72 and TS I B 3.3-73 2 Page TS / B 3.3-74 3 Page TS I B 3.3-75 2 Page TS / B 3.3-75a 6 Page TS / B 3.3-75b 7 Page TS / B 3.3-75c 6 Pages B 3.3-76 through B 3.3-77 0 Page TS I B 3.3-78 1 SUSQUEHANNA

-UNIT I TSIBLOES-3 Revision 121 SUSQUEHANNA-UNIT 1 TS / B LOES-3 Revision 121 SUSQUEHANNA STEAM ELECTRIC STATION LIST OF EFFECTIVE SECTIONS (TECHNICAL SPECIFICATIONS BASES)Section Title Revision Pages B 3.3-79 through B 3.3-81 0 Page TS I B 3.3-82 2 Page B 3.3-83 0 Pages B 3.3-84 and B 3.3-85 1 Page B 3.3-86 0 Page B 3.3-87 1 Page B 3.3-88 0 Page B 3.3-89 1 Page TS I B 3.3-90 1 Page B 3.3-91 0.Pages TS/IB 3.3-92 through TS IB 3.3-100 1*Pages TSI/B 3.3-101 through TS/B 3.3-103 .0 PageTSI/B3.3-_104

.....-Pages TS I B 3.3-1 05 and TS I B 3.3-106 0 Page TS / B3.3-107 I Page TS I B 3.3-108 0 Page TS I B 3.3-109 1 Pages TS I B 3.3-110 and TS/B83.3-111 0 Pages TS I B 3.3-112 and TS I B 3.3-1 12a I Pages TS / B 3.3-113 through TS / B 3.3-115 1 Page TS / B 3.3-116 3 Page TS / B 3.3-117 1 Pages TS I B 3.3-118 through TS I B 3.3-122 0 Pages TS I B 3.3-123 and TS I B 3.3-124 1 Page TS I B 3.3-124a 0 Page TS I B 3.3-125 0 Pages TS I B 3.3-126 and TS I B 3.3-127 1 Pages TS I B 3.3-1 28 through TS/ B 3.3-130 0 Page TS / B 3.3-131 1 Pages TS I B 3.3-1 32 through TS I B 3.3-1 34 0 Pages B 3.3-135 through B 3.3-137 0 Page TS / B 3.3-138 1 Pages B 3.3-1 39 through B 3.3-149 0 Pages TS I B 3.3-150 and TS I B 3.3-151 1 Pages TS I B 3.3-1 52 through TS/IB 3.3-154 2 Page TS I B 3.3-155 1 Pages TS I B 3.3-1 56 through TS I B 3.3-158 2 Pages TS / B 3.3-159 and TS I B 3.3-160 1 Page TS / B 3.3-161 2 Page TS I B 3.3-162 1 Page TS I B 3.3-163 2 Page TS I B 3.3-164 1 Pages TS I B 3.3-165 through TS I B 3.3-167 2 SUSQUEHANNA

-UNIT I TSIBLOES-4 Revision 121 SUSQUEHANNA-UNIT1 TS / B LOES-4 Revision 121 SUSQUEHANNA STEAM ELECTRIC STATION LIST OF EFFECTIVE SECTIONS (TECHNICAL SPECIFICATIONS BASES)Section Title Revision Pages TS/IB 3.3-168 and TS / B 3.3-169 1 Page TS I B 3.3-170 3 Page TS I B 3.3-171 2 Pages TS I B 3.3-172 through TS / B 3.3-1 77 1 Pages TS / B 3.3-178 and TS I B 3.3-179 2 Page TS / B 3.3-179a 2 Pages TS I B 3.3-179b and TS / B 3.3-179c 0 Page TS / B 3.3-180 1 Page TIS / B 3.3-181 3 Page TS / B 3.3-182 1 Page TS / B 3.3-183 2 Page TS /8B3.3-184 1_P~ageTS /B 3.3-_185 -_Page TS / B 3.3-186 1 Pages TS I B 3.3-187 and TS I B 3.3-188 2 Pages TS / B 3.3-189 through TS I B 3.3-191 1 Page TS / B 3.3-192 0 Page TS / B 3.3-193 1 Pages TS I B 3.3-194 and TS I B 3.3-195 0 Page TS I B 3.3-196 2 Pages TS I B 3.3-197 through TS I B 3.3-204 0 Page TS / B 3.3-205 1 Pages B 3.3-206 through B 3.3-209 0 Page TS / B 3.3-210 1 Pages B 3.3-211 through B 3.3-219 0 B 3.4 REACTOR COOLANT SYSTEM BASES Pages B 3.4-1 and B 3.4-2 0 Pages TS / B 3.4-3 and Page TS I B 3.4-4 4 Page TS / B 3.4-5 3 Pages TS / B 3.4-6 through TS / B 3.4-9 2 Page TS / B 3.4-10 1 Pages TS / 3.4-11 and TS I B 3.4-12 0 Page TS / B 3.4-13 2 Page TS / B 3.4-14 1 Page TS /8B3.4-15 2 Pages TS /8B3.4-16 and TS 18B3.4-17 4 Page TS / B 3.4-18 2 Pages B 3.4-19 through B 3.4-27 0 Pages TS /8B3.4-28 and TS /8B3.4-29 1 Page TS / B 3.4-30 2 Page TS / B 3.4-31 1 Pages TS / B 3.4-32 and TS / B 3.4-33 2 Page TS /8B3.4-34 1 Page TS I B 3.4-34a 0 SUSQUEHANNA

