ML090510151

Update to Technical Specification Bases Manual

ML090510151
Person / Time
Site:	Susquehanna
Issue date:	02/02/2009
From:	Susquehanna
To:	Gerlach R M Document Control Desk, Office of Nuclear Reactor Regulation
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Download: ML090510151 (26)

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Feb. 02, 2009 Page 1 of 2 MANUAL HARD COPY DISTRIBUTION DOCUMENT TRANSMITTAL 2009-5120 USER INFORMATION:

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

TO: GERLACH*ROSE M 02/02/2009 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.TSBI -TECHNICAL SPECIFICATION BASES UNIT 1 MANUAL REMOVE MANUAL TABLE OF CONTENTS DATE: 01/19/2009 ADD MANUAL TABLE OF CONTENTS DATE: 01/30/2009 CATEGORY:

DOCUMENTS TYPE: TSBI 40D I Feb. 02, 2009 Page 2 of 2 ID: TEXT 3.1.4 ADD: REV: 4 REMOVE: REV:3 CATEGORY: ID: TEXT REMOVE: DOCUMENTS TYPE: TSB1 LOES REV:90 ADD: REV: 91 ANY DISCREPANCIES WITH THE MATERIAL PROVIDED, CONTACT DCS @ X3107 OR X3136 FOR ASSISTANCE.

UPDATES FOR HARDCOPY MANUALS WILL BE DISTRIBUTED WITHIN 3 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: TSB1 Manual Title: TECHNICAL SPECIFICATION BASES UNIT 1 MANUAL Table Of Contents Issue Date: 01/30/2009 Procedure Name Rev TEXT LOES 91 Title: LIST OF EFFECTIVE SECTIONS Issue Date 01/30/2009 Change ID Change Number TEXT TOC Title: TABLE OF CONTENTS 16 10/27/2008 TEXT 2.1.1 4 Title: SAFETY LIMITS (SLS) REACTOR 04/23/2008 CORE SLS TEXT 2.1.2 1 10/04/2007 Title: SAFETY LIMITS (SLS) REACTOR COOLANT SYSTEM,'(RCS) PRESSURE S'TEXT 3. 0 2 /',10/12/2006' Title: LIMITING CONDITION FOR OPERATION-(LCO)

APPLICABILITY TEXT 3.1.1 1 ',4/18/2006 Title: REACTIVITY CONTROL SYSTEMS SHUTDOWN MARGIN (SDM)TEXT 3.1.2 Title: REACTIVITY CONTROL S SYSTEMS 11/15/2002 REACTIVITY ANOMALIES TEXT 3.1.3 2 01/19/2009 Title: REACTIVITY CONTROL SYSTEMS CONTROL ROD OPERABILITY TEXT 3.1.4 4 01/30/2009 Title: REACTIVITY CONTROL SYSTEMS CONTROL ROD SCRAM TIMES TEXT 3.1.5 Title: REACTIVITY CONTROL 1 SYSTEMS 07/06/2005 CONTROL ROD SCRAM ACCUMULATORS TEXT 3.1.6 2 04/18/2006 Title: REACTIVITY CONTROL SYSTEMS ROD PATTERN CONTROL Pagel of 8 Report Date: 01/30/09 Page I of .8 Report Date: 01/30/09 SSES MANUJAL Manual Name: TSBI Manual Title: TECHNICAL SPECIFICATION BASES UNIT 1 MANUAL TEXT -3.1.7 Title: REACTIVITY CONTROL.3 04/23/2008 SYSTEMS STANDBY LIQUID CONTROL (SLC) SYSTEM TEXT 3.1.8 2 10/04/2007 Title: REACTIVITY CONTROL SYSTEMS SCRAM DISCHARGE VOLUME (SDV) VENT AND DRAIN VALVES TEXT.3.2.1 Title: POWER DISTRIBUTION 2 04/23/2008 LIMITS AVERAGE PLANAR LINEAR HEAT GENERATION RATE (APLHGR)TEXT 3.2.2 2 04/23/2008 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 .. 4 04/23/2008 Title: INSTRUMENTATION REACTOR PROTECTION SYSTEM (RPS) INSTRUMENTATION TEXT 3.3.1.2 2 01/19/2009 Title: INSTRUMENTATION SOURCE RANGE MONITOR (SRM) INSTRUMENTATION TEXT 3.3.2.1 .3 04/23/2008, Title: INSTRUMENTATION CONTROL ROD BLOCK INSTRUMENTATION TEXT 3.3.2.2 1 04/23/2008 Title: INSTRUMENTATION FEEDWATER MAIN TURBINE HIGH WATER LEVEL TRIP INSTRUMENTATION TEXT 3.3.3.1 8 10/27/2008 Title: INSTRUMENTATION POST ACCIDENT MONITORING (PAM) INSTRUMENTATION TEXT 3.3.3.2 1 04/18/2005 Title: INSTRUMENTATION REMOTE SHUTDOWN SYSTEM TEXT 3.3.4.1 Title: INSTRUMENTATION 1 04/23/2008 a END OF CYCLE RECIRCULATION PUMP TRIP (EOC-RPT)

