ML062860264

Susquehanna - Revisions to Technical Specifications Bases Unit 2 Manual

ML062860264
Person / Time
Site:	Susquehanna
Issue date:	10/02/2006
From:	Susquehanna
To:	Gerlach R M Document Control Desk, Office of Nuclear Reactor Regulation
References
028401
Download: ML062860264 (27)

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Oct. 02, 2006 Page 1 of 2 MANUAL HARD COPY DISTRIBUTION DOCUMENT TRANSMITTAL 2006-41791 USER INFORMATION:

GERLACH*ROSE M EMPL#:028401 CA#: 0363 Address: NUCSA2 Phone#: 254-3194 TRANSMITTAL INFORMATION:

TO: GERLACH*ROSE M 10/02/2006 LOCATION:

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

WHEN REPLACING THIS MATERIAL IN YOUR HARDCOPY MANUAL, ENSURE THE UPDATE DOCUMENT ID IS THE SAME DOCUMENT ID YOU'RE REMOVING FROM YOUR MANUAL. TOOLS FROM THE HUMAN PERFORMANCE TOOL BAG SHOULD BE UTILIZED TO ELIMINATE THE CHANCE OF ERRORS.ATTENTION: "REPLACE" directions do not affect the Table of Contents, Therefore no TOC will be issued with the updated material.TSB2 -TECHNICAL SPECIFICATIONS BASES UNIT 2 MANUAL REMOVE MANUAL TABLE OF CONTENTS DATE: 09/26/2006 ADD MANUAL TABLE OF CONTENTS DATE: 09/29/2006 CATEGORY:

DOCUMENTS TYPE: TSB2 A60t Oct. 02, 2006 Page 2 of 2 ID: TEXT 3.1.4 REMOVE: REV:2 ADD: REV: 3 CATEGORY: ID: TEXT REMOVE: DOCUMENTS TYPE: TSB2 LOES REV:75 ADD: REV: 76 CATEGORY: ID: TEXT REMOVE: DOCUMENTS TYPE: TSB2 TOC REV:8 ADD: REV: 9 ANY DISCREPANCIES WITH THE MATERIAL PROVIDED, CONTACT DCS @ X3107 OR X3136 FOR ASSISTANCE.

UPDATES FOR HARDCOPY MANUALS WILL BE DISTRIBUTED WITHIN 5 DAYS IN ACCORDANCE WITH DEPARTMENT PROCEDURES.

PLEASE MAKE ALL CHANGES AND ACKNOWLEDGE COMPLETE IN YOUR NIMS INBOX UPON COMPLETION OF UPDATES. FOR ELECTRONIC MANUAL USERS, ELECTRONICALLY REVIEW THE APPROPRIATE DOCUMENTS AND ACKNOWLEDGE COMPLETE IN YOUR NIMS INBOX.

SSES MANUAL' Manual Name: TSB2-~~ual Title: TECHNICAL SPECIFICATIONS BASES UNIT 2 MANUAL Table Of Contents Issue Date: 09/29/2006 Procedure Name Rev TEXT LOES 76 Title: LIST OF EFFECTIVE SECTIONS Issue Date 09/29/2006 Change ID Change Number TEXT TOC Title: TABLE OF CONTENTS 9 09/29/2006 TEXT 2.1.1 1 Title: SAFETY LIMITS (SLS) REACTOR 10/27/2004 CORE SLS/TEXT 2.1.2 Title: SAFETY LIMITS (SLS)TEXT 3.0 Title: LIMITING CONDITION 0 11/18/2002 REACTOR COOLANT SYSTEM (RCS), PRESSURE SL 1 04/18/2005 FOR OPERATION' (LCO) APPLICABILITY TEXT 3.1.1 Title: REACTIVITY TEXT 3.1.2 Title: REACTIVITY 1 7" 03724/2005 CONTROL SYSTEMS SHUTDOWN MARGIN (SDM).0 11/18/2002 CONTROL SYSTEMS REACTIVITY ANOMALIES TEXT 3.1.3 1 07/06/2005 Title: REACTIVITY CONTROL SYSTEMS CONTROL ROD OPERABILITY TEXT 3.1.4 Title: REACTIVITY TEXT 3.1.5 Title: REACTIVITY TEXT 3.1.6 Title: REACTIVITY 3 09/29/2006 CONTROL SYSTEMS CONTROL ROD SCRAM TIMES 1 07/06/2005 CONTROL SYSTEMS CONTROL ROD SCRAM ACCUMULATORS 2 03/24/2005 CONTROL SYSTEMS ROD PATTERN CONTROL Pagel of 8 Report Date: 09/29/06 Page I of 8 Report Date: 09/29/06 SSES MANUAL Manual Nane: TSB2-Manual Title: TECHNICAL SPECIFICATIONS BASES UNIT 2 MANUAL TEXT 3.1.7 Title: REACTIVITY CONTROL 1 08/30/2005 SYSTEMS STANDBY LIQUID CONTROL (SLC) SYSTEM TEXT 3.1.8 1 10/19/2005 Title: REACTIVITY CONTROL SYSTEMS SCRAM DISCHARGE VOLUME (SDV) VENT AND DRAIN VALVES TEXT 3.2.1 Title: POWER DISTRIBUTION 2 10/05/2005 LIMITS AVERAGE PLANAR LINEAR HEAT GENERATION RATE (APLHGR)TEXT 3.2.2 1 .03/24/2005 Title: POWER DISTRIBUTION LIMITS MINIMUM CRITICAL POWER RATIO (MCPR)TEXT 3.2.3 0 11/18/2002 Title: POWER DISTRIBUTION LIMITS LINEAR HEAT GENERATION RATE LHGR TEXT 3.2.4 Title: POWER DISTRIBUTION TEXT 3.3.1.1 1 07/06/2005 LIMITS AVERAGE POWER RANGE MONITOR (APRM) GAIN AND SETPOINTS 2 07/06/2005 Title: INSTRUMENTATION REACTOR PROTECTION SYSTEM (RPS) INSTRUMENTATION TEXT 3.3.1.2 0 11/18/2002 Title: INSTRUMENTATION SOURCE RANGE MONITOR (SRM) INSTRUMENTATION TEXT 3.3.1.3 Title: OPRM INSTRUMENTATION 0 11/22/2004 TEXT 3.3.2.1 1 02/17/2005 Title: INSTRUMENTATION CONTROL ROD BLOCK INSTRUMENTATION TEXT 3.3.2.2 0 11/18/2002 Title: INSTRUMENTATION FEEDWATER

-MAIN TURBINE HIGH WATER LEVEL TRIP INSTRUMENTATION TEXT 3.3.3.1 -3 06/13/2006 Title: INSTRUMENTATION POST ACCIDENT MONITORING (PAM) INSTRUMENTATION Page 2 of 8 Report Date: 09/29/06 SSES MANUAL Manual Name: TSB2-Manual Title: TECHNICAL SPECIFICATIONS BASES UNIT 2 MANUAL TEXT 3.3.3.2 1 04/18/2005 Title: INSTRUMENTATION REMOTE SHUTDOWN SYSTEM TEXT 3.3.4.1 0 11/18/2002 Title: INSTRUMENTATION END OF CYCLE RECIRCULATION PUMP TRIP (EOC-RPT)