-UNIT I TS/BLOES-5 Revision 121 SUSQUEHANNA

-UNIT 1 TS / B LOES-5 Revision 121 SUSQUEHANNA STEAM ELECTRIC STATION LIST OF EFFECTIVE SECTIONS (TECHNICAL SPECIFICATIONS BASES)Section Title Revision Pages TS / B 3.4-35 and TIS / B 3.4-36 1 Page TS / B 3.4-37 2 Page TS I B 3.4-38 1 Pages B 3.4-39 and B 3.4-40 0 Page TS I B 3.4-41 2 Pages TS I B 3.4-42 through TS I B 3.4-45 0 Page TS / B 3.4-46 1 Pages TS B 3.4-47 and TS / B 3.4-48 0 Page TS I B 3.4-49 3 Page TS / B 3.4-50 1 Page TS /B 3.4-51 3 Page TSI/B 3.4-52 3-P~ageTSI/B 3.4-52a --_ -0_Pages TS I B 3.4-53 through TS I B 3.4-56 2 Page TS I B 3.4-57 4 Page TS I B 3.4-57a 0 Pages TS / B 3.4-58 through TS I B 3.4-60 1 B 3.5 ECCS AND RCIC BASES Pages B 3.5-1 and B 3.5-2 0 Page TS / B 3.5-3 3 Page TS / B 3.5-4 1 Page TS / B 3.5-5 2 Page TSI/B 3.5-6 I Pages B 3.5-7 through B 3.5-10 0 Page TS /B 3.5-11 I Page TS I B 3.5-12 0 Page TS I B 3.5-13 2 Pages TS / B 3.5-14 and TS I B 3.5-15 0 Pages TS / B 3.5-16 and TS / B 3.5-17 3 Page TS / B 3.5-18 1 Pages B 3.5-19 through B 3.5-24 0 Page TS / B 3.5-25 1 Page TS I B 3.5-26 and TS / B 3.5-27 2 Page TS / B 3.5-28 0 Page TS I B 3.5-29 1 Pages TS / B 3.5-30 and TS I B 3.5-31 0 B 3.6 CONTAINMENT SYSTEMS BASES Page TS / B 3.6-1 2 Page TS I B 3.6-la 3 Page TS I B 3.6-2 4 Page TS I B 3.6-3 ,3 Page TS / B 3.6-4 4 Pages TS I B 3.6-5 and TS I B 3.6-6 3 SUSQUEHANNA

-UNIT I TSIBLOES-6 Revision 121 SUSQUEHANNA-UNIT1 TS / B LOES-6 Revision 121 SUSQUEHANNA STEAM ELECTRIC STATION LIST OF EFFECTIVE SECTIONS (TECHNICAL SPECIFICATIONS BASES)Section Title Revision Page TS I B 3.6-6a 2 Page TS I B 3.6-6b 4 Page TS I B 3.6-6c 0 Page B 3.6-7 0 Page B 3.6-8 1 Pages B 3.6-9 through B 3.6-14 0 Page TS / B 3.6-15 3 Page TS I B 3.6-15a 0 Page TS / B 3.6-15Sb 2 Pages TS / B 3.6-16 and TS / B 3.6-17 2 Page TS / B 3.6-17a I Pages TS I B 3.6-18 and TS I B 3.6-19 0-P~age TS LB 3.6-20 - -__ -...Page TS I B 3.6-21 2 Page TS / B 3.6-22 1 Page TS I B 3.6-22a 0 Page TS / B 3.6-23 1 Pages TS I B 3.6-24 and TS / B 3.6-25 0 Pages TS I B 3.6-26 and TS / B 3.6-27 2 Page TS I B 3.6-28 7 Page TS I B 3.6-29 2 Page TS /8B3.6-30 1 Page TS /8B3.6-31 3 Pages TS / B 3.6-32 and TS I B 3.6-33 1 Pages TS I B 3.6-34 and TS I B 3.6-35 0 Page TS /8B3.6-36 1 Page TS /8B3.6-37 0 Page TS I B 3.6-38 3 Page TS /8B3.6-39 2 Page TS /8B3.6-40 6 Page TS I B 3.6-40a' I Page B 3.6-41 1 Pages B 3.6-42 and B 3.6-43 0 Pages TS I B 3.6-44 and TS I B 3.6-45 1 Page TS / B 3.6-46 2 Pages TS I 8 3.6-47 through TS I B 3.6-51 1 Page TS /8B3.6-52 2 Pages TS / B 3.6-53 through TS / B 3.6-56 0 Page TS I B 3.6-57 1 Page TS / 3.6-58 2 Pages B 3.6-59 through B 3.6-63 0 Pages TS I B 3.6-64 and TS I B 3.6-65 1 Pages B 3.6-66 through B 3.6-69 0 SUSQUEHANNA-UNIT1 SUSQUEHANNA