INSTRUMENTATIONW Page2 of 8 Report Date: 01/30/09 Page 2 of .8 Report Date: 01/30/09 SSES M.ANTA-I~Manual Name: TSB1 Manual Title: TECHNICAL SPECIFICATION BASES UNIT 1 MANUAL 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 2 07/06/2005 Title: INSTRUMENTATION EMERGENCY CORE COOLING SYSTEM (ECCS) INSTRUMENTATION TEXT 3.3.5.2 Title: INSTRUMENTATION 0 11/15/2002 REACTOR CORE ISOLATION COOLING (RCIC) SYSTEM INSTRUMENTATION TEXT 3.3.6.1 4 04/23/2008 Title: INSTRUMENTATION PRIMARY CONTAINMENT ISOLATION INSTRUMENTATION TEXT 3.3.6.2 3 10/27/2008 Title: INSTRUMENTATION SECONDARY CONTAINMENT ISOLATION INSTRUMENTATION TEXT 3.3.7.1 Title: INSTRUMENTATION INSTRUMENTATION TEXT 3.3.8.1 Title: INSTRUMENTATION 2 10/27/2008 CONTROL ROOM EMERGENCY OUTSIDE AIR SUPPLY (CREOAS) SYSTEM 2 12/17/2007 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 3 04/12/2006 Title: REACTOR COOLANT SYSTEM (RCS) RECIRCULATION LOOPS OPERATING TEXT 3.4.2 1 04/23/2008 Title: REACTOR COOLANT SYSTEM (RCS) JET PUMPS TEXT 3.4.3 2 04/23/2008.Title: REACTOR COOLANT SYSTEM RCS SAFETY RELIEF VALVES S/RVS S TEXT 3.4.4 0 11/15/2002 Title: REACTOR COOLANT SYSTEM (RCS) RCS OPERATIONAL LEAKAGE Page 3 of .8 Report Date: 01/30/09 I. SSES .MANUAL Manual Name: TSB1 Manual Title: TECHNICAL SPECIFICATION BASES UNIT 1 MANUAL TEXT 3.4.5 1 01/16/2006 Title: REACTOR COOLANT SYSTEM (RCS) RCS PRESSURE ISOLATION VALVE (PIV) LEAKAGE TEXT 3.4.6 1 04/18/2005 Title: REACTOR COOLANT SYSTEM (RCS) 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 1 04/18/2005 SYSTEM (RCS.) RESIDUAL HEAT REMOVAL (RHR) SHUTDOWN COOLING'SYSTEM 0 SYSTEM (RCS)11/15/2002 RESIDUAL HEAT REMOVAL-(RHR)