INSTRUMENTATION TEXT 3.3.4.2 0 11/18/2002 Title: INSTRUMENTATION ANTICIPATED TRANSIENT WITHOUT SCRAM RECIRCULATION PUMP TRIP (ATWS-RPT)

INSTRUMENTATION TEXT 3.3.5.1 Title: INSTRUMENTATION 3 07/06/2005 EMERGENCY CORE COOLING SYSTEM (ECCS) INSTRUMENTATION TEXT 3.3.5.2 0 11/18/2002 Title: INSTRUMENTATION REACTOR CORE ISOLATION COOLING (RCIC) SYSTEM INSTRUMENTATION TEXT 3.3.6.1 Title: INSTRUMENTATION 1 11/09/2004 PRIMARY CONTAINMENT ISOLATION INSTRUMENTATION TEXT 3.3.6.2 1 11/09/2004 Title: INSTRUMENTATION SECONDARY CONTAINMENT ISOLATION INSTRUMENTATION TEXT 3.3.7.1 Title: INSTRUMENTATION INSTRUMENTATION 0 11/18/2002 CONTROL ROOM EMERGENCY OUTSIDE AIR SUPPLY (CREOAS) SYSTEM TEXT 3.3.8.1 2 03/31/2006 Title: INSTRUMENTATION LOSS OF POWER (LOP) INSTRUMENTATION TEXT 3.3.8.2 Title: INSTRUMENTATION 0 11/18/2002 REACTOR PROTECTION SYSTEM (RPS) ELECTRIC POWER MONITORING TEXT 3.4.1 2 11/22/2004 Title: REACTOR COOLANT SYSTEM (RCS) RECIRCULATION LOOPS OPERATING TEXT 3.4.2 -0 11/18/2002 Title: REACTOR COOLANT SYSTEM (RCS) JET PUMPS Page3 of 8 Report Date: 09/29/06 Page 3 of 8 Report Date: 09/29/06 SSES MANUAIL Manual Name: TSB2-Manual Title: TECHNICAL SPECIFICATIONS BASES UNIT 2 MANUAL I TEXT 3.4.3 Title: REACTOR TEXT 3.4.4 Title: REACTOR TEXT 3.4.5 Title: REACTOR TEXT 3.4.6 Title: REACTOR TEXT 3.4.7 Title: REACTOR TEXT 3.4.8 Title: REACTOR 1 01/16/2006-COOLANT SYSTEM (RCS) SAFETY/RELIEF VALVES (S/RVS)0 11/18/2002 COOLANT SYSTEM (RCS) RCS OPERATIONAL LEAKAGE 1 01/16/2006 COOLANT SYSTEM (RCS) RCS PRESSURE ISOLATION VALVE (PIV) LEAKAGE 1 .COOLANT SYSTEM (RCS)04/18/2005 RCS LEAKAGE DETECTION INSTRUMENTATION 1 04/18/2005 COOLANT SYSTEM (RCS) RCS SPECIFIC ACTIVITY 1 04/18/2005 COOLANT SYSTEM (RCS) RESIDUAL HEAT REMOVAL (RHR) SHUTDOWN COOLING SYSTEM-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 0 11/18/2002 SYSTEM (RCS) RESIDUAL HEAT REMOVAL (RHR) SHUTDOWN COOLING SYSTEM 2 05/10/2006 SYSTEM (RCS) RCS PRESSURE AND TEMPERATURE (P/T) LIMITS 0 11/18/2002 SYSTEM (RCS) REACTOR STEAM DOME PRESSURE 3 01/16/2006 Title: EMERGENCY CORE COOLING SYSTEMS (ECCS) AND REACTOR CORE ISOLATION COOLING SYSTEM ECCS -OPERATING (RCIC)TEXT 3.5.2 0 11/18/2002 Title: EMERGENCY CORE COOLING SYSTEMS (ECCS) AND REACTOR CORE ISOLATION SYSTEM ECCS -SHUTDOWN TEXT 3.5.3 -1 04/18/2005 Title: EMERGENCY CORE COOLING SYSTEMS (ECCS) AND REACTOR CORE ISOLATION SYSTEM RCIC SYSTEM COOLING (RCIC)COOLING (RCIC)K- , Page4 of 8 Report Date: 09/29/06 Page 4 of 8 Report Date: 09/29/06 SSES MANUAL Manual Name: TSBZ-Manual Title: TECHNICAL SPECIFICATIONS BASES UNIT 2 MANUAL TEXT 3.6.1.1 Title: CONTAINMENT TEXT 3.6.1.2 Title: CONTAINMENT 0 11/18/2002 SYSTEMS PRIMARY CONTAINMENT 0 11/18/2002 SYSTEMS PRIMARY CONTAINMENT AIR LOCK TEXT 3.6.1.3 Title: CONTAINMENT SYSTEMS 3 12/08/2005 PRIMARY CONTAINMENT ISOLATION VALVES (PCIVS)TEXT 3.6.1.4 Title: CONTAINMENT TEXT 3.6.1.5 Title: CONTAINMENT TEXT 3.6.1.6 k 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 0 .11/18/2002 SYSTEMS CONTAINMENT PRESSURE 1 10/05/2005 DRYWELL AIR TEMPERATURE SYSTEMS 0 11/18/2002 SYSTEMS SUPPRESSION CHAMBER-TO-DRYWELL VACUUM BREAKERS 0 11/18/2002 SYSTEMS SUPPRESSION POOL AVERAGE TEMPERATURE 0 11/18/2002 SYSTEMS SUPPRESSION POOL WATER LEVEL 1 01/16/2006 SYSTEMS RESIDUAL HEAT REMOVAL (RHR) SUPPRESSION POOL COOLING 0 11/18/2002 SYSTEMS RESIDUAL HEAT REMOVAL (RHR) SUPPRESSION POOL SPRAY TEXT 3.6.3.1 2 06/13/2006 Title: CONTAINMENT SYSTEMS PRIMARY CONTAINMENT HYDROGEN RECOMBINERS TEXT 3.6.3.2 1 04/18/2005 Title: CONTAINMENT SYSTEMS DRYWELL AIR FLOW SYSTEM Page 5 of 8 Report Date: 09/29/06 Page 5 of 8 Report Date: 09/29/06 SSES MAANUAL Manual Name: TSB2-Manual Title: TECHNICAL SPECIFICATIONS BASES UNIT 2 MANUAL~~1 iý1ý1 TEXT 3.6.3.3 Title: CONTAINMENT TEXT 3.6.4.1 Title: CONTAINMENT TEXT 3.6.4.2 Title: CONTAINMENT TEXT 3.6.4.3 Title: CONTAINMENT 0 11/18/2002 SYSTEMS PRIMARY CONTAINMENT OXYGEN CONCENTRATION 6 08/08/2006 SYSTEMS SECONDARY CONTAINMENT 2 01/03/2005 SYSTEMS SECONDARY CONTAINMENT ISOLATION VALVES (I.4 09/21/2006 SYSTEMS STANDBY GAS TREATMENT (SGT) SYSTEM SCIVS)TEXT 3.7.1 Title: PLANT ULTIMP.TEXT 3.7.2 Title: PLANT TEXT 3.7.3 Title: PLANT TEXT 3.7.4 Title: PLANT TEXT 3.7.5 Title: PLANT TEXT 3.7.6 Title: PLANT TEXT 3.7.7 Title: PLANT TEXT 3.8.1 0 11/18/2002 SYSTEMS RESIDUAL HEAT REMOVAL SERVICE WATER (RHRSW) SYSTEM AND THEHEAT SINK (UHS)1 11/09/2004 SYSTEMS EMERGENCY SERVICE WATER (ESW) SYSTEM 0 11/18/2002 SYSTEMS CONTROL ROOM EMERGENCY OUTSIDE AIR SUPPLY (CREOAS) SYSTEM 0 11/18/2002 SYSTEMS CONTROL ROOM FLOOR COOLING SYSTEM 0 11/18/2002 SYSTEMS MAIN CONDENSER OFFGAS 1 01/17/2005 SYSTEMS MAIN TURBINE BYPASS SYSTEM 0 11/18/2002 SYSTEMS SPENT FUEL STORAGE POOL WATER LEVEL K-, /4 04/18/2006 Title: ELECTRICAL POWER SYSTEMS AC SOURCES -OPERATING Page6 of 8 Report Date: 09/29/06 Page 6 of 8 Report Date: 09/29/06 jSSES MANUAL Manual Name: TSB2-Manual Title: TECHNICAL SPECIFICATIONS BASES UNIT 2 MANUAL TEXT 3.8.2 Title: ELECTRICAL 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 0 11/18/2002 POWER SYSTEMS AC SOURCES -SHUTDOWN 0 11/18/2002 POWER SYSTEMS DIESEL FUEL OIL, LUBE OIL, AND STARTING AIR 1 06/13/2006 POWER SYSTEMS DC SOURCES -OPERATING 0 .11/18/2002 POWER SYSTEMS DC SOURCES -SHUTDOWN 0 11/18/2002 POWER SYSTEMS BATTERY CELL PARAMETERS 3 03/31/2006 POWER SYSTEMS DISTRIBUTION SYSTEMS -OPERATING 0 11/18/2002 POWER SYSTEMS DISTRIBUTION SYSTEMS -SHUTDOWN TEXT 3.9.1 0 11/18/2002 Title: REFUELING OPERATIONS REFUELING EQUIPMENT INTERLOCKS TEXT 3.9.2 0 11/18/2002 Title: REFUELING OPERATIONS REFUEL POSITION ONE-ROD-OUT INTERLOCK TEXT 3.9.3 0 11/18/2002 Title: REFUELING OPERATIONS CONTROL ROD POSITION TEXT 3.9.4 0 11/18/2002 Title: REFUELING OPERATIONS CONTROL ROD POSITION INDICATION TEXT 3.9.5 0 11/18/2002 Title: REFUELING OPERATIONS CONTROL ROD OPERABILITY