-UNIT I TS/BLOES-.7 Revision 121 TS / B LOES-7 Revision 121 SUSQUEHANNA STEAM ELECTRIC STATION LIST OF EFFECTIVE SECTIONS (TECHNICAL SPECIFICATIONS BASES)Section Title Revision Pages TS I B 3.6-70 through TS I B 3.6-75 I Pages B 3.6-76 and B 3.6-77 0 Page TS I B 3.6-78 1 Pages B 3.6-79 and B 3.3.6-80 0 Page TS / B 3.6-81 1 Pages TS / B 3.6-82 and TS / B 3.6-83 0 Page TS I B 3.6-84 4 Page TS / B 3.6-85 2 Page TS I B 3.6-86 4 Pages TS / B 3.6-87 through TS I B 3.6-88a 2 Page TS I B 3.6-89 6 Page TSI/B 3.6-90 4 P~ageTS / B3.6_-90a

...._0_-Pages TS I B 3.6-91 and TS / B 3.6-92 3 Page TS I B 3.6-93 2 Pages TS / B 3.6-94 through TS l B 3.6-96 1 Page TS / B 3.6-97 2 Page TS I B 3.6-98 1 Page TS l B 3.6-99 2 Pages TS I B 3.6-100 and TS / B 3.6-l00a 6 Page TS / B 3.6-100b 4 ,Page TS I B 3.6-l00c 0 Pages TS I B 3.6-101 and TS / B 3.6-102 1 Pages TS / B 3.6-103 and TS / B 3.6-104 2 Page TS / B 3.6-105 3 Page TS I B 3.6-106 2 Page TS / B 3.6-107 3 B 3.7 PLANT SYSTEMS BASES Pages TS / B 3.7-1 3 Page TS / B 3.7-2 4 Pages TS / B 3.7-3 through TS / B 3.7-5 3 Page TS I B 3.7-5a I Page TS I B 3.7-6 3 Page TS / B 3.7-6a 2 Page TS I B 3.7-6b I Page TSIlB 3.7-6c 2 Page TS I B 3.7-7 3 Page TS / B 3.7-8 2 Pages TS / B 3.7-9 through TS/IB 3.7-11 1 Pages TS / B 3.7-12 and TS I B 3.7-13 2 Pages TS I B 3.7-14 through TS I B 3.7-18 3 Page TS I B 3.7-18a I Pages TS I B 3.7-1 8b through TS / B 3.7-18e 0 SUSQUEHANNA

-UNIT 1 TSIB LOES-8 Revision 121 SUSQUEHANNA-UNIT1 TS / B LOES-8 Revision 121 S USQUEHANNA STEAM ELECTRIC STATION LIST OF EFFECTIVE SECTIONS (TECHNICAL SPECIFICATIONS BASES)Section Title Revision Pages TS I B 3.7-19 through TS / B 3.7-23 1 Page TS I B 3.7-24 1 Pages TS / B 3.7-25 and TS / B 3.7-26 0 Pages TS I B 3.7-27 through TS I B 3.7-29 5 Page TS /B 3.7-30 2 Page TS I B 3.7-31 1 Page TS / B 3.7-32 0 Page TS / B 3.7-33 1 Pages TS / B 3.7-34 through TS / B 3.7-37 0 B 3.8 ELECTRICAL POWER SYSTEMS BASES Page TSI/B 3.8-1 3 P~ages TS/LB 3.8-2 and TS+/-B 3.8-3------------