SHUTDOWN COOLING SYSTEM 3 04/23/2008 SYSTEM (RCS) RCS PRESSURE.AND.TEMPERATURE (P/T) LIMITS. '0 11/15/-20,02 SYSTEM (RCS) REACTOR STEAM DOME PRESSURE " 2 01/16/2006 Title: EMERGENCY CORE COOLING SYSTEMS (ECCS) AND REACTOR CORE SYSTEM ECCS -OPERATING TEXT 3.5.2 0 11/15/2002 Title: EMERGENCY CORE COOLING SYSTEMS (ECCS) AND REACTOR CORE SYSTEM ECCS -SHUTDOWN TEXT 3.5.3 1 04/18/2005 Title: EMERGENCY CORE COOLING SYSTEMS (ECCS) AND-REACTOR

'CORE SYSTEM RCIC SYSTEM TEXT 3.6.1.1 3 04/23/2008 Title: CONTAINMENT SYSTEMS PRIMARY CONTAINMENT TEXT 3.6.1.2 1 04/23/2008 Title: CONTAINMENT SYSTEMS PRIMARY CONTAINMENT AIR LOCK ISOLATION COOLING ,(RCIC)ISOLATION COOLING (RCIC)ISOLATION COOLING (RCIC)Page 4 of 8 Report Date: 01/30/09 Page4 of .8 Report Date: 01/30/09 SSES'.MANUAL 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 8 04/23/2008 SYSTEMS PRIMARY CONTAINMENT ISOLATION VALVES (PCIVS)'LDCN 3092 1 04/23/2008 SYSTEMS. CONTAINMENT PRESSURE 1 10/05/2005 SYSTEMS DRYWELL AIR TEMPERATURE.

0 11/15/2002 SYSTEMS SUPPRESSION.CHAMBER-TO-DRYWELL VACUUM BREAKERS 2 04/23/2008 SYSTEMS SUPPRESSION POOL AVERAGE TEMPERATURE

.0 11/15/2002 SYSTEMS SUPPRESSION POOL WATER LEVEL 1 01/1.6,/2.00.6 SYSTEMS RESiDUAL HEAT REMOVAL .(RHR). 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 0 11/15/2002 SYSTEMS PRIMARY CONTAINMENT OXYGEN CONCENTRATION 7 10/04/2007 SYSTEMS SECONDARY CONTAINMENT PageS of 8 Report Date: 01/30/09 Page 5 of .8 Report Date: 01/30/09 SSES.-MANUAL Manual Name: TSBI Manual Title: TECHNICAL SPECIFICATION BASES UNIT 1 MANUAL TEXT 3.6.4.2 2 01/03/2005 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 TEXT 3.7.2 Title: PLANT SYSTEMS.TEXT 3.7.3 Title: PLANT SYSTEMS TEXT 3.7.4 Title: PLANT SYSTEMS TEXT 3.7.5 Title: PLANT SYSTEMS TEXT 3.7.6 Title: PLANT SYSTEMS TEXT 3.7.7 Title: PLANT SYSTEMS TEXT 3.7.8 Title: PLANT SYSTEMS TEXT 3.8.1 1 12/17/2007 RESIDUAL HEAT REMOVAL SERVICE WATER (RHRSW) SYSTEM-AND THE SINK (UHS)1 11/09/2004 EMERGENCY SERVICE WATER (ESW) SYSTEM 0 11/15/2002 CONTROL ROOM EMERGENCY-OOTSIDE AIR SUPPLY (CREOAS) SYSTEM 0 11/15/2002 CONTROL ROOM FLOOR COOLING-SYSTEM 1 10/04/2007 MAIN CONDENSER OFFGAS'2 04/23/2008 MAIN TURBINE BYPASS SYSTEM " 1 10/04/2007 SPENT FUEL STORAGE POOL WATER LEVEL 0 04/2372008 5 12/17/2007 Title: ELECTRICAL POWER SYSTEMS AC SOURCES -OPERATING TEXT 3.8.2 0 11/15/2002 Title: ELECTRICAL POWER SYSTEMS AC SOURCES -SHUTDOWN Page 6 of *8 Report Date: 01/30/09 Page 6 of .8 Report Date: 01/30/09 SSES. MANUA.L 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 1 POWER SYSTEMS 3 POWER SYSTEMS 1 POWER, SYSTEMS 04/23,/2008 DIESEL FUEL OIL, LUBE OIL, AND STARTING AIR 01/19/2009 DC SOURCES ,- OPERATING 12/14/2006 DC SOURCES -SHUTDOWN 1 12/14/2006 POWER SYSTEMS BATTERY CELL PARAMETERS.