-REFUELING Page 7 of 8 Report Date: 09/29/06 Page 7 of 8 Report Date: 09/29/06 SSES MANUAL 46 I Manual Name: TSB2-Manual Title: TECHNICAL SPECIFICATIONS BASES UNIT 2 MANUAL TEXT 3.9.6 0 11/18/2002 Title: REFUELING OPERATIONS REACTOR PRESSURE VESSEL (RPV)TEXT 3.9.7 0 11/18/2002 Title: REFUELING OPERATIONS RESIDUAL HEAT REMOVAL (RHR) -TEXT 3.9.8 0 11/18/2002 Title: REFUELING OPERATIONS RESIDUAL HEAT REMOVAL (RHR) -WATER LEVEL HIGH WATER LEVEL 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 0 .11/18/2002 INSERVICE LEAK AND HYDROSTATIC TESTING OPERATION 0 11/18/2002 REACTOR MODE SWITCH INTERLOCK TESTING 0 11/18/2002 OPERATIONS SINGLE CONTROL ROD WITHDRAWAL

-HOT SHUTDOWN.0 11/18/2002 OPERATIONS SINGLE CONTROL ROD WITHDRAWAL

-COLD SHUTDOWN OPERATIONS OPERATIONS OPERATIONS OPERATIONS 0 11/18/2002 SINGLE CONTROL ROD DRIVE (CRD) REMOVAL -REFUELING 0 11/18/2002 MULTIPLE CONTROL ROD WITHDRAWAL

-REFUELING 1 03/24/2005 CONTROL ROD TESTING -OPERATING 1 03/24/2005 SHUTDOWN MARGIN (SDM) TEST -REFUELING PageS of 8 Report Date: 09/29/06 Page 8 of 8 Report Date: 09/29/06 SUSQUEHANNA STEAM ELECTRIC STATION LIST OF EFFECTIVE SECTIONS (TECHNICAL SPECIFICATIONS BASES)Section Title Revision TOC Table of Contents 9 B 2.0 SAFETY LIMITS BASES-Page TS / B 2.0-1 1 Page TS / B 2.0-2 2 Page TS /B 2.0-3 3 Page TS / B 2.0-4 4 Page TS / B 2.0-5 1 Pages B 2.0-6 through B 2.0-8 0 B 3.0 LCO AND SR APPLICABILITY BASES 0 Pages B 3.0-1 through B 3.0-4 0 Pages TS / B 3.0-5 through TS / B 3.0-7 1 Pages TS / B 3.0-8 through TS / B 3.0-9 " , 2 Pages TS / B 3.0-10 through TS / B 3.0-12 1' I Pages TS / B 3.0-13 through TS / B 3.0-15, , 2 Pages TS / B 3.0-16 and TS / B 3.0-17 \ ,, 0 B 3.1 REACTIVITY CONTROL BASES K Pages B 3.1-1 through B 3.1-4 .0 PageTS/B3.1-5 , e 1 Pages TS / B 3.1-6 and TS /B3.1-7 , 2 Pages B3.1-8 throughB3.-13>.

0* Page TS / B 3.1-14 < -1 1 Pages B 3.1-15 through"13 3.1-21 0 Page TS / B 3.1-22 '. 0 Page TS / B 3.1-23 , .1

\ 0 Page TS /.B3.1-25 1 Page TS Ib. 3.1-26 0 PageYTS /,,B 3.1-27 1 Page TS / B 3.1-28 2/,Pdg6,TS

'/3.1-29 1 Page 8 3.1-30 through B 3.1-33 0 Pages TS / B 3.1.34 through TS / B 3.1-36 1\Pages TS / B 3.1-37 and TS / B 3.1-38 2 Pages B 3.1-39 through B 3.1-44 0 Page TS / B 3.1-45 1 Pages B 3.1-46 and B 3.1-47 0 Pages TS / B 3.1-48 and TS / B 3.1-49 1 Page B 3.1-50 0 Page TS / B 3.1-51 1 SUSQUEHANNA