-2 Page TS I B 3.8-4 3 Pages TS / B 3.8-4a and TS I B 3.8-4b 0 Page TS I B 3.8-5 5 Page TS / B 3.8-6 3 Pages TS I B 3.8-7 through TSIB 3.8-8 2 Page TS / B 3.8-9 4 Page TS / B 3.8-10 3 Pages TS I B 3.8-11 and TS I B 3.8-17 2 Page TS I B 3.8-18 3 Pages TS /8B3.8-19 through TS / B 3.8-21 2 Pages TS I B 3.8-22 and TS I B 3.8-23 3 Pages TS I B 3.8-24 through TS / B 3.8-30 2 Pages TS I B 3.8-31 and TS I B 3.8-32 3 Pages TS / B 3.8-33 through TS I B 3.8-37 2 Pages B 3.8-38 through B 3.8-44 0 Page TS /8B3.8-45 3 Pages TS I B 3.8-46 through TS / B 3.8-48 0 Pages TS / B 3.8-49 and TS / B 3.8-50 3 Page TS I B 3.8-51 1 Page TS /8B3.8-52 0 Page TS /B 3.8-53 1 Pages TS I B 3.8-54 through TS / B 3.8-57 2 Pages TS /8B3.8-58 through TS / B 3.8-61 3 Pages TS / B 3.8-62 and TS / B 3.8-63 5 Page TS /8B3.8-64 4 Page TS /8B3.8-65 5 Pages TS / B 3.8-66 through TS / B 3.8-77 1 Pages TS I B 3.8-77A through TS / B 3.8-77C 0 Pages B 3.8-78 through B 3.8-80 0 Page TS /8B3.8-81 1 Pages B 3.8-82 through B 3.8-90 0 SUSQUEHANNA

-UNIT I TS/B LOES-9 Revision 121 SUSQUEHANNA-UNIT 1 TS / B LOES-9 Revision 121 SUSQUEHANNA STEAM ELECTRIC STATION LIST OF EFFECTIVE SECTIONS (TECHNICAL SPECIFICATIONS BASES)Section Title Revision B 3.9 REFUELING OPERATIONS BASES Pages TS / B 3.9-1 and TS / B 3.9-la 1 Pages TS I B 3.9-2 through TS /8B3.9-5 1 Pages TS I B 3.9-6 through TS I 8 3.9-8 0 Pages 8 3.9-9 through 8 3.9-18 0 Pages TS /8B3.9-19 through TS /83.9-21 1 Pages B 3.9-22 through 8 3.9-30 0 B 3.10 SPECIAL OPERATIONS BASES Page TSI/B 3.10-1 2 Pages TS /8B3.10-2 through TS/IB 3.10-5 1--Pages B 3.10-6_through B_310-31 .....- O- 0 Page TS /8B3.10-32 2 Page 8 3.10-33 0 Page TS / B 3.10-34 1 Pages 8 3.10-35 and 8 3.10-36 0 Page TS /8B3.10-37 1 Page TS /8B3.10-38 2 SUSQUEHANNA

-UNIT I TS / B LOES-lO Revision 121 SUSQUEHANNA-UNIT1 TS / B LOES-IO Revision 121 Rev. 4 RCS P/T" Limits B 3.4.10 B 3.4 REACTOR COOLAkNT SYSTEM (RCS)B 3.4.10 RCS Pressure and Temperature (PIT) Limits BASES BACKGROUND All components of the RCS are designed to withstand effects of cyclic loads due to system pressure and temperature changes. These loads are introduced by startup (heatup) and shutdown (cooldown) operations, power transients, and reactor trips. This LCO limits the pressure and temperature changes during RCS heatup and cooldown, within the design assumptions and the stress limits for cyclic operation.

This Specification contains PIT limit curves for heatup, cooldown, and.......in~servi~ce_

lea~kage and_ hyd~rosta~ti~c testing, and limits for the maximum rate of change of reactor coolant temperature.

The heatup curve provides limits for both heatup and criticality.

Each PIT limit curve defines an acceptable region for normal operation.

The usual use of the curves is operational guidance during heatup or cooldown maneuvering, when pressure and temperature indications are monitored and compared to the applicable curve to determine that operation is within the allowable region.The LCO establishes operating limits that provide a margin to brittle failure of the reactor vessel and piping of the reactor coolant pressure boundary (RCPB). The vessel is the component most subject to brittle failure.Therefore, the LCO limits apply mainly to the vessel.10 CFR 50, Appendix G (Ref. 1), requires the establishment of P/T limits for material fracture toughness requirements of the RCPB materials.