1 10/05/2005 POWER SYSTEMS DISTRIBUTION SYSTEMS -OPERATING 0 11/15/2002 POWER SYSTEMS DISTRIBUTION'SYSTEMS

-SHUTDOWN TEXT 3.9.1 Title: REFUELING TEXT 3.9.2 Title: REFUELING TEXT 3.9.3 Title: REFUELING TEXT 3.9.4 Title: REFUELING TEXT 3.9.5 Title: REFUELING TEXT 3.9.6 Title: REFUELING OPERATIONS OPERATIONS OPERATIONS OPERATIONS OPERATIONS OPERATIONS 0 11/15/2002 REFUELING EQUIPMENT INTERLOCKS 0 11/15/2002 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 7 of *~ Report Date: 01/30/09 Page 7 of -8 Report Date: 01/30/09 SSES MANTTA-L Manual Name: TSBl Manual 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 (RHR) -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 3.10.5i 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 Page8 of 8 Report Date: 01/30/09 Page 8 of .8 Report Date: 01/30/09 SUSQUEHANNA STEAM ELECTRIC STATION LIST OF EFFECTIVE SECTIONS (TECHNICAL SPECIFICATIONS BASES)Section Title Revision TOC Table of Contents 16 B 2.0 SAFETY LIMITS BASES Page B 2.0-1 0 Page TS / B 2.0-2 3 Page TS / B 2.0-3 5 Page TS / B2.0-4 3 Page TS / B 2.0-5 4 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 / B 3.0-1 1 Pages TS / B 3.0-2 through TS / 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 Page TS / B 3.0-10 1 Page TS / B 3.0-11 2 Page TS I B 3.0-1 Ia 0 Page TS / B 3.0-12 1 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 Pages B 3.1-1 through B 0 ,Page TS / B 3.1-5 Pages TS / B 3.1-6 and TS / B 3.1-7 2 Pages B 3.1-8 through B 3.1-13 0 Page TS / B 3.1-14 1 Page B 3.1-15. .0 Page TS / B 3.1-16 1 Pages B 3.1-17 through B 3.1-19 0 Pages TS / B 3.1-20 and TS / B 3.1-21 1 Page TS / B 3.1-22 0 Page TS / B 3.1-23 1 Page TS / B 3.1-24 0 Pages TS / B 3.1-25 through TS / B 3.1-27 1 Page TS / B 3.1-28 2 Page TS / B 3.1-29 1 Pages B 3.1-30 through B 3.1-33 0 Pages TS / B 3.3-34 through TS / B 3.3-36 1 Pages TS / B 3.1-37 and TS / B 3.1-38 2 Page TS / B 3.1-39 and TS / B 3.1-40 2 Page TS / B 3.1.40a 0 Pages TS / B 3.1.41 and TS / B 3.1-42 2 SUSQUEHANNA