-UNIT 2 TSIB LOES-1 Revision 76 SUSQUEHANNA

-UNIT 2 TS / B LOES-1 Revision 76 SUSQUEHANNA STEAM ELECTRIC STATION LIST OF EFFECTIVE SECTIONS (TECHNICAL SPECIFICATIONS BASES)Section Title Revision B 3.2 POWER DISTRIBUTION LIMITS BASES Pages TS / B 3.2-1 and TS / B 3.2-2 1 Page TS/B3.2-3 3 Page TS / B 3.2-4 1 Pages TS / B 3.2-5 and TS / B 3.2-6 3 Page TS / B 3.2-7 2 Pages TS / B 3.2-8 and TS / B 3.2-9 3 Pages TS / B 3.2-10 through TS / B 3.2-17 1 Page TS / 3.2-18 2 Page TS / 3.2-19 1 B 3.3 INSTRUMENTATION Pages TS / B 3.3-1 through TS / B 3.3-4 1 Page TS / B 3.3-5 2 Page TS / B 3.3-6 1 Pages TS / B 3.3-7 through TS / B 3.3-12 2 Page TS / B 3.3-13 1 Page TS / B 3.3-14 2 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 2 Pages TS / B 3.3-19 through TS / B 3.3-27 1 Pages TS / B 3.3-28 through TS / B 3.3-30 2 PageTS/B3.3-31 1 Page TS / B 3.3-32 3 Page TS / B 3.3-33 2 Pages TS / B 3.3-34 through TS I B 3.3-43 Pages TS / B 3.3-43a though TS / B 3.3-43i 0 Pages TS / B 3.3-44 through TS / B 3.3-54 2 Pages B 3.3-55 through B 3.3-63 0 Pages TS / B 3.3-64 and TS I B 3.3-65 2 Page TS / B 3.3-66 4 Page TS / B 3.3-67 3 Pages TS / B 3.3-68 and TS / B 3.3.69 4 Pages TS / B 3.3-70 and TS I B 3.3-71 3 Pages TS / B 3.3-72 and TS I B 3.3-73 2 Page TS I B 3.3-74 3 Page TS / B 3.3-75 2 Pages B 3.3-75a through TS I B 3.3-75c 4 Pages B 3.3-76 and TS / B 3.3-77 0 Page TS / B 3.3-78 1 Pages B 3.3-79 through B 3.3-91 0 Pages TS / B 3.3-92 through TS / B 3.3-103 1* a.j SUSQUEHANNA

-UNIT 2 TS / B LOES-2 Revision 76 SUSQUEHANNA STEAM ELECTRIC STATION LIST OF EFFECTIVE SECTIONS (TECHNICAL SPECIFICATIONS BASES)Section Title Revision Page TS / B 3.3-104 2 Pages TS / B 3.3-105 and TS / B 3.3-106 1 Page TS / B 3.3-107 2 Page TS / B 3.3-108 1 Page TS / B 3.3-109 2 Pages TS / B 3.3-110 through TS / B 3.3-112 1 Page TS / B 3.3-113 2 Page TS / B 3.3-114 1 Page TS / 8 3.3-115 through TS / 8 3.3-118 2 Pages TS / B 3.3-119 through TS / B 3.3-120 1 Pages TS / B 3.3-121 and TS / B 3.3-122 2 Page TS / B 3.3-123 1 Page TS / B 3.3-124 2 Page TS / B 3.3-124a 0 Page TS / B 3.3-125 1 Page TS / B 3.3-126 2 Page TS / B 3.3-127 3 Page TS / B 3.3-128 2 Pages TS / B 3.3-129 through TS / B 3.3-131 1 Page TS / 8 3.3-132 2 Pages TS / B 3.3-133 and TS / B 3.3-134 1 Pages B 3.3-135 through B 3.3-137 0 Page TS / B 3.3-138 1 Pages B 3.3-139 through.B 3.3-149 0 Pages TS/B 3.3-150 through TS / B 3.3-162 1 Page TS / B 3.3-163 2 Pages TS / B 3.3-164 through TS / B 3.3-177 1 Page TS / 83.3-178 2 Page TS IB 3.3-179 3 Page TS / B 3.3-179a 2 Page TS / 83.3-180 1 Page TS / B 3.3-181 2 Pages TS / B 3.3-182 through TS / B 3.3-186 1 Pages TS / 8 3.3-187 and TS / B 3.3-188 2 Pages TS / B 3.3-189 through TS / B 3.3-191 1 Pages B 3.3-192 through B 3.3-205 0 Page TS / B 3.3-206 1 Pages B 3.3-207 through B 3.3-209 0 Pages TS / B 3.3-210 through TS / B 3.3-213 1 Pages B 3.3-214 through B 3.3-220 0 B 3.4 REACTOR COOLANT SYSTEM BASES Pages TS / B 3.4-1 and TS / B 3.4-2 1 Pages TS / B 3.4-3 through TS / B 3.4-9 3 SUSQUEHANNA

-UNIT 2 TS/B LOES-3 Revision 76 SUSQUEHANNA -UNIT 2 TS / B LOES-3 Revision 76 SUSQUEHANNA STEAM ELECTRIC STATION LIST OF EFFECTIVE SECTIONS (TECHNICAL SPECIFICATIONS BASES)Section Title Revision ,..)Pages B 3.4-10 through B 3.4-14 0 Page TS / B 3.4-15 1 Pages TS / B 3.4-16 through TS / B 3.4-18 2 Pages B 3.4-19 through B 3.4-27 0 Pages TS / B 3.4-28 and TS / B 3.4-29 1 Pages B 3.4-30 through B 3.3-31 0 Page TS / B 3.4-32 1 Pages B 3.4-33 through B 3.4-36 0 Page TS / B 3.4-37 1 Pages B 3.4-38 through B 3.4-40 0 Page TS / B 3.4-41 1 Pages B 3.4-42 through B 3.4-48 0 Page TS / B 3.4-49 3 Pages TS / B 3.4-50 through TS / B 3.4-52 2 Page TS / B 3.4-53 1 Pages TS / B 3.4-54 and TS / B 3.4-55 2 Page TS / B 3.4-56 1 Page TS / B 3.4-57 2 Pages TS / B 3.4-58 through TS / B 3.4-60 1 B 3.5 ECCS AND RCIC BASES Pages TS / B 3.5-1 and TS / B 3.5-2 1 Pages TS / B 3.5-3 through TS / B 3.5-6 2 Pages TS / B 3.5-7 through TS /B 3.5-10 1 Pages TS I B 3.5-11 and TS / B 3.5-12 2 Pages TS / B 3.6-13 and TS / B 3.5-14 1 Pages TS / B 3.5-15 and TS / B.3.5-16 2 Page TS / B 3.5-17 3 Page TS / B 3.5-18 1 Pages B 3.5-19 through B 3.5-24 0 Pages TS I B 3.5-25 through TS / B 3.5-27 1 Pages B 3.5-28 through B 3.5-31 0 B 3.6 CONTAINMENT SYSTEMS BASES Page TS / B 3.6-1 2 Page TS / B 3.6-1a 3 Pages TS / B 3.6-2 through TS / B 3.6-5 2 Page TS / B 3.6-6 3 Pages TS / B 3.6-6a and TS / B 3.6-6b 2 Page TS / B 3.6-6c 0 Pages B 3.6-7 through B 3.6-14 0 Page TS / B 3.6-15 3 Pages TS / B 3.6-15a and TS / B 3.6-15b 0 SUSQUEHANNA

-UNIT 2 TS / B LOES-4 Revision 76 SUSQUEHANNA STEAM ELECTRIC STATION LIST OF EFFECTIVE SECTIONS (TECHNICAL SPECIFICATIONS BASES)Section Title Revision Page TS / 8 3.6-16 1 Page TS / B 3.6-17 2 Page TS / B 3.6-17a 0 Pages TS / B 3.6-18 and TS /B 3.6-19 1 Page TS / B 3.6-20 2 Page TS / B 3.6-21 3 Pages TS / B 3.6-21a and TS / B 3.6-21b 0 Pages TS / B 3.6-22 and TS / B 3.6-23 2 Pages TS / B 3.6-24 and TS / B 3.6-25 1 Page TS / B 3.6-26 2 Page TS / B 3.6-27 3 Page TS /B 3.6-28 6 Page TS B 3.6-29 3 Page TS / B 3.6-29a 0 Page TS /B 3.6-30 2 Page TS B 3.6-31 3 Page TS / B 3.6-32 1 Page TS / B 3.6-33 2 Page TS / B 3.6-34 1 Pages TS / B 3.6-35 through TS I B 3.6-37 2 Page TS / B 3.6-38 1 Page TS / B 3.6-39 5 Pages B 3.6-40 through B 3.6-42 0 Pages TS / B 3.6-43 and TS / B 3.6-44 1 Page TS / B 3.6-45 2 Pages TS / B 3.6-46 through TS / B 3.6-50 1 Page TS / B 3.6-51 2 Pages B 3.6-52 through B 3.6-62 0 Pages TS./ B 3.6-63 and TS / B 3.6-64 1 Pages B 3.6-65 through B 3.6-68 0 Pages B 3.6-69 through B 3.6-71 1 Page TS / B 3.6-72 2 Pages TS / B 3.6-73 through TS / B 3.6-74 1 Pages B 3.6-75 and B 3.6-76 0 Page TS / B 3.6-77 1 Pages B 3.6-78 through B 3.6-82 0 Page TS / B 3.6-83 3 Page TS / B 3.6-84 2 Page TS / B 3.6-85 4 Page TS / B 3.6-86 through TS / B 3.6-87a 2 Page TS / B 3.6-88 3 Page TS / B 3.6-89 2 Page TS / B 3.3-90 3 Pages TS / B 3.6-91 through TS / B 3.6-95 1 SUSQUEHANNA

-UNIT 2 TS/B LOES-5 Revision 76 SUSQUEHANNA

-UNIT 2 TS / B LOES-5 Revision 76 SUSQUEHANNA STEAM ELECTRIC STATION LIST OF EFFECTIVE SECTIONS (TECHNICAL SPECIFICATIONS BASES)Section Title Revision Page TS / B 3.6-96 2 Pages TS / B 3.6-97 and TS / B 3.6-98 1 Page TS / B 3.6-99 2 Page TS / B 3.6-99a 0 Pages TS / B 3.6-100 and TS / B 3.6-101 1 Pages TS / B 3.6-102 and TS / B 3.6-103 2 Page TS / B 3.6-104 3 Page TS / B 3.6-105 2 Page TS / B 3.6-106 3 B 3.7 PLANT SYSTEMS BASES Pages TS / B 3.7-1 through TS / B 3.7-6 2 Page TS / B 3.7-6a 2 Pages TS / B 3.7-6b and TS / B 3.7-6c 0 Page TS / B 3.7-7 2 Page TS / B 3.7-8 1 Pages B 3.7-9 through B 3.7-11 0 Pages TS / B 3.7-12 and TS / B 3.7-13 1 Pages TS / B 3.7-14 through TS / B 3.7-18 2 Page TS / B 3.7-18a 0 Pages TS / B 3.7-19 through TS / B 3.7-26 1 Pages B 3.7-24 through B 3.7-26 0 Pages TS / B 3.7-27 through TS I B 3.7-29 2 Page TS / B 3.7-30 1 Pages B 3.7-31 through B 3.7-33 0 B 3.8' ELECTRICAL POWER SYSTEMS BASES Pages B 3.8-1 through 8 3.8-3 0 Page TS / B 3.8-4 1 Pages TS / B 3.8-4a and TS / B 3.8-4b 0 Pages TS / B 3.8-5 and Page TS / B 3.8-6 1 Pages B 3.8-7 and B 3.8-8 0 Page TS / B 3.8-9 2 Pages TS / B 3.8-10 and TS / B 3.8-11 1 Pages B 3.8-12 through B 3.8-18 0 Page TS / B 3.8-19 1 Pages B 3.8-20 through B 3.8-22 0 Page TS / B 3.8-23 1 Page B 3.8-24 0 Pages TS / B 3.8-25 and TS / B 3.8-26 1 Pages B 3.8-27 through B 3.8-37 0 SUSQUEHANNA -UNIT 2 TS / B LOES-6 Revision 76 SUSQUEHANNA STEAM ELECTRIC STATION LIST OF EFFECTIVE SECTIONS (TECHNICAL SPECIFICATIONS BASES)Section Title Revision Page TS / B 3.8-38 1 Pages TS / B 3.8-39 through TS / B 3.8-55 0 Pages TS / B 3.8-56 through TS / B 3.8-64 1 Page TS / B 3.8-65 2 Page TS / B 3.8-66 3 Pages TS / B 3.8-67 and TS / B 3.8-68 2 Page TS / B 3.8-69 3 Pages B 3.8-70 through B 3.8-85 0 Page TS / B 3.8-86 1 Page TS / B 3.8-87 2 Pages TS / B 3.8-88 through TS / B 3.8-93 1 Pages B 3.8-94 through B 3.8-99 0 B 3.9 REFUELING OPERATIONS BASES Pages TS / B 3.9-1 and TS / B 3.9-2 1 Page TS / B 3.9-2a 1 Pages TS / B 3.9-3 and TS / B 3.9-4 1 Pages B 3.9-5 through B 3.9-30 0 B 3.10 SPECIAL OPERATIONS BASES Page TS / B 3.10-1 1 Pages B 3.10-2 through B 3.10-32 0 Page TS / B 3.10-33 2 Pages B 3.10-34 through.B 3.10-38 0 Page TS I B 3.10-39 2 TSB2 Text LOES.doc 9/21/2006 SUSQUEHANNA

-UNIT 2 TSIB LOES-7 Revision 76 SUSQUEHANNA

-UNIT 2 TS / B LOES-7 Revision 76 TABLE OF CONTENTS (TECHNICAL SPECIFICATIONS BASES)B2.0 SAFETY LIMITS (SLs) ............................................................................

TS/12.0-1 B2.1.1 Reactor Core SLs .....................................................................

TS/B 2.0-1 B2.1.2 Reactor Coolant System (RCS) Pressure SL .................................

B2.0-6 B3.0 LIMITING CONDITION FOR OPERATION (LCO) APPLICABILITY

..............

B3.0-1 B3.0 SURVEILLANCE REQUIREMENT (SR) APPLICABILITY

......................

TS/B3.0-10 B3.1 REACTIVITY CONTROL SYSTEMS ....................................................

B3.1-1 B3.1.1 Shutdown Margin (SDM) ................................................................

B3.1-1 B3.1.2 Reactivity Anomalies

..............................

B3.1-8 B3.1.3 Control Rod OPERABILITY

............................................................

B3.1-13 B3.1.4 Control Rod Scram Times ........................................................

TS/B3.1-22 B3.1.5 Control Rod Scram Accumulators

............................................

TS/B3.1-29 B3.1.6 Rod Pattern Control ..................................................................

TS/B3.1-34 83.1.7 Standby Liquid Control (SLC) System ............................................

B3.1-39 B3.1.8 Scram Discharge Volume (SDV) Vent and Drain Valves ................

B3.1-47 B3.2 POWER DISTRIBUTION LIMITS ..................................................

TS/B3.2-1 B3.2.1 Average Planar Linear Heat Generation Rate (APLHGR) ........ TS/B3.2-1 B3.2.2 Minimum Critical Power Ratio (MCPR) .....................................

TS/B3.2-5 B3.2.3 Linear Heat Generation Rate (LHGR) .......................................

TS/B3.2-10 B3.2.4 Average Power Range Monitor (APRM) Gain and Setpoints

.....................................................................

TS/B3.2-14 B3.3 INSTRUMENTATION

....................................................................

TS/B3.3-1 B3.3.1.1 Reactor Protection System (RPS) Instrumentation

...................

TS/B3.3-1 B3.3.1.2 Source Range Monitor (SRM) Instrumentation

.........................

TS/B3.3-35 B3.3.1.3 Oscillation Power Range Monitor ...................

TS/B3.3-43a B3.3.2.1 Control Rod Block Instrumentation

........................

...................

TS/B3.3-44 B3.3.2.2 Feedwater

-Main Turbine High Water Level Trip Instrum entation .........................................................................

B3.3-55 B3.3.3.1 Post Accident Monitoring (PAM) Instrumentation

.....................

TS/B3.3-64 B3.3.3.2 Remote Shutdown System .............................................................

B3.3-76 B3.3.4.1 End of Cycle Recirculation Pump Trip (EOC-RPT)Instrum entation .........................................................................

B3.3-81 B3.3.4.2 Anticipated Transient Without Scram Recirculation Pump Trip (ATWS-RPT)

Instrumentation

..................................

B3.3-92 B3.3.5.1 Emergency Core Cooling System (ECCS)Instrum entation ...................................................................

TS/B3.3-101 B3.3.5.2 Reactor Core Isolation Cooling (RCIC) System Instrum entation .........................................................................

8 3.3-135 B3.3.6.1 Primary Containment Isolation Instrumentation

.............

B3.3-147 B3.3.6.2 Secondary Containment Isolation Instrumentation

...................

TS/83.3-180 B3.3.7.1 Control Room Emergency Outside Air Supply (CREOAS)System Instrumentation

...........................................................

B3.3-192 (continued)

SUSQUEHANNA

-UNIT 2 TS / B TOC -1 Revision 9 TABLE OF CONTENTS (TECHNICAL SPECIFICATIONS BASES)B3.3 INSTRUMENTATION (continued)

B3.3.8.1 Loss of Power (LOP) Instrumentation

.......................................

TS/B3.3-206 B3.3.8.2 Reactor Protection System (RPS) Electric Power M onitoring

................................................................................

B3.3-214 B3.4 REACTOR COOLANT SYSTEM (RCS) .........................................

TS/B3.4-1 B3.4.1 Recirculation Loops Operating

.................................................

TS/B3.4-1 B3.4.2 Jet Pumps ......................................................................................

B3.4-10 B3.4.3 Safety/Relief Valves (S/RVs) ....................................................

TS/B3.4-15 83.4.4 RCS Operational LEAKAGE .........................

83.4-19 B3.4.5 RCS Pressure Isolation Valve (PIV) Leakage .................................

B3.4-24 B3.4.6 RCS Leakage Detection Instrumentation

........................................

B3.4-30 B3.4.7 RCS Specific Activity ......................................................................

B3.4-35 B3.4.8 Residual Heat Removal (RHR) Shutdown Cooling System -Hot Shutdown ...........................................................

B3.4-39 B3.4.9 Residual Heat Removal (RHR) Shutdown Cooling System -Cold Shutdown .........................

B3.4-44 B3.4.10 RCS Pressure and Temperature (P/T) Limits .........................

TS/13.4-49 B3.4.11 Reactor Steam Dome Pressure TS/B3.4-58 83.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) AND REACTOR CORE ISOLATION COOLING (RCIC) SYSTEM ............................

TSIB3.5-1 B3.5.1 ECCS -Operating

...................................................................

TS/B3.5-1 B3.5.2 ECCS -Shutdown ........................................................................

B3.5-19 B3.5.3 RCIC System ...............

.......................................................

TS/B3.5-25 B3.6 CONTAINMENT SYSTEMS ...........................................................

TS/B3.6-1 B3.6.1..1 Primary Containment

...........................

TS/B3.6-1 B3.6.1.2 Primary Containment Air Lock ........................................................

B3.6-7 B3.6.1.3 Primary Containment Isolation Valves (PCIVs) .........................

TS/B3.6-15 B3.6.1.4 Containment Pressure ....................................................................

83.6-40 B3.6.1.5 Drywell Air Temperature

..........................................................

TS/B3.6-43 B3.6.1.6 Suppression Chamber-to-Drywell Vacuum Breakers ................

TS/B3.6-46 B3.6.2.1 Suppression Pool Average Temperature

........................................

B3.6-52 B3.6.2.2 Suppression Pool Water Level .......................................................

B3.6-58 B3.6.2.3 Residual Heat Removal (RHR) Suppression Pool C ooling .....................................................................................

B3.6-61 B3.6.2.4 Residual Heat Removal (RHR) Suppression Pool Spray ................

B3.6-65 B3.6.3.1 Not Used .................................................................................

TS/B3.6-69 B3.6.3.2 Drywell Air Flow System .................................................................

B3.6-75 B3.6.3.3 Primary Containment Oxygen Concentration

..................................

B3.6-80 B3.6.4.1 Secondary Containment

...........................................................

TS/B3.6-83 B3.6.4.2 Secondary Containment Isolation Valves (SCIVs) ....................

TS/B3.6-90 B3.6.4.3 Standby Gas Treatment (SGT) System ....................................

TS/B3.6-100 (continued)

SUSQUEHANNA

-UNIT 2 TS / B TOC -2 Revision 9 TABLE OF CONTENTS (TECHNICAL SPECIFICATIONS BASES)B3.7 PLANT SYSTEMS .........................................................................

TS/B3.7-1 B3.7.1 Residual Heat Removal Service Water (RHRSW) System and the Ultimate Heat Sink (UHS) ......................................

TS/B3.7-1 B3.7.2 Emergency Service Water (ESW) System ................................

TS/B3.7-7 B3.7.3 Control Room Emergency Outside Air Supply (CREOAS) System .............................................................

TS/B3.7-12 B3.7.4 Control Room Floor Cooling System ........................................

TS/B3.7-19 B3.7.5 Main Condenser Offgas .................................................................

B3.7-24 B3.7.6 Main Turbine Bypass System .....................

.............................

TS/B3.7-27 B3.7.7 Spent Fuel Storage Pool Water Level ...........................................

B3.7-31 B3.8 ELECTRICAL POWER SYSTEM .........................................................

83.8-1 B3.8.1 AC Sources -Operating

................................................................

B3.8-1 B3.8.2 AC Sources -Shutdown ................................................................

B3.8-39 B3.8.3 Diesel Fuel Oil, Lube Oil, and Starting Air ......................................

B3.8-47 B3.8.4 DC Sources -Operating

..........................................................

TS/B3.8-56 B3.8.5 DC Sources -Shutdown ...........................

B3.8-70 83.8.6 Battery Cell Parameters

.................................................................

B3.8-77 B3.8.7 Distribution Systems -Operating

...................................................

B3.8-84 B3.8.8 Distribution Systems -Shutdown ...................................................

B3.8-94 B3.9 REFUELING OPERATIONS

..........................................................

TS/B3.9-1 83.9.1 Refueling Equipment Interlocks

................................................

TS/B3.9-1 83.9.2 Refuel Position One-Rod-Out Interlock

..................................

B3.9-5 B3.9.3 Control Rod Position .....................................................................

B3.9-9 B3.9.4 Control Rod Position Indication

......................................................

B3.9-12 B3.9.5 Control Rod OPERABILITY

-Refueling

.........................................

B3.9-16 B3.9.6 Reactor Pressure Vessel (RPV) Water Level ..................................

B3.9-19 B3.9.7 Residual Heat Removal (RHR) -High Water Level ......................

B3.9-22 B3.9.8 Residual Heat Removal (RHR) -Low Water Level .........................

B3.9-26 83.10 SPECIAL OPERATIONS

...............................................................

TS/B3.10-1 B3.10.1 Inservice Leak and Hydrostatic Testing Operation

...................

TS/B3.10-1 B3.10.2 Reactor Mode Switch Interlock Testing ..........................................

B3.10-6 B3.10.3 Single Control Rod Withdrawal

-Hot Shutdown .............................

B3.10-11 B3.10.4 Single Control Rod Withdrawal

-Cold Shutdown ............

B3.10-16 83.10.5 Single Control Rod Drive (CRD) Removal -Refueling

...................

B3.10-21 B3.10.6 Multiple Control Rod Withdrawal

-Refueling

...............

B3.10-26 B3.10.7 Control Rod Testing -Operating

....................................................

B3.10-30 B3.10.8 SHUTDOWN MARGIN (SDM) Test- Refueling

.............................

B3.10-34 TSB2 TOC.doc 9/2012006 SUSQUEHANNA

-UNIT 2 TS/BTOC-3 Revision 9 PPL Rev. 3 Control Rod Scram Times B 3.1.4 B3.1 B 3.1.4 REACTIVITY CONTROL SYSTEMS Control Rod Scram Times BASES BACKGROUND The scram function of the Control Rod Drive (CRD) System controls reactivity changes during abnormal operational transients to ensure that specified acceptable fuel design limits are not exceeded (Ref. 1). The control rods are scrammed by positive means using hydraulic pressure exerted on the CRD piston.When a scram signal is initiated, control air is vented from the scram valves, allowing them to open by spring action. Opening the exhaust valve reduces the pressure above the main drive piston to atmospheric pressure, and opening the inlet valve applies the accumulator or reactor pressure to the bottom of the piston. Since the notches in the index tube are tapered on the lower edge, the collet fingers are forced open by cam action, allowing the index tube to move upward without restriction because of the high differential pressure across the piston. As the drive moves upward and the accumulator pressure reduces below the reactor pressure, a ball check valve opens, letting the reactor pressure complete the scram action. If the reactor pressure is low, such as during startup, the accumulator will fully insert the control rod in the required.time without assistance from reactor pressure.APPLICABLE SAFETY ANALYSES The analytical methods and assumptions used in evaluating the control rod scram function are presented in References 2, 3, and 4. The Design Basis Accident (DBA) and transient analyses assume that all of the control rods scram at a specified insertion rate. The resulting negative scram reactivity forms the basis for the determination of plant thermal limits (e.g., the MCPR). Other distributions of scram times (e.g., several control rods scramming slower than the average time with several control rods scramming faster than the average time) can also provide sufficient scram reactivity.

Surveillance of each individual control rod's scram time ensures the scram reactivity assumed in the DBA and transient analyses can be met.(continued)

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-UNIT 2 TS / B 3.1-22 Revision 0 PPL Rev. 3 Control Rod Scram Times B 3.1.4 BASES APPLICABLE SAFETY ANALYSES (continued)

The scram function of the CRD System protects the MCPR Safety Limit (SL) (see Bases for SL 2.1.1, "Reactor Core SLs," and LCO 3.2.2,"MINIMUM CRITICAL POWER RATIO (MCPR)") and the 1% cladding plastic strain fuel design limit (see Bases for LCO 3.2.3, "LINEAR HEAT GENERATION RATE (LHGR)" and LCO 3.2.4, "Average Power Range Monitor (APRM) Gain and Setpoints"), which ensure that no fuel damage will occur if these limits are not exceeded.

Above 800 psig, the scram function is designed to insert negative reactivity at a rate fast enough to prevent the actual MCPR from becoming less than the MCPR SL, during the analyzed limiting power transient.

Below 800 psig, the scram function is assumed to perform during the control rod drop accident and, therefore, also provides protection against violating fuel damage limits during reactivity insertion accidents (Ref. 5) (see-Bases for LCO 3.1.6, "Rod Pattern Control").

For the reactor vessel overpressure protection analysis, the scram function, along with the safety/relief valves, ensure that the peak vessel pressure is maintained within the applicable ASME Code limits.Control rod scram times satisfy Criterion 3 of the NRC Policy Statement (Ref. 6).LCO The scram times specified in Table 3.1.4-1 (in the accompanying LCO)are required to ensure that the scram reactivity assumed in the DBA and transient analysis is met (Ref. 7). To account for single failures and "slow" scramming control rods, the scram times specified in Table 3.1.4-1 are faster than those assumed in the design basis analysis.

The scram times have a margin that allows up to approximately 7% of the control rods (e.g., 185 x 7% t 13) to have scram times exceeding the specified limits (i.e.,"slow" control rods) including a single stuck control rod (as allowed by LCO 3.1.3, "Control Rod OPERABILITY')

and an additional control rod failing to scram per the single failure criterion.

The scram times are specified as a function of reactor steam dome pressure to account for the pressure dependence of the scram times. The scram times are specified relative to measurements based on reed switch positions, which provide the control rod position indication.

The reed switch closes ("pickup")

when the index tube passes a specific location and then opens ("dropout")

as the index tube travels upward. Verification of the specified scram times in Table 3.1.4-1 is (continued)

SUSQUEHANNA

-UNIT 2 TS / B 3.1-23 Revision I PPL Rev. 3 Control Rod Scram Times B 3.1.4 BASES LCO -(continued) accomplished through measurement of the "dropout" times. To ensure that local scram reactivity rates are maintained within acceptable limits, no more than one "slow" control rod may occupy a face or diagonally adjacent location to any other "slow" or stuck control rod.Table 3.1.4-1 is modified by two Notes which state that control rods with scram times not within the limits of the table are considered "slow" and that control rods with scram times > 7 seconds are considered inoperable as required by SR 3.1.3.4.This LCO.applies only to OPERABLE control rods since inoperable control rods will be inserted and disarmed (LCO 3.1.3). Slow scramming control rods may be conservatively declared inoperable and not accounted for as"slow" control rods.APPLICABILITY In MODES I and 2, a scram is assumed to function during transients and accidents analyzed for these plant conditions.

These events are assumed to occur during startup and power operation; therefore, the scram function of the control rods is required during these MODES. In MODES 3 and 4, the control rods are not able to be withdrawn (except as permitted by LCO 3.10.3 and LCO 3.10.4) since the reactor mode switch is in shutdown and a control rod block is applied. This provides adequate requirements for control rod scram capability during these conditions.

Scram requirements in MODE 5 are contained in LCO 3.9.5, "Control Rod OPERABILITY-Refueling." ACTIONS A.1 When the requirements of this LCO are not met, the rate of negative reactivity insertion during a scram may not be within the assumptions of the safety analyses.

Therefore, the plant must be brought to a MODE in which the LCO does not apply. To achieve this status, the plant must be brought to MODE 3 within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. The allowed Completion Time of.12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> is reasonable, based on operating experience, to reach MODE 3 from full power conditions in an orderly manner and without challenging plant systems.(continued)

SUSQUEHANNA

-UNIT 2 TS / B 3.1-24 Revision 0 PPL Rev. 3 Control Rod Scram Times B 3.1.4 BASES (continued)

SURVEILLANCE REQUIREMENTS The four SRs of this LCO are modified by a Note stating that during a single control rod scram time surveillance, the CRD pumps shall be isolated from the associated scram accumulator.

With the CRD pump isolated, (i.e., charging valve closed) the influence of the CRD pump head does not affect the single control rod scram times. During a full core scram, the CRD pump head would be seen by all control rods and would have a negligible effect on the scram insertion times.SR 3.1.4.1 The scram reactivity used in DBA and transient analyses is based on an assumed control rod scram time. Measurement of the scram times with reactor steam dome pressure > 800 psig demonstrates acceptable scram times for the transients analyzed in References 3 and 4.Maximum scram insertion times occur at a reactor steam dome pressure of approximately 800 psig because of the competing effects of reactor steam dome pressure and stored accumulator energy. Therefore, demonstration of adequate scram times at reactor steam dome pressure> 800 psig ensures that .the measured scram times will be within the specified limits at higher pressures.

Limits are specified as a function of reactor pressure to account for the sensitivity of the scram insertion times with pressure and to allow a range of pressures over which scram time testing can be performed.

To ensure that scram time testing is performed within a reasonable time following a shutdown >_ 120 days or longer, control rods are required to be tested before exceeding 40% RTP following the shutdown.

This Frequency is acceptable considering the additional surveillances performed for control rod OPERABILITY, the frequent verification of adequate accumulator pressure, and the required testing of control rods affected by fuel movement within the associated core cell and by work on control rods or the CRD System.I I L (continued)

SUSQUEHANNA

-UNIT 2 TS / B 3.1-25 Revision 1 PPL Rev. 3 Control Rod Scram Times B 3.1.4 BASES SURVEILLANCE REQUIREMENTS (continued)

SR 3.1.4.2 Additional testing of a sample of control rods is required to verify the continued performance of the scram function during the cycle. A representative sample contains at least 10% of the control rods. The sample remains representative if no more than 20% of the control rods in the sample tested are determined to be "slow." With more than 20% of the sample declared to be "slow" per the criteria in Table 3.1.4-1, additional control rods are tested until this 20% criterion (e.g., 20% of the entire sample size) is satisfied, or until the total number of "slow" control rods (throughout the core, from all surveillances) exceeds the LCO limit.For planned testing, the control rods selected for the sample should be different for each test. Data from inadvertent scrams should be used whenever possible to avoid unnecessary testing at power, even if the control rods with data may have been previously tested in a sample. The 120 day Frequency is based on operating experience that has shown control rod scram times do not significantly change over an operating cycle. This Frequency is also reasonable based on the additional Surveillances done on the CRDs at more frequent intervals in accordance with LCO 3.1.3 and LCO 3.1.5, "Control Rod Scram Accumulators." SR 3.1.4.3 When work that could affect the scram insertion time is performed on a control rod or the CRD System, testing must be done to demonstrate that each affected control rod retains adequate scram performance over the range of applicable reactor pressures from zero to the maximum permissible pressure.

The scram testing must be performed once before declaring the control rod OPERABLE.

The required scram time testing must demonstrate the affected control rod is still within acceptable limits.The limits for reactor pressures

< 800 psig are established based on a high probability of meeting the acceptance criteria at reactor pressures

>_800 psig. Limits for > 800 psig are found in Table 3.1.4-1. If testing demonstrates the affected control rod does not meet these limits, but is within the 7-second limit of Table 3.1.4-1, Note 2, the control rod can be declared OPERABLE and "slow." (continued)

SUSQUEHANNA

-UNIT 2 TS / B 3.1-26 Revision 0 PPL Rev. 3 Control Rod Scram Times B 3.1.4 BASES SURVEILLANCE SR 3.1.4.3 (continued)

REQUIREMENTS Specific examples of work that could affect the scram times are (but are not limited to) the following:

removal of any CRD for maintenance or modification; replacement of a control rod; and maintenance or modification of a scram solenoid pilot valve, scram valve, accumulator, isolation valve or check valve in the piping required for scram.The Frequency of once prior to declaring the affected control rod OPERABLE is acceptable because of the capability to test the control rod over a range of operating conditions and the more frequent surveillances on other aspects of control rod OPERABILITY.

SR 3.1.4.4 When work that could affect the scram insertion time is performed on a control rod or CRD System, or when fuel movement within the affected core cell occurs, testing must be done to demonstrate each affected control rod is still within the limits of Table 3.1.4-1 with the reactor steam dome pressure 800 psig. Where work has been performed at high reactor pressure, the requirements of SR 3.1.4.3 and SR 3.1.4.4 can be satisfied with ond test. For a control rod affected by work performed while shut down, however, a zero pressure and high pressure test may be required.

This testing ensures that, prior to withdrawing the control rod for continued operation, the control rod scram performance is acceptable for operating reactor pressure conditions.

Alternatively, a control rod scram test during hydrostatic pressure testing could also satisfy both criteria.When fuel movement within the reactor pressure vessel occurs, only those control rods associated with the core cells affected by the fuel movement are required to be scram time tested. During a routine refueling outage, it is expected that all control rods will be affected.The Frequency of once prior to exceeding 40% RTP is acceptable because of the capability to test the control rod over a range of operating conditions and the more frequent surveillances on other aspects of control rod OPERABILITY.

REFERENCES

1. 10 CFR 50, Appendix A, GDC 10.2. FSAR, Section 4.3.2.3. FSAR, Section 4.6.(continued)

SUSQUEHANNA

-UNIT 2 TS / B 3.1-27 Revision 1 PPL Rev. 3 Control Rod Scram Times B 3.1.4 BASES REFERENCES (continued)

4. FSAR, Section 15.0 5. FSAR, Section 15.4.9.I 6. Final Policy Statement on Technical Specifications Improvements, July 22, 1993 (58 FR 39132).7. Letter from R. F. Janecek (BWROG) to R.W. Starostecki (NRC),"BWR Owners Group Revised Reactivity Control System Technical Specifications," BWROG-8754, September 17, 1987.SUSQUEHANNA

-UNIT 2 TS / B 3.1-28 Revision 2