Reference I requires an adequate margin to brittle failure during normal operation, anticipated operational occurrences, and system hydrostatic tests.It mandates the use of the ASME Code,Section XI, Appendix G (Ref. 2).The actual shift in the RTNDT of the vessel material will be established periodically by removing and evaluating the irradiated reactor vessel material specimens, in accordance with ASTM E 185 (Ref. 3) and Appendix H of 10 CFR 50 (Ref. 4). The operating PIT limit curves will be adjusted, as necessary, based on the evaluation findings and the recommendations of RG 1.99, "Radiation Embrittlement of Reactor Vessel Materials" (Ref. 5).The calculations to determine neutron fluence will be developed using the BWRVIP RAMA code methodology, which is NRC approved and meets the intent of RG 1.190, "Calculational and Dosimetry Methods for Determining Pressure Vessel Neutron Fluence" (Ref. 11). See FSAR Section 4.1.4.5 for determining fluence (Ref. 12).(continued)

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-UNIT I1SIB3449Rvso TS / B 3.4-49 Revision 3 Rev. 4 RCS P/T" Limits B 3.4.10 BASES BACKGROUND (continued)

The P/T limit curves are composite curves established by superimposing limits derived from stress analyses of those portions of the reactor vessel and head that are the most restrictive.

At any specific pressure, temperature, and temperature rate of change, one location within the reactor vessel will dictate the most restrictive limit. Across the span of the P/T limit curves, different locations are more restrictive, and, thus, the curves are composites of the most restrictive regions.The heatup curve used to develop the P/T limit curve composite represents a different set of restrictions than the cooldown curve used to develop the P/T limit curve composite because the directions of the thermal gradients through the vessel-wall are reversed.

The thermal gradient-reversal-alters the location of the tensile stress between the outer and inner walls.The criticality limits include the Reference I requirement that they be at least 40°F above the heatup curve or the cooldown curve and not lower than the minimum permissible temperature for the inservice leakage and hydrostatic testing.The consequence of violating the LCO limits is that the RCS has been operated under conditions that can result in brittle failure of the RCPB, possibly leading to a nonisolable leak or loss of coolant accident.

In the event these limits are exceeded, an evaluation must be performed to determine the effect on the structural integrity of the RCPB components.

ASME Code,Section XI, Appendix E (Ref. 6), provides a recommended methodology for evaluating an operating event that causes an excursion outside the limits.APPLICABLE SAFETY ANALYSES The P/l" limits are not derived from Design Basis Accident (DBA) analyses.They are prescribed during normal operation to avoid encountering pressure, temperature, and temperature rate of change conditions that might cause undetected flaws to propagate and cause nonductile failure of the RCPB, a condition that is unanalyzed.

Reference 7 establishes the methodology for determining the P/l" limits. Since the P/T limits are not derived from any DBA, there are no acceptance limits related to the P/T limits. Rather, the P/T limits are acceptance limits themselves since they preclude operation in an unanalyzed condition.

RCS P/T limits satisfy Criterion 2 of the NRC Policy Statement (Ref. 8).(continued)

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-UNIT 1 SIB3450Rvso TS / B 3.4-50 Revision 1 Rev. 4 RCS P/T Limits 8 3.4.10 BASES APPLICABLE The Effective Full Power Years (EFPY) shown on the curves are SAFETY approximations of the ratio of the energy that has been and is anticipated to ANALYSES be generated in a year to the energy that could have been generated if the (continued) unit ran at original thermal power rating of 3293 MWT for the entire year.These values are based on fluence limits that are not to be exceeded.LCO The elements of this LCO are: a. RCS pressure and temperature are to the right of the applicable curves specified in Figures 3.4.10-1 through 3.4.10-3 and within the applicable heat-up or cool down rate specified in SR 3.4.10.1 during RCS heatup, cooldown, and inservice leak and hYdrostatic testing;b._ The temperature difference between the reactorivessel bottom~he~ad coolant and the reactor pressure vessel (RPV) coolant is _< 145 0 F during recirculation pump startup, and during increases in THERMAL POWER or loop flow while operating at low THERMAL POWER or loop flow;c. The temperature difference between the reactor coolant in the respective recirculation loop and in the reactor vessel is < 50°F during recirculation pump startup, and during increases in THERMAL POWER or loop flow while operating at low THERMAL POWER or loop flow;d. RCS pressure and temperature are to the right of the criticality limits specified in Figure 3.4.10-3 prior to achieving criticality; and e. The reactor vessel flange and the head flange temperatures are > 70°F when tensioning the reactor vessel head bolting studs.These limits define allowable operating regions and permit a large number of operating cycles while also providing a wide margin to nonductile failure.The P/T limit composite curves are calculated using the worst case of material properties, stresses, and temperature change rates anticipated under all heatup and cooldown conditions.

The design calculations account for the reactor coolant fluid temperature impact on the inner wall of the vessel and the temperature gradients through the vessel wall. Because these fluid temperatures drive the vessel wall temperature gradient, monitoring reactor coolant temperature provides a conservative method of ensuring the P/T limits are not exceeded.