-UNIT 1 TS / B LOES-1 Revision 91 SUSQUEHANNA STEAM ELECTRIC STATION LIST OF EFFECTIVE SECTIONS (TECHNICAL SPECIFICATIONS BASES)Section Title Revision Page TS / B 3.1.43 1 Page TS / B 3.1-44 0 Page TS / B 3.1-45 3 Pages TS / B 3.1-46 through TS / B 3.1-49 1 Page TS / B 3.1-50 0 Page TS / B 3.1-51 2 B 3.2 POWER DISTRIBUTION LIMITS BASES Page TS / B 3.2-1 2 Pages TS / B 3.2-2 and TS / B 3.2-3 3 Pages TS / B 3.2-4 and TS / B 3.2-5 2 Page TS / B 3.2-6 3 Page B 3.2-7 1 Page TS / B 3.2-8 3 Pages TS / B 3.2-9 and TS / B 3.2.10 2 Page TS / B 3.2-11 3 Page TS / B 3.2-12 1 Page TS / B 3.2-13 2 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 Page TS / B 3.3-7 3 Page TS / B 3.3-7a 1 Page TS / B 3.3-8 4 Pages TS / B 3.3-9 through TS /B 3.3-12 3 Pages TS / B 3.3-12a 1 Pages TS / B 3.3-12b and TS /B 3.3-12c 0 Page TS / 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 / B 3.3-20 through TS / B 3.3-22 2 Page TS / B 3.3-22a 0 Pages TS / B 3.3-23 and TS / B 3.3-24 2 Pages TS / 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 Pages TS / B 3.3-28 through TS / B 3.3-30 3 Page TS / B 3.3-30a 0 SUSQUEHANNA

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-UNIT 1 TS I B LOES-2 Revision 91 TS / B LOES-2 Revision 91 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 / 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 TS / B 3.3-39 2 Pages TS / B 3.3-40 through TS I B 3.3-43 1 Page TS / B 3.3-44 4 Pages TS / B 3.3-44a and TS / B 3.3-44b 0 Page TS / B 3.3-45 3 Pages TS / B 3.3-45a and TS / B 3.3-45b 0 Page TS / B 3.3-46 3 Pages TS / B 3.3-47 2 Pages TS / B 3.3-48 through TS / B 3.3-51 3 Pages TS / B 3.3-52 and TS / B 3.3-53 2 Page TS / B 3-3-53a 0 Page TS / B 3.3-54 4 Page B 3.3-55 1 Page B 3.3-56 0 Page B 3.3-57 1 Page B 3.3-58 0 Page B 3.3-59 1 Pages B 3.3-60 through 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 / B 3.3-71 3 Pages TS / B 3.3-72 and TS / B 3.3-73 2 Page TS / B 3.3-74 3 Page TS / B 3.3-75 2 Page TS / B 3.3-75a 6 Page TS L B 3.3-75b 7 Page TS / B 3.3-75c 5 Pages B 3.3-76 through 3.3-77 0 Page TS / B 3.3-78 1 Pages B 3.3-79 through B 3.3-81 0 Page B 3.3-82 1 Page B 3.3-83 0 Pages B 3.3-84 and B 3.3-85 1 SUSQUEHANNA

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-UNIT 1 TS I B LOES-3 Revision 91 TS / B LOES-3 Revision 91 SUSQUEHANNA STEAM ELECTRIC STATION LISTOFEFFECTIVE SECTIONS (TECHNICAL SPECIFICATIONS BASES)Section Title Revision 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 / B 3.3-90 1 Page B 3.3-91 0 Pages TS / B 3.3-92 through TS / B 3.3-100 1 Pages B 3.3-101 through B 3.3-103 0 Page TS / B 3.3-104 1 Pages B 3.3-105 and B 3.3-106 0 Page TS / B 3.3-107 1 Page B 3.3-108 0 Page TS / B 3.3-109 1 Pages B 3.3-110 and B 3.3-111 0 Pages TS / B 3.3-112 and TS / B 3.3-112a 1 Pages TS / B 3.3-113 through TS / B 3.3-115 1 Page TS / B 3.3-116 2 Page TS / B 3.3-117 1 Pages B 3.3-118 through B 3.3-122 0 Pages TS / B 3.3-123 and TS / B 3.3-124 1 Page TS / B 3.3-124a 0 Page B 3.3-125 0 Pages TS / B 3.3-126 and TS / B 3.3-127 1 Pages B 3.3-128 through B 3.3-130 0 Page TS / B 3.3-131 1 Pages B 3.3-132 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 and TS / B 3.3-151 1 Pages TS / B 3.3-152 through TS / B 3.3-154 2 Page TS / B 3.3-155 1 Pages TS / B 3.3-156 through TS / B 3.3-158 2 Pages TS / B 3.3-159 through TS / B 3.3-162 1 Page TS / B 3.3-163 2 Pages TS / B 3.3-164 and TS / B 3.3-165 1 Pages TS / B 3.3-166 and TS / B 3.3-167 2 Pages TS / B 3.3-168 and TS / B 3.3-169 1 Page TS / B 3.3-170 2 Pages TS / B 3.3-171 through TS / B 3.3-177 1 Pages TS / B 3.3-178 through TS / B 3.3-179a 2 Pages TS / B 3.3-179b and TS / B 3.3-179c 0 Page TS / B 3.3-180 1 Page TS / B 3.3-181 3 Page TS / B 3.3-182 1 Page TS / B 3.3-183 2 Page TS I B 3.3-184 1 SUSQUEHANNA