Proper monitoring of vessel temperatures to assure compliance with brittle fracture temperature limits and vessel thermal stress limits during normal heatup and cooldown, and.during inservice leakage and hydrostatic testing, is established in PPL Calculation EC-062-0573 (Ref. 9). For P/T curves A, B, and C, the bottom head drain line coolant temperature should be monitored and maintained to the right of the most limiting curve.(continued)

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-UNIT 1 S/B3451Rvso TS / B 3.4-51 Revision 3 Rev. 4 RCS P/T Limits B 3.4.10 BASES LCO (continued)

Curve A must be used for any ASME Section III Design Hydrostatic Tests performed at unsaturated reactor conditions.

Curve A may also be used for ASME Section XI inservice leakage and hydrostatic testing when heatup and cooldown rates can be limited to 20°F in a one-hour period.Curve A is based on pressure stresses only. Thermal stresses are assumed to be insignificant.

Therefore, heatup and cooldown rates are limited to 20°F in a one-hour period when using Curve A to ensure minimal thermal stresses.

The recirculation loop suction line temperatures should be monitored to determine the temperature change rate.Curves B and C are to be used for non-nuclear and nuclear heatup and cooldown, respectively.

In addition, Curve B may be used for ASME Section Xl leakage and hydrostatic_

testing, but not for ASME Section III Design Hydrostatic Tests performed at unsaturated reactor conditions.

Heatup and cooldown rates are limited to 1 00°F in a one-hour period when using Curves B and C. This limits the thermal gradient through the vessel wall, which is used to calculate the thermal stresses in the vessel wall. Thus, the LCO for the rate of coolant temperature change limits the thermal stresses and ensures the validity of the P/T curves. The vessel belt-line fracture analysis assumes a l0 0°F/hr coolant heatup or cooldown rate in the beitline area. The 100°F limit in a one-hour period applies to the coolant in the beltline region, and takes into account the thermal inertia of the vessel wall. Steam dome saturation temperature (TsAT), as derived from steam dome pressure, should be monitored to determine the beltline temperature change rate at temperatures above 212°F. At temperatures below 212°F, the recirculation loop suction line temperatures should be monitored.

During heatups and cooldowns, the reactor vessel could experience a vacuum (negative pressure) at low temperatures (unsaturated conditions) and low rates of temperature change. Under a vacuum, the vessel wall would experience a uniform compressive loading, which would counteract the tensile stress due to any thermal gradients through the vessel wall. To ensure the margin to brittle fracture is no less than at any other pressure, Curves A, B, and C require a minimum vessel metal temperature of 70°F when the reactor vessel is at a negative pressure.(continued)

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-UNIT I1Sl .-2Rvso TS / B 3.4-52 Revision 3 Rev. 4 RCS PIT Limits B] 3.4.10 BASES LCO (continued)

Violation of the limits places the reactor vessel outside of the bounds of the stress analyses and can increase stresses in other RCS components.

The consequences depend on several factors, as follows: a. The severity of the departure from the allowable operating pressure temperature regime or the severity of the rate of change of temperature;

b. The length of time the limits were violated (longer violations allow the temperature gradient in the thick vessel walls to become more pronounced);

and c. The existences, sizes, and orientations of flaws in the vessel material.APPLICABILITY The potential for violating a P/T limit exists at all times. For example, PIT limit violations could result from ambient temperature conditions that result in the reactor vessel metal temperature being less than the minimum allowed temperature for boltup. Therefore, this LCO is applicable even when fuel is not loaded in the core.ACTIONS A.1 and A.2*1 Operation outside the PIT limits while in MODES 1, 2, and 3 must be corrected so that the RCPB is retumed to a condition that has been verified by stress analyses.The 30 minute Completion Time reflects the urgency of restoring the parameters to within the analyzed range. Most violations will not be severe, and the activity can be accomplished in this time in a controlled manner.B]esides restoring operation within limits, an evaluation is required to determine if RCS operation can continue.

The evaluation must verify the RCPB integrity remains acceptable and must be completed if continued operation is desired. Several methods may be used, including comparison with pre-analyzed transients in the stress analyses, new analyses, or inspection of the components.(continued)

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-UNIT I TS / B 3.4-52a Rvso Revision 0 Rev. 4 RCS P/T- Limits B 3.4.10 BASES ACTIONS A.1I and A.2. (continued)

ASME Code, Section Xl, Appendix E (Ref. 6), may be used to support the evaluation.

However, its use is restricted to evaluation of the vessel beltline.The 72 hour8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months Completion Time is reasonable to accomplish the evaluation of a mild violation.

More severe violations may require special, event specific stress analyses or inspections.

A favorable evaluation must be completed if continued operation is desired.Condition A is modified by a Note requiring Required Action A.2 be completed whenever the Condition is entered. The Note emphasizes the need to perforrm the evaluation of the effects of the excursion Outside the-- --- -- -allowable alone per Required Action A. 1 is-insufficient because higher than analyzed stresses may have occurred and may have affected the RCPB integrity.

B.1I and B.2 If a Required Action and associated Completion Time of Condition A are not met, the plant must be placed in a lower MODE because either the RCS remained in an unacceptable P/T region for an extended period of increased stress, or a sufficiently severe event caused entry into an unacceptable region. Either possibility indicates a need for more careful examination of the event, best accomplished with the RCS at reduced pressure and temperature.

With the reduced pressure and temperature conditions, the possibility of propagation of undetected flaws is decreased.(continued)

SUSQUEHANNA -UNIT1IT .-3Rvso TS ! B 3.4-53 Revision 2 Rev. 4 RCS P/T Limits B 3.4.10 BASES ACTIONS B.1 and B.2 (continued)

Pressure and temperature are reduced by placing the plant in at least MODE 3 within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in MODE 4 within 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months . The allowed Completion Times are reasonable, based on operating experience, to reach the required plant conditions from full power conditions in an orderly manner and without challenging plant systems.C.1 and C.2 Operation outside the P/T limits in other than MODES 1, 2, and 3 (including defueled conditions) must be corrected so that the RCPB is returned to a condition that-has-been verified by stress analyses.

The Required Action must be initiated without delay and continued until the limits are restored.Besides restoring the P/T limit parameters to within limits, an evaluation is required to determine if RCS operation is allowed. This evaluation must verify that the RCPB integrity is acceptable and must be completed before approaching criticality or heating up to > 200°F. Several methods may be used, including comparison with pre-.analyzed transients, new analyses, or inspection of the components.

ASME Code,Section XI, Appendix E (Ref. 6), may be used to support the evaluation; however, its use is restricted to evaluation of the beltiine.SURVEILLANCE SR 3.4.10.1 REQUIREMENTS Verification that operation is within limits (i.e., to the right of the applicable curves in Figures 3.4.10-1 through 3.4.10-3) is required every 30 minutes when RCS pressure and temperature conditions are undergoing planned changes. This Frequency is considered reasonable in view of the control room indication available to monitor RCS status. Also, since temperature rate of change limits are specified in hourly increments, 30 minutes permits a reasonable time for assessment and correction of minor deviations.

Surveillance for heatup, cooldown, or inservice leakage and hydrostatic testing may be discontinued when the criteria given in the relevant plant procedure for ending the activity are satisfied.

This SR has been modified with a Note that requires this Surveillance to be performed only during system heatup and cooldown operations and inservice leakage and hydrostatic testing.(continued)

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-UNIT 1 SIB3454Rvso TS / B 3.4-54 Revision 2 Rev. 4 RCS P/T Limits B 3.4.10 BASES SURVEILLANCE SR 3.4.10.1 (continued)

REQUIREMENTS Notes to the acceptance criteria for heatup and cooldown rates ensure that more restrictive limits are applicable when the P/T limits associated with hydrostatic and inservice testing are being applied.SR 3.4.10.2 A separate limit is used when the reactor is approaching criticality.

Consequently, the RCS pressure and temperature must be verified within the appropriate limits (i.e., to the right of the criticality curve in--Figure 3.4:10-3)-

before withdrawing~

control rods that will make the-reactor critical.Performing the Surveillance within 15 minutes before control rod withdrawal for the purpose of achieving criticality provides adequate assurance that the limits will not be exceeded between the time of the Surveillance and the time of reactor criticality.

Although no Surveillance Frequency is specified, the requirements of SR 3.4.10.2 must be met at all times when the reactor is critical.SR 3.4.10.3 and SR 3.4.10.4 Differential temperatures within the applicable limits ensure that thermal stresses resulting from the startup of an idle recirculation pump will not exceed design allowances.

In addition, compliance with these limits ensures that the assumptions of the analysis for the startup of an idle recirculation loop (Ref. 10) are satisfied.

Performing the Surveillance within 15 minutes before starting the idle recirculation pump provides adequate assurance that the limits will not be exceeded between the time of the Surveillance and the time of the idle pump start.An acceptable means of demonstrating compliance with the temperature differential requirement in SR 3.4.10.4 is to compare the temperatures of the operating recirculation loop and the idle loop. If both loops are idle, compare the temperature difference between the reactor coolant within the idle loop to be started and coolant in the reactor vessel.(continued)

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-UNIT I1SIB3455Rvso TS / B 3.4-55 Revision 2 Rev. 4 RCS P/T Limits B 3.4.10 BASES SURVEILLANCE SR 3.4.10.3 and SR 3.4.10.4 (continued)

REQUIREMENTS SR 3.4.10.3 has been modified by a Note that requires the Surveillance to be performed only in MODES 1, 2, 3, and 4. In MODE 5, the overall stress on limiting components is lower. Therefore, AT limits are not required.