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-UNIT 1 TS I B LOES-4 Revision 91 TS / B LOES-4 Revision 91 SUSQUEHANNA STEAM ELECTRIC STATION LIST OF EFFECTIVE SECTIONS (TECHNICAL SPECIFICATIONS BASES)Section Title Revision Page TS / B 3.3-185 3 Page TS / B 3.3-186 1 Pages TS / B 3.3-187 and TS / B 3.3-188 2 Pages TS / B 3.3-189 through TS / B 3.3-191 1 Page TS / B 3.3-192 0 Page TS / B 3.3-193 1 Pages TS / B 3.3-194 and TS / B 3.3-195 0 Page TS / B 3.3-196 2 Pages TS / B 3.3-197 through TS / 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 / B 3.4-4 4 Pages TS / B 3.4-5 through TS / B 3.4-9 2 Pages B 3.4-10 through B 3.4-12 0 Page B 3.4-13 1 Page B 3.4-14 0 Page TS / B 3.4-15 2 Pages TS / B 3.4-16 and TS / B 3.4-17 3 Page 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 and B 3.4-31 0 Page TS / B 3.4-32 1 Pages B 3.4-33 and B 3.4-34 0 Pages TS / B 3.4-35 and TS / B 3.4-36 1 Page TS / B 3.4-37 2 Page TS / B 3.4-38 1 Pages B 3.4-39 and 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 Page TS / B 3.4-50 1 Page TS / B 3.4-51 3 Page TS / B 3.4-52 2 Page TS / B 3.4-53 1 Pages TS / B 3.4-54 through TS / B 3.4-56 2 Page TS / B 3.4-57 3 Pages TS / B 3.4-58 through TS / B 3.4-60 1 SUSQUEHANNA

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-UNIT 1 TS / B LOES-5 Revision 91 TS / B LOES-5 Revision 91 SUSQUEHANNA STEAM ELECTRIC STATION LIST OF EFFECTIVE SECTIONS (TECHNICAL SPECIFICATIONS BASES)Section Title Revision B 3.5 ECCS AND RCIC BASES Pages B 3.5-1 and B 3.5-2 0 Page TS / B 3.5-3 2 Page TS / B 3.5-4 1 Page TS / B 3.5-5 2 Page TS / B 3.5-6 1 Pages B 3.5-7 through B 3.5-10 0 Page TS / B 3.5-11 1 Page TS / B 3.5-12 0 Page TS / B 3.5-13 1 Pages TS / B 3.5-14 and TS / B 3.5-15 0 Pages TS / B 3.5-16 through TS / B 3.5-18 1 Pages B 3.5-19 through B 3.5-24 0 Page TS / B 3.5-25 1 Pages TS / B 3.5-26 and 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 Page TS / B 3.6-2 4 Page TS / B 3.6-3 3 Page TS / B 3.6-4 4 Pages TS / B 3.6-5 and 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 0 Page B 3.6-8 1 Pages B 3.6-9 through B 3.6-14 0 Page TS / B 3.6-15 2 Page TS / B 3.6-15a 0 Page TS LB 3.6-15b 2 Pages TS / B 3.6-16 and TS / B 3.6-17 1 Page TS / B 3.6-17a 0 Pages TS / B 3.6-18 and TS / B 3.6-19 0 Page TS / B 3.6-20 1 Page TS / B 3.6-21 2 Page TS / B 3.6-22 1 Page TS / B 3.6-22a 0 Page TS / B 3.6-23 1 Pages TS / B 3.6-24 and TS / B 3.6-25 0 Pages TS / B 3.6-26 and TS / B 3.6-27 2 Page TS / B 3.6-28 7 Page TS / B 3.6-29 2 Page TS / B 3.6-30 1 SUSQUEHANNA

-UNIT 1 TS / B LOES-6 Revision 91 SUSQUEHANNA

-UNIT 1 TS / B LOES-6 Revision 91 SUSQUEHANNA STEAM ELECTRIC STATION LIST OF EFFECTIVE SECTIONS (TECHNICAL SPECIFICATIONS BASES)Section Title Revision Page TS / B 3.6-31 3 Page TS / B 3.6-32 0 Page TS / B 3.6-33 1 Pages TS / B 3.6-34 and TS I B 3.6-35 0 Page TS / B 3.6-36 1 Page TS / B 3.6-37 0 Page TS / B 3.6-38 3 Page TS / B 3.6-39 2 Page TS / B 3.6-40 6 Page B 3.6-41 1 Pages B 3.6-42 and B 3.6-43 3 Pages TS / B 3.6-44 and TS / B 3.6-45 1 Page TS / B 3.6-46 2 Pages TS / B 3.6-47 through TS / B 3.6-51 1 Page TS / B 3.6-52 2 Pages TS / B 3.6-53 through TS / B 3.6-56 0 Page TS / B 3.6-57 1 Page TS / 3.6-58 2 Pages B 3.6-59 through B 3.6-63 0 Pages TS / B 3.6-64 and TS / B 3.6-65 1 Pages B 3.6-66 through B 3.6-69 0 Pages TS / B 3.6-70 through TS / B 3.6-72 1 Page TS / B 3.6-73 2 Pages TS / B 3.6-74 and TS / B 3.6-75 1 Pages B 3.6-76 and B 3.6-77 0 Page TS / B 3.6-78 1 Pages B 3.6-79 through B 3.3.6-83 0 Page TS / B 3.6-84 3 Page TS / B 3.6-85 2 Page TS / B 3.6-86 4 Pages TS / B 3.6-87 through TS / B 3.6-88a 2 Page TS / B 3.6-89 4 Page TS / B 3.6-90 2 Page TS / B 3.6-91 3 Pages TS / B 3.6-92 through TS / B 3.6-96 1 Page TS / B 3.6-97 2 Pages TS / B 3.6-98 and TS / B 3.6-99 1 Page TS / B 3.6-100 2 Pages TS / 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 SUSQUEHANNA

-UNIT 1 TS I B LOES-7 Revision 91 SUSQUEHANNA

-UNIT 1 TS / B LOES-7 Revision 91 SUSQUEHANNA STEAM ELECTRIC STATION LIST OF EFFECTIVE SECTIONS (TECHNICAL SPECIFICATIONS BASES)Section Title Revision 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 / B 3.7-5a 0 Pages TS / B 3.7-6 and TS / B 3.7-6a 2 Pages TS / B 3.7-6b and TS / B 3.7-6c 1 Page TS / B 3.7-7 3 Page TS / B 3.7-8 2 Pages TS / B 3.7-9 through 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 3.7-23 1 Page TS / B 3.7-24 1 Pages TS / B 3.7-25 and TS / B 3.7-26 0 Pages TS / B 3.7-27 through TS B B 3.7-29 5 Page TS / B 3.7-30 2 Page TS / 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 B 3.7-37 0 B 3.8 ELECTRICAL POWER SYSTEMS BASES Pages TS / B 3.8-1 through TS / B 3.8-3 2 Page TS / B 3.8-4 3 Pages TS / B 3.8-4a and TS / B 3.8-4b 0 Page TS I B 3.8-5 5 Page TS / B 3.8-6 3 Pages TS / B 3.8-7 through TS/B 3.8-8 2 Page TS / B 3.8-9 4 Page TS / B 3.8-10 3 Pages TS / B 3.8-11 and TS / B 3.8-17 2 Page TS / B 3.8-18 3 Pages TS / B 3.8-19 through TS I B 3.8-21 2 Pages TS / B 3.8-22 and TS / B 3.8-23 3 Pages TS / B 3.8-24 through TS / B 3.8-37 2 Pages B 3.8-38 through B 3.8-44 0 Page TS / B 3.8-45 1 Pages TS / B 3.8-46 through B 3.8-48 0 Page TS / B 3.8-49 1 Pages B 3.8-50 through B 3.8-53 0 Pages TS / B 3.8-54 through TS / B 3.8-57 2 Pages TS / B 3.8-58 through TS / B 3.8-61 3 Pages TS / B 3.8-62 and TS / B 3.8-63 5 Page TS / B 3.8-64 4 SUSQUEHANNA

-UNIT 1 TS / B LOES-8 Revision 91 SUSQUEHANNA STEAM ELECTRIC STATION LIST OF EFFECTIVE SECTIONS (TECHNICAL SPECIFICATIONS BASES)Section Title Revision Page TS L B 3.8-65 5 Pages TS / B 3.8-66 through TS / B 3.8-77 1 Pages TS / B 3.8-77A through TS / B 3.8-77C 0 Pages B 3.8-78 through B 3.8-80 0 Page TS / B 3.8-81 1 Pages B 3.8-82 through B 3.8-90 0 B 3.9 REFUELING OPERATIONS BASES Pages TS / B 3.9-1 and TS / B 3.9-1a 1 Pages TS / B 3.9-2 through TS / B 3.9-4 1 Pages B 3.9-5 through B 3.9-18 0 Pages TS / B 3.9-19 through TS / B 3.9-21 1 Pages B 3.9-22 through B 3.9-30 0 B 3.10 SPECIAL OPERATIONS BASES Page TS / B 3.10-1 2 Pages TS / B 3.10-2 through TS / B 3.10-5 1 Pages B 3.10-6 through B 3.10-31 0 Page TS / B 3.10-32 2 Page B 3.10-33 0 Page TS / B 3.10-34 1 Pages B 3.10-35 and B 3.10-36 0 Page TS / B 3.10-37 1 Page TS I B 3.10-38 2 TSB1 Text LOES.doc 01/20/2009 SUSQUEHANNA

-UNIT 1 TS I B LOES-9 Revision 91 SUSQUEHANNA

-* UNIT 1 TS / B LOES-9 Revision 91 PPL Rev. 4 Control Rod Scram Times B 3.1.4 B 3.1 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 1 TS / B 3.1-22 Revision 0 PPL Rev. 4 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% z 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)

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-UNIT 1 TS / B 3.1-23 Revision 1 PPL Rev. 4 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 1 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)

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-UNIT 1'TS / B 3.1-24 PPL Rev. 4 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.(continued)

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-UNIT 1 TS / B 3.1-25 Revision 1 PPL Rev. 4 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 7.5% of the control rods in the sample tested are determined to be "slow." With more than 7.5% of the sample declared to be "slow" per the criteria in Table 3.1.4-1, additional control rods are tested until this 7.5% criterion (e.g., 7.5% 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 200 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)

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-UNIT 1 TS / B 3.1-26 Revision 1 PPL Rev. 4 Control Rod Scram Times B 3.1.4 BASES REQUIREMENTS SR 3.1.4.3 (continued)

SURVEILLANCE 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 one 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.I 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)

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-UNIT 1 TS / B 3.1-27 Revision 1 PPL Rev. 4 Control Rod Scram Times B 3.1.4 BASES REFERENCES (continued)

4. FSAR, Section 15.0.5. FSAR, Section 15.4.9.6. 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 1 TS / B 3.1-28 Revision 2