The Note also states the SR is only required to be met during a recirculation pump start-up, because this is when the stresses occur.SR 3.4.10.5 and SR 3.4.10.6 Differential temperatures within the applicable limits ensure that thermal--stres-es resultingg from increases irn-THERMAL POWER or recirc~lation loop flow during single recirculation loop operation will not exceed design allowances.

Performing the Surveillance within 15 minutes before beginning such an increase in power or flow rate provides adequate assurance that the limits will not be exceeded between the time of the Surveillance and the time of the change in operation.

An acceptable means of demonstrating compliance with the temperature differential requirement in SR 3.4.10.6 is to compare the temperatures of the operating recirculation loop and the idle loop.Plant specific startup test data has determined that the bottom head is not subject to temperature stratification at power levels > 27% of RTP and with single loop flow rate _>21,320 gpm (50% of rated loop flow). Therefore, SR 3.4.10.5 and SR 3.4.10.6 have been modified by a Note that requires the Surveillance to be met only under these conditions.

The Note for SR 3.4.10.6 further limits the requirement for this Surveillance to exclude comparison of the idle loop temperature if the idle loop is isolated from the RPV since the water in the loop cannot be introduced into the remainder of the. Reactor Coolant System.SR 3.4.10.7.

SR 3.4.10.8, and SR 3.4.10.9 Limits on the reactor vessel flange and head flange temperatures are generally bounded by the other P/T limits during system heatup and cooldown.

However, operations approaching MODE 4 from MODE 5 and in MODE 4 with RCS temperature less than or equal to certain specified values require assurance that these temperatures meet the LCO limits.(continued)

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-UNIT 1 S/B3456Rvso TS / B 3.4-56 Revision 2 Rev. 4 RCS P/T Limits B 3.4.10 BASES SURVEILLANCE REQUIREMENTS SR 3.4.10.7, SR 3.4.10.8, and SR 3.4.10.9 (continued)

The flange temperatures must be verified to be above the limits 30 minutes before and while tensioning the vessel head bolting studs to ensure that once the head is tensioned the limits are satisfied.

When in MODE 4 with RCS temperature

< 80°F, 30 minute checks of the flange temperatures are required because of the reduced margin to the limits. When in MODE 4 with RCS temperature

< 1 00°F, monitoring of the flange temperature is required every 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months to ensure the temperature is within the specified limits.The 30 minute Frequency reflects the urgency of maintaining the temperatures-within limits, and also limits the time that the temperature limits could be exceeded.

The 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Frequency is reasonable based on the rate of temperature change possible at these temperatures.

REFERENCES

1. 10 CFR 50, Appendix G.2. ASME, Boiler and Pressure Vessel Code,Section XI, Appendix G.3. ASTM E 185-73.4. 10 CFR 50, Appendix H.5. Regulatory Guide 1.99, Revision 2, May 1988.6. ASME, Boiler and Pressure Vessel Code, Section Xl, Appendix E.(continued)

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-UNIT 1 T .-7Rvso TS / B 3.4-57 Revision 4 Rev. 4 RCS P/T Limits B 3.4.10 BASES REFERENCES

7. Licensed Topical Reports: (continued)

a. Structural Integrity Associates Report No. SlR-05-044, Revision 1-A,"Pressure-Temperature Limits Report Methodology for Boiling Water Reactors," June 2013.b. Structural Integrity Associates Report No. 0900876.401, Revision 0-A, "Linear Elastic Fracture Mechanics Evaluation of GE BWR Water Level Instrument Nozzles for Pressure-Temperature Curve Evaluations," May 2013.8. Final Policy Statement on Technical Specifications Improvements,--------July-22, -1993 (58 FR 39132). --- .......-9. PPL Calculation EC-062-0573, "Study to Support the Bases Section of Technical Specification 3.4.10." 10. FSAR, Section 15.4.4.11. Regulatory Guide 1.190, March 2001.12. ESAR, Section 4.1.4.5.SUSQUEHANNA

-UNIT I1SIB345aRvso TS / B 3.4-57a Revision 0 Nov. 05, 2015 Page 1 of 2 MANUAL HARD COPY DISTRIBUTION DOCUMENT TRANSMITTAL 2015-44473 USER INFORMATION: