ML100890542

Technical Requirements Manual, Revision 56

ML100890542
Person / Time
Site:	Susquehanna
Issue date:	03/17/2010
From:	Susquehanna
To:	Gerlach R Document Control Desk, Office of Nuclear Reactor Regulation
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Mar. 17, 2010 Page 1 of 2 MANUAL HARD COPY DISTRIBUTION DOCUMENT TRANSMITTAL 2010-11075 USER INFORMATION:

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

TO: GERLACH*ROSE M 03/17/2010 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.

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DOCUMENTS TYPE: TRMl Mar. 17, 2010 Page 2 of 2 ID: TEXT 3.2.1 REMOVE: REV:10 ADD: REV: 11 CATEGORY: ID: TEXT REMOVE: DOCUMENTS TYPE: TRMI LOES REV:55 ADD: REV: 56 ANY DISCREPANCIES WITH THE MATERIAL PROVIDED, CONTACT DCS @ X3107 OR X3136 FOR ASSISTANCE.

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SSES MANUAL Manual Name: TRMI Manual Title: TECHNICAL REQUIREMENTS MANUAL UNIT 1 Table Of Contents Issue Date Procedure TEXT LOES Title: TEXT TOC Title: TEXT 1.1 Title: TEXT 2.1 Title: TEXT 2.2 Title: e C 3/16/2010 Name Rev Issue Date 56 03/16/2010 LIST OF EFFECTIVE SECTIONS Change ID Change Number TABLE OF CONTENTS USE AND APPLICATION PLANT PROGRAMS AND E PLANT PROGRAMS AND S 16 .04/16/2009 0 11/18/2002 DEFINITIONS 1 02/04/2005 8 TRIP SETPOINT TABLE LDCN 4414 TEXT 3.0 4 .0523/2008 Title: TECHNICAL REQUIREMENT FOR\OPERATION (TRO) APPLICABILITY

& SURVEILLANCE (TRS)APPLICABILITY TEXT 3.1.1 1 11/09/2007 Title: REACTIVITY CONTROL SYSTEMS ANTICIPATED TRANSIENT WITHOUT SCRAM ALTERNATE ROD(ATWS-ARI)

INSTRUMENTATION TEXT 3.1.2 0 11/18/2002 Title: REACTIVITY CONTROL SYSTEMS CONTROL ROD DRIVE (CRD) HOUSING SUPPORT TEXT 3.1.3 5 04/16/2009 Title: REACTIVITY CONTROL SYSTEMS CONTROL ROD BLOCK INSTRUMENTATION TEXT 3.1.4 0 11/18/2002 Title: REACTIVITY CONTROL SYSTEMS CONTROL ROD SCRAM ACCUMULATORS INSTRUMENTATION

&CHECK VALVE TEXT 3.2.1 11 03/16/2010 Title: CORE OPERATING LIMITS REPORT (COLR)Page 1 of 15 Report Date: 03/16/10 Page 1 of 15 Report Date: 03/16/10 SSES MANUAL Manual Name: TRMI Manual Title: TECHNICAL REQUIREMENTS MANUAL UNIT 1 TEXT 3.3.1 Title: INSTRUMENTATION 0 11/18/2002 RADIATION MONITORING INSTRUMENTATION TEXT 3.3.2 2 11/09/2007 Title: INSTRUMENTATION SEISMIC MONITORING INSTRUMENTATION TEXT 3.3.3 2 11/09/2007 Title: INSTRUMENTATION METEOROLOGICAL MONITORING INSTRUMENTATION TEXT 3.3.4 Title: INSTRUMENTATION TEXT 3.3.5 Title: INSTRUMENTATION TEXT 3.3.6 Title: INSTRUMENTATION TEXT 3.3.7 Title: INSTRUMENTATION.

TEXT 3.3.8 Title: INSTRUMENTATION TEXT 3.3.9 5 05/23/2008 TRM POST-ACCIDENT MONITORING INSTRUMENTATION 0 11/18/2002 THIS PAGE INTENTIONALLY LEFT BLANK 2 10/19/2005 TRM ISOLATION ACTUATION INSTRUMENTATION 1 11/09/2007 MAIN TURBINE OVERSPEED PROTECTION SYSTEM 1 10/22/2003 TRM RPS INSTRUMENTATION 3 04/17/2008 Title: OPRM INSTRUMENTATION CONFIGURATION TEXT 3.3.10 1 12/14/2004 Title: INSTRUMENTATION REACTOR RECIRCULATION PUMP MG SET STOPS TEXT 3.3.11 1 10/22/2003 Title: INSTRUMENTATION MVP ISOLATION INSTRUMENTATION TEXT 3.3.12 0 04/16/2009 Title: WATER MONITORING INSTRUMENTATION Page Z of 15 Report Date: 03/16/10 Page 2 of 15 Report Date: 03/16/10 SSES MANUAL Manual Name: TRMI Manual Title: TECHNICAL REQUIREMENTS MANUAL UNIT 1 TEXT 3. 4.1 Title: REACTOR TEXT 3.4.2 Title: REACTOR TEXT 3.4.3 Title: REACTOR TEXT 3.4.4 Title: REACTOR TEXT 3.4.5 Title: REACTOR TEXT 3.5.1 1 04/26/2006 COOLANT SYSTEM REACTOR COOLANT SYSTEM CHEMISTRY 1 04/16/2009 COOLANT SYSTEM STRUCTURAL INTEGRITY 1 11/09/2007 COOLANT SYSTEM HIGH/LOW PRESSURE INTERFACE LEAKAGE MONITORS 2 04/17/2008 COOLANT SYSTEM REACTOR RECIRCULATION FLOW AND ROD LINE LIMIT 1 04/26/2006 COOLANT SYSTEM REACTOR VESSEL MATERIALS 1 02/04/2005 Title: EMERGENCY CORE COOLING AND RCIC ADS MANUAL INHIBIT TEXT 3.5.2 1 11/09/2007 Title: EMERGENCY CORE COOLING AND RCIC ECCS AND RCIC SYSTEM MONITORING INSTRUMENTATION TEXT 3.5.3 0 11/18/2002 Title: EMERGENCY CORE COOLING AND RCIC LONG TERM NITROGEN SUPPLY TO ADS TEXT 3.6.1 0 11/18/2002 Title: CONTAINMENT VENTING OR PURGING TEXT 3.6.2 0 11/18/2002 Title: CONTAINMENT SUPPRESSION CHAMBER-TO-DRYWELL VACUUM BREAKER POSITION INDICATION TEXT 3.6.3 0 11/18/2002 Title: CONTAINMENT SUPPRESSION POOL ALARM INSTRUMENTATION

' TEXT 3.6.4 0 11/18/2002 Title: CONTAINMENT PRIMARY CONTAINMENT CLOSED SYSTEM BOUNDARIES Page 3 of 15 Report Date : 03/16/10 SSES MANUAL Manual Name: TRM1 Manual Title: TECHNICAL REQUIREMENTS MANUAL UNIT 1 TEXT 3.7.1 Title: PLANT TEXT 3.7.2 Title: PLANT TEXT 3.7.3.1 Title: PLANT TEXT 3.7.3.2 Title: PLANT TEXT 3.7.3.3 Title: PLANT TEXT 3.7.3.4 Title: PLANT'TEXT 3.7.3.5 Title: PLANT TEXT 3.7.3.6 Title: PLANT TEXT 3.7.3.7 Title: PLANT TEXT 3.7.3.8 Title: PLANT TEXT 3.7.4 Title: PLANT 0 11/18/2002 SYSTEMS EMERGENCY SERVICE WATER SYSTEM (ESW) SHUTDOWN 0 11/18/2002 SYSTEMS ULTIMATE HEAT SINK (UHS) AND GROUND WATER LEVEL 2 04/16/2009 SYSTEMS FIRE SUPPRESSION WATER SUPPLY SYSTEM 3 04/16/2009 SYSTEMS SPRAY AND SPRINKLER SYSTEMS 3 SYSTEMS C02 SYSTEMS 2 SYSTEMS HALON SYSTEMS 04/16/2009 04/16/2009 2 04/16/2009 SYSTEMS FIRE HOSE STATIONS 2 04/16/2009 SYSTEMS YARD FIRE HYDRANTS AND HYDRANT HOSE HOUSES 1 04/26/2006 SYSTEMS FIRE RATED ASSEMBLIES 7 01/20./2010 SYSTEMS FIRE DETECTION INSTRUMENTATION LDCN 3503 1 04/26/2006 SYSTEMS SOLID RADWASTE SYSTEM TEXT 3.7.5.1 Title: PLANT 0 11/18/2002 SYSTEMS MAIN CONDENSER OFFGAS HYDROGEN MONITOR Page 4 of 15 Report Date: 03/16/10 Page4 of 15 Report Date: 03/16/10 SSES MANUAL* Manual Name: TRM1 Manual Title: TECHNICAL REQUIREMENTS MANUAL UNIT 1 TEXT 3.7.5.2 0 11/18/2002 Title: PLANT SYSTEMS MAIN CONDENSER OFFGAS EXPLOSIVE GAS MIXTURE TEXT 3.7.5.3 1 04/26/2006 Title: PLANT SYSTEMS LIQUID HOLDUP TANKS TEXT 3.7.6 2 06/27/2008 Title: PLANT SYSTEMS ESSW PUMPHOUSE VENTILATION TEXT 3.7.7 2 09/05/2008 Title: PLANT SYSTEMS MAIN CONDENSER OFFGAS PRETREATMENT LOGARITHMIC RADIATION MONITORING TEXT 3.7.8 4 06/21/2007 Title: PLANT SYSTEMS SNUBBERS TEXT 3..7.9 1 08/28/2006 Title: PLANT SYSTEMS CONTROL STRUCTURE HVAC TEXT 3.7.10 1 12/14/2004 Title: PLANT SYSTEMS SPENT FUEL STORAGE POOLS (SFSPS)TEXT 3.7.11 Title: STRUCTURAL TEXT 3.8.1 Title: ELECTRICAL PROTECTIVE TEXT 3.8.2.1 Title: ELECTRICAL CONTINUOUS TEXT 3.8.2.2 Title: ELECTRICAL AUTOMATIC TEXT 3.8.3 Title: ELECTRICAL 0 04/16/2009 INTEGRITY 1 02/04/2005 POWER PRIMARY CONTAINMENT PENETRATION CONDUCTOR OVERCURRENT DEVICES LDCN 4760 2 11/09/2007 POWER MOTOR OPERATED VALVES (MOV) THERMAL OVERLOAD PROTECTION

-2 12/14/2004 POWER MOTOR OPERATED VALVES (MOV) THERMAL OVERLOAD PROTECTION

-0 11/18/2002 POWER DIESEL GENERATOR (DG) MAINTENANCE ACTIVITIES Page ~ of 15 Report Date: 03/16/10 Page5 of 1_55 Report Date: 03/16/10 SSESMANUAL Manual Name: TRMI 4 Manual Title: TECHNICAL REQUIREMENTS MANUAL UNIT 1 TEXT 3.8.4 0 11/18/2002 Title: ELECTRICAL POWER 24 VDC ELECTRICAL POWER SUBSYSTEM TEXT 3.8.5 0 11/18/2002 Title: ELECTRICAL POWER DEGRADED VOLTAGE PROTECTION TEXT 3.8.6 0 11/18/2002 Title: ELECTRICAL POWER EMERGENCY SWITCHGEAR ROOM COOLING TEXT 3.8.7 1 06/15/2009 Title: BATTERY MAINTENANCE AND MONITORING PROGRAM TEXT 3.9.1 0 11/18/2002 Title: REFUELING OPERATIONS DECAY TIME-TEXT 3.9.2 0 11/18/2002 Title: REFUELING OPERATIONS COMMUNICATIONS TEXT 3.9.3 0 11/18/2002 Title: REFUELING OPERATIONS REFUELING PLATFORM TEXT 3.10.1 1 04/26/2006 Title: MISCELLANEOUS SEAL SOURCE CONTAMINATION TEXT 3.10.2 2 08/08/2006 Title: MISCELLANEOUS SHUTDOWN MARGIN TEST RPS INSTRUMENTATION TEXT 3.10.3 1 04/26/2006 Title: MISCELLANEOUS INDEPENDENT SPENT FUEL STORAGE INSTALLATION (ISFSI)TEXT 3.10.4 2 04/17/2008 Title: MISCELLANEOUS LEADING EDGE FLOW METER (LEFM)TEXT 3.11.1.1 1 04/26/2006 Title: RADIOACTIVE EFFLUENTS LIQUID EFFLUENTS CONCENTRATION Page 6 of 15 Report Date: 03/16/10 SSES MANUAL Manual Name: TRMI1 Manual Title: TECHNICAL REQUIREMENTS MANUAL UNIT 1 TEXT 3.11.1.2 Title: RADIOACTIVE TEXT 3.11.1.3 Title: RADIOACTIVE TEXT 3.11.1.4 Title: RADIOACTIVE TEXT 3.11.1.5 Title: RADIOACTIVE TEXT 3.11.2.1 Title: RADIOACTIVE TEXT 3.11.2..2 Title: RADIOACTIVE TEXT 3.11.2.3 Title: RADIOACTIVE FORM TEXT 3.11.2.4 Title: RADIOACTIVE TEXT 3.11.2.5 Title: RADIOACTIVE TEXT 3.11.2.6 Title: RADIOACTIVE TEXT 3.11.3 Title: RADIOACTIVE TEXT 3.11.4.1 Title: RADIOACTIVE 1 04/26/2006 EFFLUENTS LIQUID EFFLUENTS DOSE.1 04/26/2006 EFFLUENTS LIQUID WASTE TREATMENT SYSTEM EFFLUENTS EFFLUENTS EFFLUENTS EFFLUENTS EFFLUENTS EFFLUENTS EFFLUENTS EFFLUENTS 1 12/14/2004 LIQUID RADWASTE EFFLUENT MONITORING INSTRUMENTATION 2 05/02/2007 RADIOACTIVE LIQUID PROCESS MONITORING INSTRUMENTATION 3 04/26/2006 DOSE RATE 1 04/26/2006 DOSE -NOBLE GASES 1 04/26/2006 DOSE -IODINE, TRITIUM, AND RADIONUCLIDES IN PARTICULATE 0 11/18/2002 GASEOUS RADWASTE TREATMENT SYSTEM 3 11/14/2006 VENTILATION EXHAUST TREATMENT SYSTEM 4 09/16/2009 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION 1 04/26/2006 EFFLUENTS TOTAL DOSE 4 08/08/2006 EFFLUENTS MONITORING PROGRAM Page 2 of 15 Report Date: 03/16/10 Page 7 of 15 Report Date: 03/16/10 SSES MANUTAL Manual Name: TRM1 Manual Title: TECHNICAL REQUIREMENTS MANUAL UNIT 1 TEXT 3.11.4.2 2 04/26/2006 Title: RADIOACTIVE EFFLUENTS LAND USE CENSUS TEXT 3.11.4.3 1 04/26/2006 Title: RADIOACTIVE EFFLUENTS INTERLABORATORY COMPARISON PROGRAM TEXT 3.12.1 0 11/19/2002 Title: LOADS CONTROL PROGRAM CRANE TRAVEL-SPENT FUEL POOL STORAGE POOL TEXT 3.12.2 4 04/17/2008 Title: LOADS CONTROL PROGRAM HEAVY LOADS REQUIREMENTS TEXT 3.12.3 0 11/19/2002 Title: LOADS CONTROL PROGRAM LIGHT LOADS REQUIREMENT

ý. 0 TEXT 4.1 Title: TEXT 4.2 Title: TEXT 4.3 Title: TEXT 4.4 Title: TEXT 4.5 Title: TEXT 4.6 Title: TEXT 4.7 Title: 0 08/31/1998 CONTROLS ORGANIZATION ADMINISTRATIVE ADMINISTRATIVE CONTROLS*0 ADMINISTRATIVE CONTROLS 1 ADMINISTRATIVE CONTROLS 0 ADMINISTRATIVE CONTROLS 0 ADMINISTRATIVE CONTROLS 0 ADMINISTRATIVE CONTROLS 08/31/1998 REPORTABLE EVENT ACTION 08/31/1998 SAFETY LIMIT VIOLATION 12/18/2008 PROCEDURES

& PROGRAMS 08/31/1998 REPORTING REQUIREMENTS 08/31/1998 RADIATION PROTECTION PROGRAM 08/31/1998 TRAINING Page ~ of 15 Report Date: 03/16/10 Page 8 of 15 Report Date: 03/16/10 SSES MANUAL Manual Name: TRM1 Manual Title: TECHNICAL REQUIREMENTS MANUAL UNIT 1 TEXT B3.0 4 05/23/2008 Title: APPLICABILITY BASES TECHNICAL REQUIREMENT FOR OPERATION (TRO) APPLICABILITY TEXT B3.1.1 1 11/09/2007 Title: REACTIVITY CONTROL SYSTEMS BASES ANTICIPATED TRANSIENT WITHOUT SCRAM ALTERNATE ROD INJECTION (ATWS-ARI)

INSTRUMENTATION TEXT B3.1.2 0 11/19/2002 Title: REACTIVITY CONTROL SYSTEMS BASES CONTROL ROD DRIVE (CRD) HOUSING SUPPORT TEXT B3.1.3 3 03/31/2006 Title: REACTIVITY CONTROL SYSTEMS BASES CONTROL ROD BLOCK INSTRUMENTATION TEXT B3.1.4 0 11/19/2002 Title: REACTIVITY CONTROL SYSTEMS BASES CONTROL ROD SCRAM ACCUMULATORS INSTRUMENTATION AND CHECK VALVE TEXT B3.2.1 0 11/19/2002 Title: CORE OPERATING LIMITS BASES CORE OPERATING LIMITS REPORT (COLR)>TEXT B3.3.1 Title: INSTRUMENTATION TEXT B3.3.2 Title: INSTRUMENTATION TEXT B3.3.3 Title: INSTRUMENTATION TEXT B3.3.4 Title: INSTRUMENTATION TEXT B3.3.5 Title: INSTRUMENTATION TEXT B3.3.6 Title: INSTRUMENTATION 0 11/19/2002 BASES RADIATION MONITORING INSTRUMENTATION 1 11/09/2007 BASES SEISMIC MONITORING INSTRUMENTATION 3 12/18/2008 BASES METEOROLOGICAL MONITORING INSTRUMENTATION 3 11/09/2007 BASES TRM POST ACCIDENT MONITORING (PAM) INSTRUMENTATION 2 11/09/2007 BASES THIS PAGE INTENTIONALLY LEFT BLANK 3 10/19/2005 BASES TRM ISOLATION ACTUATION INSTRUMENTATION Page ~. of 15 Report Date: 03/16/10 Page 9 of 15 Report Date: 03/16/10 SSES MANUAL Manual Name: TRM1 Manual Title: TECHNICAL REQUIREMENTS MANUAL UNIT 1 TEXT B3.3.7 Title: INSTRUMENTATION BASES TEXT B3.3.8 Title: INSTRUMENTATION BASES TEXT B3.3.9 Title: OPRM INSTRUMENTATION 1 11/09/2007 MAIN TURBINE OVERSPEED PROTECTION SYSTEM 1 10/22/2003 TRM REACTOR PROTECTION SYSTEM (RPS) INSTRUMENTATION

'3 04/17/2008 TEXT B3.3.10 1 12/18/2008 Title: INSTRUMENTATION BASES REACTOR RECIRCULATION PUMP MG SET STOPS TEXT B3.3.11 1 10/22/2003 Title: INSTRUMENTATION BASES MVP ISOLATION INSTRUMENTATION TEXT B3.3.12 0 04/16/2009 Title: WATER MONITORING INSTRUMENTATION TEXT B3.4.1 0 11/19/2002 Title: REACTOR COOLANT SYSTEM BASES REACTOR COOLANT SYSTEM CHEMISTRY TEXT B3.4.2 1 04/16/2009 Title: REACTOR COOLANT SYSTEM BASES STRUCTURAL INTEGRITY TEXT B3.4.3 1 11/09/2007 Title: REACTOR COOLANT SYSTEM BASES HIGH/LOW PRESSURE INTERFACE LEAKAGE MONITOR TEXT B3.4.4 0 11/19/2002 Title: REACTOR COOLANT SYSTEM BASES REACTOR RECIRCULATION FLOW AND ROD LINE LIMIT TEXT B3.4.5 0 11/19/2002 Title: REACTOR COOLANT SYSTEM BASES REACTOR VESSEL MATERIALS TEXT B3.5.1 0 11/19/2002 Title: ECCS AND RCIC BASES ADS MANUAL INHIBIT Page ~ of 15 Report Date: 03/16/10 Page 10 of 15 Report Date: 03/16/10 SSES MANUAL Manual Name: TRMl Manual Title: TECHNICAL REQUIREMENTS MANUAL UNIT 1 TEXT B3.5.2 1 11/09/2007 Title: ECCS AND RCIC BASES ECCS AND RCIC SYSTEM MONITORING INSTRUMENTATION TEXT B3.5.3 1 11/09/2007 Title: ECCS AND RCIC BASES LONG TERM NITROGEN SUPPLY TO ADS TEXT B3.6.1 0 11/19/2002 Title: CONTAINMENT BASES VENTING OR PURGING TEXT B3.6.2 0 11/19/2002 Title: CONTAINMENT BASES SUPPRESSION CHAMBER-TO-DRYWELL VACUUM BREAKER POSITION INDICATION TEXT B3.6.3 2 04/17/2008 Title: CONTAINMENT BASES SUPPRESSION POOL ALARM INSTRUMENTATION LDCN 3933 TEXT B3.6.4 1 12/14/2004 Title: CONTAINMENT BASES PRIMARY CONTAINMENT CLOSED SYSTEM BOUNDARIES TEXT B3.7.1 Title: PLANT TEXT B3.7.2 Title: PLANT TEXT B3.7.3.1 Title: PLANT TEXT B3.7.3.2 Title: PLANT TEXT B3.7.3.3 Title: PLANT TEXT B3.7.3.4 Title: PLANT SYSTEMS BASES SYSTEMS BASES SYSTEMS BASES SYSTEMS BASES SYSTEMS BASES SYSTEMS BASES 0 11/19/2002 EMERGENCY SERVICE WATER SYSTEM (SHUTDOWN) 0 11/19/2002 ULTIMATE HEAT SINK (UHS) GROUND WATER LEVEL 2 01/07/2008 FIRE SUPPRESSION WATER SUPPLY SYSTEM 2 04/26/2006 SPRAY AND SPRINKLER SYSTEMS 0 11/19/2002 C02 SYSTEMS 1 04/26/2006 HALON SYSTEMS Page jj of 15 Report Date: 03/16/10 Page 11 of .15 Report Date: 03/16/10 SSES MANUAL Manual Name: TRMI Manual Title: TECHNICAL REQUIREMENTS MANUAL UNIT 1 TEXT B3.7.3.5 Title: PLANT TEXT B3.7.3.6 Title: PLANT TEXT B3.7.3.7 Title: PLANT TEXT B3.7.3.8 Title: PLANT TEXT B3.7.4 Title: PLANT TEXT B3.7.5.1 Title: PLANT TEXT B3.7.5.2 Title: PLANT TEXT B3.7.5.3 Title: PLANT TEXT B3.7.6 Title: PLANT 1 04/26/2006 SYSTEMS BASES FIRE HOSE STATIONS 1 04/26/2006 SYSTEMS BASES YARD FIRE HYDRANTS AND HYDRANT HOSE HOUSES 0 11/19/2002 SYSTEMS BASES FIRE RATED ASSEMBLIES 1 01/12/2004 SYSTEMS BASES FIRE DETECTION INSTRUMENTATION 0 11/19/2002 SYSTEMS BASRS SOLID RADWASTE SYSTEM 0 11/19/2002 SYSTEMS BASES MAIN CONDENSER OFFGAS HYDROGEN MONITOR 0 11/19/2002 SYSTEMS BASES MAIN CONDENSER OFFGAS EXPLOSIVE GAS MIXTURE 0 11/19/2002 SYSTEMS BASES LIQUID HOLDUP TANKS 2 06/27/2008 SYSTEMS BASES ESSW PUMPHOUSE VENTILATION TEXT B3.7.7 2 01/31/2008 Title: PLANT SYSTEMS BASES MAIN CONDENSER OFFGAS PRETREATMENT LOGARITHMIC RADIATION MONITORING INSTRUMENTATION TEXT B3.7.8 3 06/21/2007 Title: PLANT SYSTEMS BASES SNUBBERS TEXT B3.7.9 1 12/14/2004 Title: PLANT SYSTEMS BASES CONTROL STRUCTURE HVAC Page 12 of 15 Report Date: 03/16/10 SSES MANUAL Manual Name: TRMI 10. Manual Title: TECHNICAL REQUIREMENTS MANUAL UNIT 1 TEXT B3.7.10 1 12/14/2004 Title: PLANT SYSTEMS BASES SPENT FUEL STORAGE POOLS TEXT B3.7.11 Title: STRUCTURAL TEXT B3.8.1 Title: ELECTRICAL PROTECTIVE TEXT B3.8.2.1 Title: ELECTRICAL CONTINUOUS TEXT B3.8.2.2 Title: ELECTRICAL AUTOMATIC TEXT B3.8.3 Title: ELECTRICAL TEXT B3.8.4 Title: ELECTRICAL TEXT B3.8.5 Title: ELECTRICAL TEXT B3.8.6 Title: ELECTRICAL 0 04/16/2009 INTEGRITY 2 03/10/2010 POWER BASES PRIMARY CONTAINMENT PENETRATION CONDUCTOR OVERCURRENT DEVICES 0 11/19/2002 POWER BASES MOTOR OPERATED VALVES (MOV) THERMAL OVERLOAD PROTECTION

-1 09/17/2004 POWER BASES MOTOR OPERATED VALVES (MOV) THERMLAL OVERLOAD PROTECTION

-0 11/19/2002 POWER BASES DIESEL GENERATOR (DG) MAINTENANCE ACTIVITIES 0 11/19/2002 POWER BASES 24 VDC ELECTRICAL POWER SUBSYSTEM 0 11/19/2002 POWER BASES DEGRADED VOLTAGE PROTECTION 1 02/04/2005 POWER BASES EMERGENCY SWITCHGEAR ROOM COOLING TEXT B3.8.7 1 06/15/2009 Title: BATTERY MAINTENANCE AND MONITORING PROGRAM TEXT B3.9.1 0 11/19/2002 Title: REFUELING OPERATIONS BASES DECAY TIME TEXT B3.9.2 0 11/19/2002 Title: REFUELING OPERATIONS BASES COMMUNICATIONS Page fl of 15 Report Date: 03/16/10 Page 13 of .15 Report Date: 03/16/10 SSES MANUJAL Manual Name: TRM1 Manual Title: TECHNICAL REQUIREMENTS MANUAL UNIT 1 TEXT B3.9.3 0 11/19/2002 Title: REFUELING OPERATIONS BASES REFUELING PLATFORM TEXT B3.10.1 0 11/19/2002 Title: MISCELLANEOUS BASES SEALED SOURCE CONTAMINATION TEXT B3.10.2 1 03/31/2006 Title: MISCELLANEOUS BASES SHUTDOWN MARGIN TEST RPS INSTRUMENTATION TEXT B3.10.3 0 11/19/2002 Title: MISCELLANEOUS BASES INDEPENDENT SPENT FUEL STORAGE INSTALLATION (ISFSI)TEXT B3.10.4 1 04/17/2008-Title: MISCELLANEOUS BASES LEADING EDGE FLOW METER (LEFM)TEXT B3.11.1.1 Title: RADIOACTIVE TEXT B3.11.1.2 Title: RADIOACTIVE TEXT B3.11.1.3 Title: RADIOACTIVE TEXT B3.11.1.4 Title: RADIOACTIVE TEXT B3.11.1.5 Title: RADIOACTIVE EFFLUENTS EFFLUENTS EFFLUENTS EFFLUENTS EFFLUENTS 0 11/19/2002 0 BASES LIQUID EFFLUENTS CONCENTRATION 0 11/19/2002 BASES LIQUID EFFLUENTS DOSE 0 11/19/2002 BASES LIQUID WASTE TREATMENT SYSTEM 0 11/19/2002 BASES LIQUID RADWASTE EFFLUENT MONITORING INSTRUMENTATION 0 11/19/2002 BASES RADIOACTIVE LIQUID PROCESS MONITORING INSTRUMENTATION TEXT B3.11.2.1 1 Title: RADIOACTIVE EFFLUENTS BASES TEXT B3.11.2.2 0 Title: RADIOACTIVE EFFLUENTS BASES 12/14/2004 DOSE RATE 11/19/2002 DOSE -NOBLE GASES Page 24 of 15 Report Date: 03/16/10 Page 14 of 15 Report Date: 03/16/10 SSES MANUAL Manual Name: TRMI.Manual Title: TECHNICAL REQUIREMENTS MANUAL UNIT 1 TEXT B3.11.2.3 Title: RADIOACTIVE EFFLUENTS PARTICULATES FORM TEXT B3.11.2.4 Title: RADIOACTIVE EFFLUENTS TEXT B3.11.2.5 Title: RADIOACTIVE EFFLUENTS TEXT B3.11.2.6 Title: RADIOACTIVE EFFLUENTS INSTRUMENTATION 0 11/19/2002 BASES DOSE -IODINE, TRITIUM, AND RADIONUCLIDES IN 0 BASES 11/19/2002 GASEOUS RADWASTE TREATMENT SYSTEM 4 11/14/2006 BASES VENTILATION EXHAUST TREATMENT SYSTEM 1 01/27/2004 BASES RADIOACTIVE GASEOUS EFFLUENT MONITORING TEXT B3.11.3 0 11/19/2002 Title: RADIOACTIVE EFFLUENTS BASES TOTAL DOSE TEXT B3.11.4.1 Title: RADIOACTIVE EFFLUENTS 2 01/06/2006 BASES MONITORING PROGRAM TEXT B3.11.4.2 0 11/19/2002 Title: RADIOACTIVE EFFLUENTS BASES LAND USE CENSUS TEXT B3.11.4.3 0 11/19/2002 Title: RADIOACTIVE EFFLUENTS BASES INTERLABORATORY COMPARISON PROGRAM TEXT B3.12.1 1 10/04/2007 Title: LOADS CONTROL PROGRAM BASES CRANE TRAVEL-SPENT FUEL STORAGE POOL TEXT B3.12.2 Title: LOADS CONTROL PROGRAM TEXT B3.12.3 Title: LOADS CONTROL PROGRAM 0 BASES 11/19/2002 HEAVY LOADS REQUIREMENTS 0 11/19/2002 BASES LIGHT LOADS REQUIREMENTS Page 15. of 15 Report Date: 03/16/10 Page 15 of 15 Report Date: 03/16/10 SUSQUEHANNA STEAM ELECTRIC STATION PPL Rev. 56 LIST OF EFFECTIVE SECTIONS (TECHNICAL REQUIREMENTS MANUAL)Section Title TOC TABLE OF CONTENTS 1.0 2.0 USE AND APPLICATION Pages TRM / 1.0-1 through TRM / 1.0-3 PLANT PROGRAMS Page 2.0-1 Pages TRM / 2.0-2 and TRM / 2.0-3 Page TRM / 2.0-4 Page TRM / 2.0-5 Page TRM / 2.0-6 Page TRM / 2.0-7 Page TRM / 2.0-8 Page TRM / 2.0-9-Page TRM / 2.0-10 Page TRM / 2.0-11 Page TRM / 2.0-12 Pages TRM / 2.0-13 and TRM / 2.0-14 Page TRM / 2.0-15 3.0 APPLICABILITY Page TRM / 3.0-1 Page TRM / 3.0-2 Page TRM / 3.0-3 Page TRM / 3.0-4 Effective Date 04/07/2009 10/04/2002 08/31/1998 01/28/2005 06/25/2002 04/02/1999 03/27/2008 05/15/2008 03/27/2008 11/15/2004 02/02/2010 11/15/2004 03/27/2008 11/15/2004 11/15/2005 04/14/2008 04/12/2007 03/15/2002 11/30/2005 10/31/2007 08/31/1998 03/22/2006 04/07/2009 03/27/2008 02/18/1999 02/18/1999 07/07/1999 03/11/2010 07/16/1999 10/31/2007 08/31/1998 10/31/2007 08/31/1998 04/12/2007 3.1 3.2 REACTIVITY CONTROL SYSTEMS Page TRM / 3.1-1 Pages TRM / 3.1-2 through TRM / 3.1-5 Page TRM / 3.1-6 Page TRM / 3.1-7 Page TRM / 3.1-8 Pages TRM / 3.1-9 and TRM / 3.1-9a Page TRM / 3.1-10 CORE OPERATING LIMITS REPORT Page TRM / 3.2-1 Pages TRM / 3.2-2 through TRM / 3.2-54 INSTRUMENTATION Pages TRM / 3.3-1 through TRM / 3.3-3 Page TRM / 3.3-4 and TRM / 3.3-5 Page TRM / 3.3-6 Page TRM / 3.3-7 Page 3.3-8 Page TRM / 3.3-9 3.3 SUSQUEHANNA

-UNIT I TRM / LOES-1 EFFECTIVE DATE 03/11/2010 SUSQUEHANNA STEAM ELECTRIC STATION PPL Rev. 56 LIST OF EFFECTIVE SECTIONS (TECHNICAL REQUIREMENTS MANUAL)Section Title Effective Date 3.4 Page TRM / 3.3-9a Page TRM / 3.3-10 Page TRM / 3.3-11 Page TRM / 3.3-1 Ia Page TRM / 3.3-12 Page TRM / 3.3-13 Page TRM / 3.3-14 Page TRM / 3.3-15 Page TRM / 3.3-16 Page TRM / 3.3-17 Page TRM / 3.3-18 Pages TRM / 3.3-19 through TRM / 3.3-21 Page TRM /.3.3-22 Page TRM / 3.3-22a Pages TRM / 3.3-22b through TRM / 3.3-22d Page TRM / 3.3-23 Pages TRM / 3.3-24 and TRM / 3.3-25 Page TRM / 3.3-26 Pages TRM / 3.3-27 and TRM / 3.3-28 REACTOR COOLANT SYSTEM Page TRM / 3.4-1 Pages 3.4-2 through 3.4-5 Pages TRM / 3.4-6 through TRM / 3.4-8 Page TRM / 3.4-9 Page TRM / 3.4-10 Page TRM / 3.4-11 Page TRM / 3.4-12 Page TRM / 3.4-13 EMERGENCY CORE COOLING AND RCIC Page TRM / 3.5-1 Pages 3.5-2 and 3.5-3 Pages TRM / 3.5-4 and TRM / 3.5-5 Pages 3.5-6 and 3.5-7 CONTAINMENT Pages 3.6-1 through 3.6-3 Page TRM / 3.6-4 Page 3.6-5 Pages TRM / 3.6-6 through TRM / 3.6-8 12/17/1998 10/31/2007 06/02/2005 04/14/2008 03/30/2001 09/13/2005 12/14/1998 10/22/2003 06/27/2001 06/14/2002 10/31/2007 10/22/2003 03/27/2008 11/15/2004 03/22/2006 12/03/2004 05/16/2003 10/22/2003 04/07/2009

'03/31/2006 10/23/1998 04/01/2009 08/31/1998 10/31/2007 08/31/1998 03/27/2008 03/31/2006 01/28/2005 08/31/1998 10/31/2007 08/31/1998 08/31/1998 01/07/2002 08/31/1998 12/31/2002 08/31/1998 03/31/2006 3-5 3.6 3.7 PLANT SYSTEMS Pages 3.7-1 through 3.7-3 Page TRM / 3.7-4 SUSQUEHANNA

-UNIT 1 TRM / LOES-2 EFFECTIVE DATE 03/11/2010 SUSQUEHANNA

-UNIT I TRM I LOES-2 EFFECTIVE DATE 03/11/2010 SUSQUEHANNA STEAM ELECTRIC STATION PPL Rev. 56 LIST OF EFFECTIVE SECTIONS (TECHNICAL REQUIREMENTS MANUAL)Section Title Effective Date Pages TRM / 3.7-5 Pages TRM / 3.7-6 through TRM / 3.7-8 Pages TRM / 3.7-9 and TRM / 3.7-10 Page TRM / 3.7-11 Page TRM / 3.7-12 Page TRM / 3.7.13 Page TRM / 3.7-14 Pages TRM / 3.7-15 and TRM / 3.7-16 Page TRM / 3.7-17 Page TRM / 3.7-18 Page TRM / 3.7-19 Pages TRM / 3.7-20 through TRM / 3.7-22 Page TRM / 3.7-23 Page TRM / 3.7-24 Pages TRM / 3.7-25 and TRM 3.7-26 Page TRM 3.7-27 Page TRM / 3.7-28 Page TRM / 3.7-29 Page TRM / 3.7-30 Pages TRM / 3.7-31 and TRM / 3.7-32 Page TRM / 3.7-33 Page TRM / 3.7-34 Page TRM / 3.7-34a Page TRM / 3.7-35 Pages TRM / 3.7-36 and TRM / 3.7-37 Pages 3.7-38 and 3.7-39 Page TRM / 3.7-40 Page TRM / 3.7-41 Page TRM / 3.7-41a Page TRM / 3.7-42 Page TRM / 3.7-43 Pages TRM / 3.7-44 through TRM / 3.7-46 Page TRM / 3.7-47 Page TRM / 3.7-48 Page TRM / 3.7-49 Page TRM / 3.7-50 Page TRM / 3.7-51 Page TRM / 3.7-52 Page TRM / 3.7-53 Page TRM / 3.7-54 Pages TRM / 3.7-55 through TRM 3.7-57 ELECTRICAL POWER Page TRM / 3.8-1 Pages TRM / 3.8-2 through TRM 3.8-4 04/07/2009 08/02/1999 04/07/2009 12/29/1999 08/02/1999 04/07/2009 08/09/2005 08/02/1999 04/07/2009 08/02/1999 04/07/2009 08/02/1999 04/07/2009 03/31/2006 08/02/1999 10/31/2007 11/29/2006 08/09/2005 01/13/2010 11/16/2001 01/09/2004 11/16/2001 10/05/2002 03/31/2006 02/01/1999 08/31/1998 03/31/2006 02/14/2005 06/20/2008 09/04/2008 08/31/1998 10/05/2006 06/07/2007 10/05/2006 0610712007 03/09/2001 08/16/2006 12/03/2004 04/15/2003 07/29/1999 04/01/2009 04/02/2002 01/28/2005 3.8 SUSQUEHANNA

-UNIT 1 TRM / LOES-3 EFFECTIVE DATE 03/11/2010 SUSQUEHANNA STEAM ELECTRIC STATION PPL Rev. 56 LIST OF EFFECTIVE SECTIONS (TECHNICAL REQUIREMENTS MANUAL)Section Title Pages TRM / 3.8-5 and TRM / 3.8-6 Page TRM / 3.8-7 Pages TRM / 3.8-8 through TRM / 3.8-10 Page TRM / 3.8-11 Page TRM / 3.8-12 Pages 3.8-13 and 3.8-14 Pages TRM / 3.8-15 through TRM / 3.8-17 Page 3.8-18 Page TRM / 3.8-19 Page 3.8-20 Pages TRM / 3.8-21 through TRM / 3.8-23 Pages 3.8-24 and 3.8-25 Page TRM / 3.8-26 Page TRM / 3.8-27 Pages TRM / 3.8-28 and TRM / 3.8-29 Effective Date 04/02/2002 10131/2007 12/03/2004 09/03/2004 12/03/2004 08/31/1998 04/02/2002 08/31/1998 04/02/2002 08/31/1998 06/06/1999 08/31/1998 05/28/2009 11/29/2006 05/28/2009 3.9 REFUELING OPERATIONS Pages 3.9-1 through 3.9-3 3.10 3.11 MISCELLANEOUS Page TRM / 3.10-1 Pages 3.10-2 and 3.10-3 Pages 3.10-2 and 3.10-3 Page TRM / 3.10-4 Pages TRM / 3.10-5 and TRM / 3.10-6 Page TRM / 3.10-7 RADIOACTIVE EFFLUENTS Page TRM / 3.11-1 Pages 3.11-2 and 3.11-3 Page TRM / 3.11-4 Page 3.11-5 Page TRM / 3.11-6 Pages TRM / 3.11-7 through TRM / 3.11-9 Page TRM / 3.11-10 Pages 3.11-11 and 3.11-12 Page TRM / 3.11-13 Page TRM / 3.11-14 Pages 3.11-15 and 3.11-16 Page TRM /3.11-17 Page 3.11-18 Page TRM / 3.11-19 Pages TRM / 3.11-20 and TRM / 3.11-21 Page TRM / 3.11-22 Page TRM /3.11-23 08/31/1998 03/31/2006 08/31/1998 08/31/1998 08/01/2006 03/22/2006 03/31/2006 03/31/2006 08/31/1998 03/31/2006 08/31/1998 03/31/2006 08/31/1998 12/03/2004 08/31/1998 04/12/2007 12/03/2004 09/01/1998 03/31/2006 08/31/1998 08/15/2005 03/31/2006 04/02/2002 11/14/2006 SUSQUEHANNA

-UNIT I TRM / LOES-4 EFFECTIVE DATE 03/11/2010 SSUSQUEHANNA

-UNIT 1 TRM I LOES-4 EFFECTIVE DATE 03/111/2010 SUSQUEHANNA STEAM ELECTRIC STATION PPL Rev. 56 LIST OF EFFECTIVE SECTIONS (TECHNICAL REQUIREMENTS MANUAL)Section Title Page TRM / 3.11-24 Page TRM / 3.11-25 Pages TRM / 3.11-26 and TRM / 3.11-27 Page TRM / 3.11-28 Page TRM / 3.11-29 Pages TRM / 3.11.30 through TRM /3.11.32 Page TRM / 3.11-33 Page 3.11-34 Page TRM / 3.11-35 Pages TRM / 3.11-36 through TRM / 3.11-39 Pages 3.11-40 through 3.11-43 Page TRM / 3.11-44 Page TRM / 3.11-45 Page 3.11-46 Page TRM / 3.11-47 LOADS CONTROL PROGRAM Pages TRM / 3.12-1 through TRM / 3.12-3 Page TRM / 3.12-4 Page TRM / 3.12-5 ADMINISTRATIVE CONTROLS Pages TRM / 4.0-1 through TRM / 4.0-3 Page TRM / 4.0-4 Pages TRM / 4.0-5 through TRM / 4.0-8 Effective Date 05/13/2005 04/12/2007 01/21/2004 09/08/2009 12/03/2004 01/21/2004 03/31/2006 08/31/1998 03/31/2006 11/30/2005 08/31/1998 08/01/2006 03/31/2006 08/31/1998 03/31/2006 02/05/1999" 03/14/2008 02/05/1999 3.12 4.0 08/31/1998 12/11/2008 08/31/1998-w SUSQUEHANNA

-UNIT 1 TRM / LOES-5 EFFECTIVE DATE 03/11/2010 SUSQUEHANNA STEAM ELECTRIC STATION PPL Rev. 56 LIST OF EFFECTIVE SECTIONS (TECHNICAL REQUIREMENTS MANUAL)Section Title Effective Date B 3.0 B 3.1 B 3.2 B 3.3 APPLICABILITY BASES Pages TRM / B 3.0-1 through TRM / B 3.0-3 Page TRM / B 3.0-4 Page TRM / B 3.0-5 Page TRM / B 3.0-6 Page TRM / B 3.0-7 Pages TRM / B 3.0-8 through TRM / B 3.'0-10 Pages TRM / B 3.0-11 and TRM / B 3.0-12 Pages TRM / B 3.0-13 and TRM / B 3.0-14 Page TRM / B 3.0-15 REACTIVITY CONTROL SYSTEMS BASES Page TRM / B 3.1-1 Pages TRM / B 3.1-2 and TRM / B 3.1-3 Page B 3.1-4 Page TRM / B 3.1-5 Pages TRM / B 3.1-6 and TRM / B 3.1-7 Page TRM / B 3.1-8 CORE OPERATING LIMITS BASES Page B 3.2-1 INSTRUMENTATION BASES Page TRM / B 3.3-1 Pages TRM / B 3.3-2 and TRM / B 3.3-2a Page TRM / B 3.3-3 Page TRM / B 3.3-3a Pages TRM / B 3.3-4 and TRM / B 3.3-5 Pages TRM / B 3.3-6 through TRM / B 3.3-9 Page B 3.3-10 Pages TRM / B 3.3-11 and TRM / B 3.3-12 Page TRM / B 3.3-13 Page TRM / B 3.3-14 Page TRM / B 3.3-14a Page TRM / B 3.3-14b Pages TRM / B 3.3-15 and TRM / B 3.3-16 Page TRM / B 3.3-17 Pages TRM / B 3.3-17a through TRM / B 3.3-17c Page TRM / B 3.3-17d Pages TRM / B 3.3-17e and TRM / B 3.3-17f Page TRM / B 3.3-18 Page TRM / B 3.3-19 Page TRM / B 3.3-20 Page TRM / B 3.3-21 Pages TRM / B 3.3-22 and TRM / B 3.3-23 08/31/1998 01/10/2007 04/14/2008 08/31/1998 04/12/2007 08/31/1998 03/15/2002 11/30/2005 03/15/2002 07/13/1999 10/31/2007 08/31/1998 11/15/2005 03/22/2006 02/18/1999 08/31/1998 04/07/2000 10/31/2007 12/11/2008 10/31/2007 05/30/2006 10/31/2007 08/31/1998 09/13/2005 12/03/2004 06/25/2002 10/31/2007 10/31/2007 10/22/2003 03/22/2006 03/22/2006 03/27/2008 03/22/2006 12/11/2008 05/16/2008 10/22/2003 05/16/2003 04/07/2009 SUSQUEHANNA

-UNIT I TRM / LOES-6 EFFECTIVE DATE 03/11/2010 SUSQUEHANNA

-UNIT 1 TRM /LOES-6 EFFECTIVE DATE 03/11/2010 SUSQUEHANNA STEAM ELECTRIC STATION PPL Rev. 56 LIST OF EFFECTIVE SECTIONS (TECHNICAL REQUIREMENTS MANUAL)Section Title Effective Date B 3.4 B 3.5 B 3.6 B 3.7 REACTOR COOLANT SYSTEM BASES Page B 3.4-1 Pages TRM / B 3.4-2 and TRM / B 3.4-3 Pages TRM / B 3.4-4 and TRM / B 3.4-4a Page TRM / B 3.4-5 Page B 3.4-6 ECCS AND RCIC BASES Pages B 3.5-1 and B 3.5-2 Pages TRM / B 3.5-3 through TRM / B 3.5-5 CONTAINMENT BASES Page TRM / B 3.6-1 Page TRM / B 3.6-2 Page B 3.6-3 Page TRM / B 3.6-4 Page TRM / B 3.6-5 Page TRM / B 3.6-6 Pages B.3.6-7 through TRM / B 3.6-11 PLANT SYSTEMS BASES Pages B 3.7-1 and B 3.7-2 Pages TRM / B 3.7-3 and TRM / B 3.7-3a Page TRM / B 3.7-4 Page TRM / B 3.7-5 Page TRM / B 3.7-6 Pages TRM / B 3.7-7 and TRM / B 3.7-7a Page TRM / B 3.7-8 Page TRM / B 3.7-9 Page TRM I B 3.7-10 Page TRM / B 3.7-1Oa Page TRM / B 3.7-11 Page TRM / B 3.7-11a Pages TRM / B 3.7-12 through T\RM / B 3.7-14 Page TRM / B 3.7-14a Page TRM / B 3.7-14b Pages TRM / B 3.7-15 and TRM / B 3.7-16 Pages B 3.7-17 through B 3.7-20 Page TRM / B 3.7-21 Page TRM / B 3.7-21a Page TRM / B 3.7-22 and TRM / B 3.7-23 Pages TRM / B 3.7-24 through TRM / B 3.7-28 Pages TRM / B 3.7-29 and TRM / B 3.7-30 Pages TRM / B 3.7-30a and TRM / B 3.7-30b Page TRM / B 3.7-31 Page TRM / B 3.7-32 08/31/1998 04/01/2009 10/31/2007 10/15/1999 08/31/1998 08/31/1998 10/31/2007 07/26/2001 02/01/1999 08/31/1998 03/27/2008 04/04/2007 12/03/2004 12/31/2002 08/31/1998 12/27/2007 03/31/2006 08/02/1999 03/31/2006 08/02/1999 08/02/1999 03/31/2006 08/02/1999 03/31/2006 08/02/1999 03/31/2006 08/02/1999 08/02/1999 01/09/2004 02/01/1999 08/31/1998 02/14/2005 06/20/2008 01/30/2008 10/05/2006 06/07/2007 10/05/2006 12/03/2004 03/09/2001 SUSQUEHANNA

-UNIT 1 TRM / LOES-7 EFFECTIVE DATE 03/11/2010 SUSQUEHANNA

-UNIT 1 TRM / LOES-7 EFFECTIVE DATE 03/11/2010 SUSQUEHANNA STEAM ELECTRIC STATION PPL Rev. 56 LIST OF EFFECTIVE SECTIONS (TECHNICAL REQUIREMENTS MANUAL)Section Title Effective Date B 3.8 B.3.9 Page TRM / B 3.7-33 Page TRM / B 3.7-34 Page TRM / B 3.7-35 Pages TRM / B 3.7-36 through TRM / B 3.7-40 ELECTRICAL POWER BASES Page TRM / B 3.8-1 Pages TRM / B 3.8-2 and TRM / B 3.8-2 Page TRM / B 3.8-2a Page TRM / B 3.8-3 Page TRM / B 3.8-3a Page TRM / B 3.8-4 Page TRM / B 3.8-4a Page TRM / B 3.8-5 Pages TRM / B 3.8-6 through TRM / B 3.8-16 Page TRM / B 3.8-17 Pages TRM / B 3.8-18 through TRM / B 3.8-20 Pages TRM / B 3.8-21 through TRM / B 3.8-24 REFUELING OPERATIONS BASES Pages B 3.9-1 through-B 3.9-7 B 3.10 MISCELLANEOUS BASES-Page B 3.10-1 Pages TRM / B 3.10-2 and TRM / B 3.10-3 Pages TRM / B 3.10-4 and TRM / B 3.10-5 B 3.11 RADIOACTIVE EFFLUENTS BASES Pages B 3.11-1 through B 3.11-9 Page TRM / B 3.11-10 Pages TRM/B 3.11-11 and TRM/B 3.11-11 a Pages TRM/B 3.11-12 and TRM/B 3.11-13 Page TRM / B 3.11-14 Page TRM / B 3.11-15 Pages B 3.11-16 through B 3.11-19 Page TRM / B 3.11-20 Page TRM / B 3.11-20a Page TRM / B 3.11-21 Pages TRM / B 3.11-22 and TRM / B 3.11.23 Page TRM / B 3.11.23a Pages TRM / B 3.11-24 and TRM / B 3.11-25 Pages B 3.11-26 and B 3.11-27 Pages TRM / B 3.11-28 and TRM / B 3.11-29 Page TRM / B 3.11-30 Pages B 3.7-31 through B 3.7-35 Page TRM / B 3.11-36 04/15/2003 12/03/2004 07/05/2000 04/01/2009 04/02/2002 01/28/2005 03/01/2010 04/02/2002 04/02/2002 08/10/2004 04/02/2002 08/31/1998 04/02/2002 01/28/2005 11/29/2006 05/28/2009 08/31/1998 08/31/1998 03/22/2006 08/23/1999 08/30/1998 02/01/1999 04/07/2000 02/01/1999 12/03/2004 02/01/1999 08/30/1998 04/02/2002 04/02/2002 05/13/2005 1.1/14/2006 05/13/2005 01/21/2004 08/30/1998 11/30/2005 12/03/2004 08/30/1998 02/12/1999 SUSQUEHANNA

-UNIT 1 TRM / LOES-8 EFFECTIVE DATE 03/11/2010 SUSQUEHANNA

-UNIT 1 TRM / LOES-8 EFFECTIVE DATE 03/11/2010 SUSQUEHANNA STEAM ELECTRIC STATION PPL Rev. 56 LIST OF EFFECTIVE SECTIONS (TECHNICAL REQUIREMENTS MANUAL)Section Title Effective Date B.3.12 LOADS CONTROL PROGRAM BASES Page-TRM / B 3.12-1 Pages TRM / B 3.12-2 and TRM / B 3.12-3 09/19/2007 02/05/1999 TRMI text LOES 3/12/2010 SUSQUEHANNA

-UNIT 1 TRM / LOES-9 EFFECTIVE DATE 03/11/2010 Core Operating Limits Report (COLR)3.2.1 PPL Rev. 11 3.2 Core Operating Limits Report (COLR)3.2.1 Core Operating Limits Report (COLR)TRO 3.2.1 The Core Operating Limits specified in the attached COLR shall be met.APPLICABILITY:

Specified in the referenced Technical Specifications.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Core Operating Limits not A.1 Perform action(s) described Specified in met. in referenced Technical referenced Specification.

Technical Specifications.

TECHNICAL REQUIREMENT SURVEILLANCE SURVEILLANCE FREQUENCY-----------

NOTE ----------------------------------------

N/A No associated Surveillances.

Surveillances are implemented in the applicable Technical Specifications.

SUSQUEHANNA

-UNIT 1 TRM / 3.2-1 EFFECTIVE DATE 07/07/1999 PPL Rev. 11 PL-NF-10-001 Rev. 0 Page 1 of 53 Susquehanna SES Unit 1 Cycle 17 CORE OPERATING LIMITS REPORT Nuclear Fuels Engineering March 2010 S P l *SUSQUEHANNA UNIT I TRM/3.2-2 EFFECTIVE DATE 3/11/2010 PPL Rev. 11 PL-NF-10-001 Rev. 0 Page 2 of 53 CORE-OPERATING LIMITS REPORT REVISION DESCRIPTION INDEX Rev. Affected No. Sections Description/Purpose of Revision 0 ALL Issuance of this COLR is in support of Unit 1 Cycle 17 operation.

FORM NFP-QA-008-2, Rev. 1 SUSQUEHANNA UNIT 1 TRM/3.2-3 EFFECTIVE DATE 3/11/2010 PPL Rev. 11 PL-NF-10-001 Rev. 0 Page 3 of 53 SUSQUEHANNA STEAM ELECTRIC STATION Unit 1 Cycle 17 CORE OPERATING LIMITS REPORT Table of Contents 1.0 INT R O D UCTIO N ...................................................................................................

4 2 .0 D E F IN IT IO N S .............................................................................................................

5 3.0 SHUTDOW N MARG IN ...........................................................................................

6 4.0 AVERAGE PLANAR LINEAR HEAT GENERATION RATE (APLHGR) ...............

.... 7 5.0 MINIMUM CRITICAL POWER RATIO (MCPR) ........................................................

9 6.0 LINEAR HEAT GENERATION RATE (LHGR) .......................................................

24 7.0 ROD BLOCK MONITOR (RBM) SETPOINTS AND OPERABILITY R EQ U IR EM ENTS ..................................................................................................

32 8.0 RECIRCULATION LOOPS -SINGLE LOOP OPERATION

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

34 9.0 POWER / FLOW MAP ..........................................................................................

49 10.0 O PRM SETPO INTS ...............................................................................................

51 11.0 R E F E R E N C E S ............................................................................................................

52 SUSQUEHANNA UNIT I TRM/3.2-4 EFFECTIVE DATE 3/11/2010 PPL Rev. 11 PL-NF-10-001 Rev. 0 Page 4 of 53

1.0 INTRODUCTION

This CORE OPERATING LIMITS REPORT for Susquehanna Unit 1 Cycle 17 is prepared in accordance with the requirements of Susquehanna Unit 1, Technical Specification 5.6.5. As required by Technical Specifications 5.6.5, core shutdown margin, the core operating limits, RBM setpoints, and OPRM setpoints presented herein were developed using NRC-approved methods and are established such that all applicable limits of the plant safety analysis are met.SUSQUEHANNA UNIT 1 TRM/3.2- 5 EFFECTIVE DATE 3/11/2010 PPL Rev. 11 PL-NF-10-001 Rev. 0 Page 5 of 53 2.0 DEFINITIONS Terms used in this COLR but not defined in Section 11.0 of the Technical Specifications or Section 1.1 of the Technical Requirements Manual are provided below.2.1 The AVERAGE PLANAR EXPOSURE at a specified height shall be equal to the total energy produced per unit length at the specified height divided by the total initial weight of uranium per unit length at that height.2.2 The PELLET EXPOSURE shall be equal to the'total energy produced per unit length of fuel rod at the specified height divided by the total initial weight of uranium per unit length of that rod at that height.2.3 FDLRX is the ratio of the maximum LHGR calculated by the core monitoring system for each fuel bundle divided by the LHGR limit for the applicable fuel bundle type.2.4 LHGRFACf is amultiplier applied to the LHGR limit when operating at less than 108 Mlbm/hr core flow. The LHGRFACf multiplier protects against both fuel centerline melting and cladding strain during anticipated system transients initiated from core flows less than 108 Mlbm/hr.2.5 LHGRFACp is a multiplier applied to the LHGR limit when operating at less than 100%rated power. The LHGRFACP multiplier protects against both fuel centerline melting and cladding strain during anticipated system transients initiated from partial power conditions.

2.6 MFLCPR is the ratio of the applicable MCPR operating limit for the applicable fuel bundle type divided by the MCPR calculated by the core monitoring system for each fuel bundle.2.7 MAPRAT is the ratio of the maximum APLHGR calculated by the core monitoring system for each fuel bundle divided by the APLGHR limit for the applicable fuel bundle type.2.8 OPRM is the Oscillation Power Range Monitor. The Oscillation Power Range Monitor (OPRM) will reliably detect and suppress anticipated stability related power oscillations while providing a high degree of confidence that the MCPR safety limit is not violated.2.9 Np is the OPRM setpoint for the number of consecutive confirmations of oscillation half-cycles that will be considered evidence of a stability related power oscillation.

2.10 Sp is the OPRM trip setpoint for the peak to average OPRM signal.2.11 Fp is the core flow, in Mlbm / hr, below which the OPRM RPS trip is activated.

SUSQUEHANNA UNIT I TRM!3.2- 6 EFFECTIVE DATE 3/11/2010 PPL Rev. 11 PL-NF-10-001 Rev. 0 Page 6 of 53 3.0 SHUTDOWN MARGIN 3.1 Technical Specification Reference Technical Specification 3.1.1 3.2 Description The SHUTDOWN MARGIN shall be equal to or greater than: a) 0.38% Ak/k with the highest worth rod analytically determined OR b) 0.28% Ak/k with the highest worth rod determined by test Since core reactivity will-vary during the cycle as a function of fuel depletion and poison burnup, Beginning of Cycle (BOC) SHUTDOWN MARGIN (SDM) tests must also account for changes in core reactivity during the cycle. Therefore, the SDM measured at BOC must be equal to or greater than the applicable requirement from either 3_.2.a or 3.2.b plus an adder, "R". The adder, "R", is the difference between the calculated value of maximum core reactivity (that is, minimum SDM) during the operating cycle and the calculated BOC core reactivity.

If the value of "R" is zero (that is, BOC is the most reactive point in the cycle) no correction to the BOC measured value is required.The SHUTDOWN MARGIN limits provided in 3.2a and 3.2b are applicable in MODES 1, 2, 3, 4, and 5. This includes core shuffling.

SUSQUEHANNA UNIT 1 TRM/3. 2- 7 EFFECTIVE DATE 3/11/2010 PPL Rev. 11 PL-NF-10-001 Rev. 0 Page 7 of 53 4.0 AVERAGE PLANAR LINEAR HEAT GENERATION RATE (APLHGR)4.1 Technical Specification Reference Technical Specification 3.2.1 4.2 Description The APLHGRs for ATRIUM T M-10 fuel shall not exceed the limit shown in Figure 4.2-1.The APLHGR limits in Figure 4.2-1 are valid for Main Turbine Bypass Operable and Inoperable, EOC-RPT Operable and Inoperable, and Backup Pressure Regulator Operable and Inoperable in Two Loop operation.

The APLHGR limits for Single Loop operation are provided in Section 8.0.SUSQUEHANNA UNIT 1 TRM/3.2-8 EFFECTIVE DATE 3/11/2010

16. SSES UNIT 1 CYCLE 17 16.0> i L i.. ..., ! REFERENCE T'S" 3.2"I. ' .: , ........z ~14.0 . " ' ,......r ..............

--, --------- " "..".."..........

"....-.----."..'.'"T"""" , .. , ".USED IN DETERMININ MAG RAT (0.0, 12.5)" -' .(15000, 12.5): -.' .......- .... ..--~ ~ n -... .....' .. ..... ..... ....." w -2 1 ... ... ............ ..... .... ...r-(D>-17~ ~ .j. ..;. .. ., ., .. ....... ..... ........ ... .... .. ....... .....-- ----- -9)-- -- --------..... ....... ..(67000,69 6 .0 ------------------------------------m°, --m ---° .....t --, CD 4.0 0 10000 20000 30000 40000 50000 60000 70000-- 0 m "T Average Planar Exposure (MWD/MTU)

W D r-CD (0 <(D Z AVERAGE PLANAR LINEAR HEAT GENERATION RATE LIMIT VERSUS co c)-AVERAGE PLANAR EXPOSURE TWO LOOP OPERATION o TM_ATRIUM -10 FUEL 0) o FIGURE 4.2-1 PPL Rev. 11 PL-NF-10-001 Rev. 0 Page 9 of 53 5.0 MINIMUM CRITICAL POWER RATIO (MCPR)5.1 Technical Specification Reference Technical Specification 3.2.2, 3.3.4.1, 3.7.6, and 3.7.8 5.2 Description The MCPR limit is specified as a function of core power, core flow, average scram insertion time per Section 5.3 and plant equipment operability status. The MCPR limits for all fuel types (ATRIUMTM-10) shall be the greater of the Flow-Dependent or the Power-Dependent MCPR, depending on the applicable equipment operability status.a) Main Turbine Bypass / EOC-RPT / Backup Pressure Regulator Operable Figure 5.2-1: Flow-Dependent MCPR value determined from BOC to EOC Figure 5.2-2: Power-Dependent MCPR value determined from BOC to EOC b) Main Turbine Bypass Inoperable Figure 5.2-3: Flow-Dependent MCPR value determined from BOC to EOC Figure 5.2-4: Power-Dependent MCPR value determined from BOC to EOC c) EOC-RPT Inoperable Figure 5.2-5: Flow-Dependent MCPR value determined from BOC to EOC Figure 5.2-6: Power-Dependent MCPR value determined from BOC to EOC d) Backup Pressure Regulator Inoperable Figure 5.2-7: Flow-Dependent MCPR value determined from BOC to EOC Figure 5.2-8: Power Dependent MCPR value determined from BOC to EOC The MCPR limits in Figures 5.2-1 through 5.2-8 are valid for Two Loop operation.

The MCPR limits for Single Loop operation are provided in Section 8.0.SUSQUEHANNA UNIT I TRM/3.2-10 EFFECTIVE DATE 3/11/2010 PPL Rev. 11 PL-NF-10-001 Rev. 0 Page 10 of 53 5.3 Average Scram Time Fraction If the average measured scram times are greater than the Realistic Scram times listed in Table 5.3-1 then the MCPR operating limits corresponding to the Maximum Allowable Average Scram Insertion Time must be implemented.

Determining MCPR operating limits based on interpolation between scram insertion times is not permitted.

The evaluation of scram insertion time data, as it relates to the attached table should be performed per Reactor Engineering procedures.

SUSOUEHANNA UNIT I TRM/3.2- 11 EFFECTIVE DATE 3/11/2010 PPL Rev. 11 PL-NF-10-001 Rev. 0 Page 11 of 53 Main Turbine Bypass / EOC-RPT I Backup Pressure Regulator Operable SUSQUEHANNA UNIT 1 TRM/3.2-12 EFFECTIVE DATE 3/11/2010 0 m 2.2 2.1 2.0 1.9-q 1.81.7 0..0 L 1.6 SSES UNIT 1 CYCLE 17 I 1 I 1 LEGEND CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME CURVE B: REAUSTIC AVERAGE SCRAM INSERTION TIME SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 USED IN DETERMINING MFLCPR (30, 1.61)

REFERENCE:

T.S. 3.2.12-(108,1.23)-u-u I-:xj CD m-n-T-m m CD Cm 1.5 1.4 1.3 1.2 30 40 50 60 70 80 90 100 110 Total Core Flow (MLB/HR)MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW MAIN TURBINE BYPASS! EOC-RPT/ BACKUP PRESSURE REGULATOR OPERABLE TWO LOOP OPERATION (BOC TO EOC)FIGURE 5.2-1-1f CD 0'CD r-0 0 cz c-SSES UNIT 1 CYCLE 17 3.6 3.4 1~ILl 3.2 1 --(23, 3.06) (23, 3.11)3.0 [ " (26, 2.97)(26, 2.81A) 2.8 ý- C , II I I .I LEGEND CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME CURVE C: CORE POWER 5 26% AND CORE FLOW 50 MLBM/HR-H.E-J 2.6 Ed 2.4 0.0 2.2 09-SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE_ -jPER SR 3.7.6.1 AND 3.7.6.2' ]JUSED IN DETERMINING MFLCPR (26.01, 2.00)-u I'-CDI (26.01, 1.91)1.8 F -4 4. 4 I 4 +m m m m CD)WH CD-(40, 1.70)4. 4 F 4 +F 4.-4 F 4 +1.6 1.4 1.2-.a A F 4 -........~4- -4 F +(40, 1.63)--4. 10 (80, 1.45)--(94.46,1.37)"

REFERENCE:

T.S. 3.2.21 II (80, 1.41) (85, 1.39).4. 4 F (94.46, 1.33)(100, 1.36)(100,1.33) 00 20 30 40 50 60 70 80 Core Power (% RATED)MCPR OPERATING LIMIT VERSUS CORE POWER MAIN TURBINE BYPASS / EOC-RPT/ BACKUP PRESSURE REGULATOR OPERABLE TWO LOOP OPERATION (BOC TO EOC)FIGURE 5.2-2 90 CD CD 0 cn co"o 0 0"0 PPL Rev. 11 PL-NF-10-001 Rev. 0 Page 14 of 53 Main Turbine Bypass Inoperable SUSOUEHANNA UNIT I TRM/3.2-15 EFFECTIVE DATE 3/11/2010 C/)c/)m7 2: 2.2 2.1 2.0 1.9 CO E 1.8-J 1.7 0.1 cc ,.o1.6 SSES UNIT 1 CYCLE 17 LEGEND CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME (30, 2.00) CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME SAFETY ANALYSES ASSUME THA'T TWO OR MORE BYPASS VALVES AR INOPERABLE PER SR 3.7.6.1 OR 3.7.6.2 USED IN DETERMINING MFLCPR A F B 1

REFERENCE:

T.S. 3.7.6_ _ _ _ I1__ _ _ _ _ _ _ _ _ _ __ _ _ _ _ _ _ _ _ _Cu r-CD mT m m C)CD 1.5 1.4 1.3 1.2 30 40 50 60 70 80 90 100 110 Total Core Flow (MLB/HR)MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW MAIN TURBINE BYPASS INOPERABLE TWO LOOP OPERATION (BOC TO EOC)FIGURE 5.2-3 (n 0 cn CIO-u z-Il 0 0 0

-CD Ul)m-n m C-)m CD C-)SSES UNIT 1 CYCLE 17 3.6 3.4 23, 3.51)(26, 3.23)3.2 (23, 3.06 3.0 (26, 2 2.8 I tiz_.: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME: REALISTIC AVERAGE SCRAM INSERTION TIME: CORE POWER <26% AND CORE FLOW 5 50 MLBM/HR.86)-_C 4. 1o %%I -I4*J 2.6 0).S=2.4 0 mr (L 2.2 2.0 1.8 1.6 1.4 1.2 It4 -4 SAFETY ANALYSES ASSUME THAT TWO OR MORE BYPASS VALVES ARE INOPERABLE PER SR 3.76.1 OR 3.7.6.2 (26.01, 2.03) USED IN DETERMINING MFLCPR r-(D I 4. 4-(40, 1.74)I+ -4 4 A 4- 1 ~ I B (70, 1.56)'I 100.00,1.56)

+/- ______ I 4- 4 1 .1. .1* 4 REFERENCE T.S 3.7.6and 32.2 _____ ____ ____ ____ ____20 30 40 50 60 70 80 90 100 Core Power (% RATED)MCPR OPERATING LIMIT VERSUS CORE POWER MAIN TURBINE BYPASS INOPERABLE TWO LOOP OPERATION (BOC to EOC)FIGURE 5.2-4 (0<CD~ 'c) -n o)-4 c C.0 PPL Rev. 11 PL-NF-10-001 Rev. 0 Page 17 of 53 EOC-RPT Inoperable SUSQUEHANNA UNIT I TRM/3.2-18 EFFECTIVE DATE 3/11/2010 c(m SSES UNIT 1 CYCLE 17-H I,_E..4-a-a-2.2 2.1 2.0 1.9 1.8 1.7 1.6 1.5 1.4 1.3 3END .- -i i RVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME WE B: REALISTIC AVERAGE SCRAM INSERTION TIME 4-ILUE 4 4-!SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 USED IN DETERMINING MFLCPR (30, 1.61)A B

REFERENCE:

T.S. 3.3.4.1 and 3.2.21_ _ _ _I--(108,1.23)-

CD.-L m m m m C-)-H m ci-H m ci R)ci I'CD 1.2 30 40 50 60 70 80 90 100 110 Total Core Flow (MLB/HR)MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW EOC-RPT INOPERABLE TWO LOOP OPERATION (BOC TO EOC)FIGURE 5.2-5 CD-C)00 0 T n1 0p SSES UNIT 1 CYCLE 17 CD 3.6 3.4 I I I I 3.2 -(23, 3.1)-(23, 3.06) 1 CURVE 3.0 (26,2.97)(26, 2.86) CURVE 2.8 -C --iD"A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME.B: REALISTIC AVERAGE SCRAM INSERTION TIME-C: CORE POWER 26% AND CORE FLOW <50 MLBM/HR E-J 2.6 2.4 0 cL 2.2 2.0 1.8 1.6 1.4 1.2 SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2USED IN DETERMINING MFLCPR (26.01, 2.00)(D mr m 4 m CD CD%4;;;:z z(40, l.-j nil I 1 .5. .4.-7v A 4.I _ _ _ I _(80, 1.45)-J I s (94.46, 1.43)-(100, 1.43)REFERENCE T ad322 20 30 40 50 60 70 Core Power (% RATED)MCPR OPERATING LIMIT VERSUS CORE POWER EOC-RPT INOPERABLE TWO LOOP OPERATION (BOC to EOC)FIGURE 5.2-6 80 90 100 (D (.0 (0 CD)(D 0 0 i PPL Rev. 11 PL-NF-10-001 Rev. 0 Page 20 of 53 Backup Pressure Regulator Inoperable SUSOUEHANNA UNIT I TRM/3.2-21 EFFECTIVE DATE 3111/2010

,c)CD1 SSES UNIT 1 CYCLE 17 2.2 2.1 2.0 1.9 I I I I LEGEND CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME 1~ 1- 1+ + 4 4 SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2[-N 1.8..J 03 0~C.) 1.6lC-)CD CD 1.5 1.4 1.3 1.2 USED IN DETERMINING MFLCPR (30, 1.61)

REFERENCE:

T.S. 3.7.8 and 3.2.2 1.23)-_ _ I _ _- _ _0_ _,_1__2_ _ _-tJ I-CD 5 30 40 50 60 70 80 90 100 110 Total Core Flow (MLB/HR)MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW BACKUP PRESSURE REGULATOR INOPERABLE TWO LOOP OPERATION (BOC TO EOC)FIGURE 5.2-7 WD CD r-CD *o -n CA) I~

c/)m 7-1-I, m m m C~)N)mR-D SSES UNIT 1 CYCLE 17 3.6 3.4 I I I I 3.2 [-(23, 3.11)(23, ,306) 1 CURVE 3.0 (26,2.97)(26, 2.86) CURVE 2.8 H C" D A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME B: REALISTIC AVERAGE SCRAM INSERTION TIME C: CORE POWER <26% AND CORE FLOW < 50 MLBM/HR E-' 2.6 2.4 0 a. 2.2 2.0 1.8 1.6 1.4 1.2 SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES-(26.01,2.40)

ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 USED IN DETERMINING MFLCPR 0A (80, 1.48)

REFERENCE:

T.S. 3.7.8 and 3.2.2 (94.46,1_ _ _ I __ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _.4-u I-CD 5 (100, 1.36)1.37)20 30 40 50 60 70 80 90 100 Core Power (% RATED)MCPR OPERATING LIMIT VERSUS CORE POWER BACKUP PRESSURE.REGULATOR INOPERABLE TWO LOOP OPERATION (BOC to EOC)FIGURE 5f2-8 CD N)0 0Q1 WA CD 0 z 0 PPL Rev. 11 PL-NF-10-001 Rev. 0 Page 23 of 53 Table 5.3-1 Average Scram Time Fraction Table For Use With Scram Time Dependent MCPR Operating Limits Control Rod Average Scram Time to Position (seconds)Position 45 0.470, 0.520 39 0.630 0.860 25 1.500 1.910 5 2.700 3.440 Average Scram Realistic Maximum Insertion Time Allowable SUSOUEHANNA UNIT I TRM/3.2-24 EFFECTIVE DATE 3/11/2010 PPL Rev. 11 PL-NF-10-001 Rev. 0 Page 24 of 53 6.0 LINEAR HEAT GENERATION RATE (LHGR)6.1 Technical Specification Reference Technical Specification 3.2.3 and 3.7.6 6.2 Description The maximum LHGR for ATRIUMTM-10 fuel shall not exceed the LHGR limit determined from Figure 6.2-1. The LHGR limit in Figure 6.2-1 is valid for Main Turbine Bypass Operable and Inoperable, EOC-RPT Operable and Inoperable, and Backup Pressure Regulator Operable and Inoperable.

To protect against both fuel centerline melting and cladding strain during anticipated system transients initiated from reduced power and flow conditions, power and flow dependent LHGR limit multipliers are provided.

The following figures are applicable to EOC-RPT Operable and Inoperable and Backup Pressure Regulator Operable and Inoperable:

a) Main Turbine Bypass Operable Figure 6.2-2: Flow-Dependent LHGR Limit Multiplier Figure 6.2-3: Power-Dependent LHGR Limit Multiplier b) Main Turbine Bypass Inoperable Figure 6.2-4: Flow-Dependent LHGR Limit Multiplier Figure 6.2-5: Power-Dependent LHGR Limit Multiplier The LGHR limit and LHGR limit multipliers in Figures 6.2-1 through 6.2-5 are valid for both Two Loop and Single Loop operation.

SUSQUEHANNA UNIT I TRM/3.2- 25 EFFECTIVE DATE 3/11/2010

'0 O*O 1SSES UNIT 1 CYCLE 17 16.0 14.0 (0.0, 13.4)-------(189oo, 13.4)-:-------------EFERENCE:

T.S. 3.2.3 i I .I ,i i ,l l.i ll O ~ a USED INIETERMINING FDLIRXIi Ii.. ..... ............... .... ..........E C -D..-..-. -.. .... ................

.- .--- ------------------

---

-8.0. .... ... .... ..... ...... ... ... ....6.0 -------g~ ~~ ~ ..I .S iII .1 .II .I ....OIi .I .....4.0. ....... ........ ...../ ... ..0 10000 20000 30000 40000 50000 60000 70000 80000 N)l OPellet Exposure (MWD/MTU)

D LINEAR HEAT GENERATION RATE LIMIT VERSUS PELLET EXPOSUREN)0-I l l l l I I ~ ~ l l I I IUI IIi l l l l l l l ATRIUM -..1.0 FUEL 0 FIGURE 6.2-1 cn C..................................................J ...............CA)'

PPL Rev. 11 PL-NF-10-001 Rev. 0 Page 26 of 53 Main Turbine Bypass: Operable SUSQUEHANNA UNIT 1 TRM/3.2- 27 EFFECTIVE DATE 3/11/2010 SSES UNIT 1 CYCLE 17 110 (80,1.00)

..... .....180. 1. 0.. .... ...1.0........................

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

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

0 .0. .......... ... ...---------------...... .... .....-- -------------( 8,.. 00)cc. .........-- --..... .I ------.. ...-j-S0.7 ....----................ --------I ---------, a00.60------------

---

-----------------------

__ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES..... .. ...-........

.. -ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 0.50-----a a a a a a

REFERENCE:

T.S. 3.2.3 and 3..7.6 0.40----------------------.-----SE---DTEMIIN-FLR

...a............

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

a.----- L ------------

---

.........

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

0.30 -f 30 40 50 60 70 80 90 100 110 Total Core Flow (MLB/hr) WD CD r-(D

• Z FLOW DEPENDENT LHGR LIMIT MULTIPLIER c) p MAIN TURBINE BYPASS OPERABLE 0 ATRIU M,, 0 FUEL 0, FIGURE 6.2-2 CSSES UNIT 1 CYCLE 17 LEGEND .. ...-1->..............

....,,94 6 100* (94.46,1.00) x> .CURVE A: BASE CURVE a '----- '--~(lOO91.oo)

-CURVE B: CORE POW ER -26% AND CORE FLOW 50 MLBM-HR ... ... .1.00)A- ------- ---AREOER BEPE-R3-.-

AND 3.7.6.2 ---0.8 .. .. ... .. .. ... .. .. ... .. ..-- ----- -- --- --- -... .... ... .. ..... .----. 4-- --: U ...,. ..1..... ..... ...... ....., ....... I ...... I ......r....... ...... I ----- I --I- --(26.01,0.65) 0 * * * * *

REFERENCE:

T.S. 3.2.3 and 3.7.6 -USED IN DETERMINING FDLRX-n I I I I II ° *-------------...................... ...... ....... .... -m (26,0.46) 26.01,05 , , I (,RE)ERENCE:

T.S. 32 0 .6. ...........I ..... ......... ....I " " III 0263.420.4 ..... .........

.........

....-- --- -...... ...... .................

... ..- --A-R (23 0343)9 ..FUE------------

---

-F I- U R .2..-- ..... I .... .....Cor Pwe (23 RAED 39(...0.3 CD ' ' zv, POWER DEPENDENT LHGR LIMIT MULTIPLIER N 0 ,-n MAIN TURBINE BYPASS OPERABLE 0 , ATRIUMM-0 FUEL cn *FIGURE 6.2-3W PPL Rev. 11 PL-NF-10-001 Rev. 0 Page 29 of 53 Main Turbine Bypass Inoperable SUSQUEHANNA UNIT I TRM/3.2-30 EFFECTIVE DATE 3/11/2010 1SSES UNIT 1 CYCLE 17~~1.10 ...(99, 1.00)I. ...... .....0. 0 ....--....I- --I- --Io. .. ....... .... ........ ... .. .. .. .. .. .... ... ..... 4......a......

I ..... .. ...... ........ .. .I .. ..0.7 --- ------ -------- SAFETY ANALYSES ASSUME THAT TWO OR MORE BYPASS VALVES ARE INOPERABLE PER SR 3.7.6.1 OR 3.7.6.2 (a. a .a......... .. .................0.60 , ......... .....

REFERENCE:

T.S. 3.2.3 and 3.7.....................

--a-----------

a a .a a a a USED IN DETERMINING FDLRX 0.50 ..........

.... .... ..... ...... ....... ---a.. -..... ....a..... ....."---------------------------a , , , a a a a a a a , a-71"* (30,.0.......

........ 0.40 .............

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

0.40.....................................................................................

.. ...... .0.30 I 30 40 50 60 70 80 90 100 110 N)Total Core Flow (MLB/HR) Dl) r-CDCD " FLOW DEPENDENT LI-GR LIMIT MULTIPLIER0 MAIN TURBINE BYPASS INOPERABLE0 ATRIUMM 0 FUEL c FIGURE 6.2-4

1. SSES UNIT 1 CYCLE 17 , S m LEGEND.......> .CURVE A: BASE CURVE-"CURVE B: CORE POWER 26% AND CORE FLOW 50 MLBM/HR !80.77.,-0.93)

.....0.9 -----------------------------------------------------------------

---

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

(100,0.93) 0 9 ...................

.. ... ......... ..... ....--.......

..........

.. ........S0.8------

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

--A.. .... ...............................

__\0.7 -..----. .. ..... ..... --- -- -,--- -- ,-- --S , AFETY ANALYSES ASSUME THAT TWO OR MORE BYPASS VALVES C CLIARE INOPERABLE PER SR 3.7.6.1 OR 3.7.6.2--0 : (26.01,0.65)

,...i ...i ..... ........ ...... ......" ..................0 .6 .....0 ......

REFERENCE:

T.S. 3.2.3 and 3.7.6 USED IN DETERMINING FDLRX (2 ,,4). * * * ,"5 (23,0.43) ( 2.. B ...................................................

..m ( 60. 46 .................

..... .. .. ...... ------ .. ..... i ............ " " r........

.........r~(26.0,0.42) m, 0.4 -..--.....

..... -- -- ...... ... ..... ........-----------

.-. ----------......

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

I ---- I ------(23-n,0.9

: :: : CD C-') 0.3 I 20 30 40 50 60 70 80 90 100 CD ~~Core Power (% RATED) CDr D (2 ,0.9D....POWER DEPENDENT LHGR LIMIT MULTIPLIER c -n MAIN TURBINE BYPASS INOPERABLE 00l ATRIUM~m-10 FUEL0 FIGURE 6.2-5 I c PPL Rev. 11 PL-NF-10-001 Rev. 0 Page 32 of 53 7.0 ROD BLOCK MONITOR (RBM) SETPOINTS AND OPERABILITY REQUIREMENTS 7.1 Technical Specification Reference Technical Specification 3.3.2.1 7.2 Description The RBM Allowable Value and Trip Setpoints for;a) Low Power Range Setpoint, b) Intermediate Power Range Setpoint, c) High Power Range Setpoint, e) Low Power Range -Upscale, f) Intermediate Power Range -Upscale, and g) High Power Range -Upscale shall be established as specified in Table 7.2-1. The RBM setpoints are valid for Two Loop and Single Loop Operation, Main Turbine Bypass Operable and Inoperable, EOC-RPT Operable and Inoperable, and Backup Pressure Regulator Operable and Inoperable.

The RBM system design objective is to block erroneous control rod withdrawal initiated by the operator before fuel design limits are violated.

If the full withdrawal of any control rod would not violate a fuel design limit, then the RBM system is not required to be operable.

Table 7.2-2 provides RBM system operability requirements to ensure that fuel design limits are not violated.SUSOUEHANNA UNIT 1 TRM/3.2-33 EFFECTIVE DATE 3/11/2010 PPL Rev. 11 PL-NF-10-001 Rev. 0 Page 33 of 53 Table 7.2-1 RBM Setpoints Allowable Nominal Trip Function Value(') Setpoint Low Power Range Setpoint 28.0 24.9 Intermediate Power Range Setpoint 63.0 61.0 High Power Range Setpoint 83.0 81.0 Low Power Range -Upscale 123.4 123.0 Intermediate Power Range -Upscale 117.4 117.0 High Power Range -Upscale 109.6 109.2 (1) Power setpoint function (Low, Intermediate, and High Power Range Setpoints) determined in percent of rated thermal power. Upscale trip setpoint function (Low, Intermediate, and High Power Range -Upscale)determined in percent of reference level.Table 7.2-2 RBM System Operability Requirements Thermal Power MCPR (2,3)(% of Rated)_28 and < 90 < 1.7690 and < 95 < 1.47> 95 < 1.70 (2) Applicable to Main Turbine Bypass Operable and Inoperable, EOC-RPT Operable and Inoperable, and Backup Pressure Regulator Operable and Inoperable.

(3) Applicable to both Two Loop and Single Loop Operation.

SUSOUEHANNA UNIT I TRM/3.2-34 EFFECTIVE DATE 3/11/2010 PPL Rev. 11 PL-NF-10-001 Rev. 0 Page 34 of 53 8.0 RECIRCULATION LOOPS -SINGLE LOOP OPERATION 8.1 Technical Specification Reference Technical Specification 3.2.1, 3.2.2, 3.2.3, 3.3.4.1, 3.4.1, 3.7.6, and 3.7.8 8.2 Description APLHGR The APLHGR limit for ATRIUMTM-10 fuel shall be equalto the APLHGR Limit from Figure 8.2-1.The APLHGR limits in Figure 8.2-1 are valid for Main Turbine Bypass Operable and Inoperable, EOC-RPT Operable and Inoperable, and Backup Pressure Regulator Operable and Inoperable in Single Loop operation.

Minimum Critical Power Ratio Limit The MCPR limit is specified as a function of core power, core flow, and plant equipment operability status. The MCPR limits tor all fuel types (ATRIUM T M-10)shall be the greater of the Flow-Dependent or the Power-Dependent MCPR, depending on the applicable equipment operability status.a) Main Turbine Bypass / EOC-RPT / Backup Pressure Regulator Operable Figure 8.2-2: Flow-Dependent MCPR value determined from BOG to EOC Figure 8.2-3: Power-Dependent MCPR value determined from BOG to EOC b) Main Turbine Bypass Inoperable Figure 8.2-4: Flow-Dependent MCPR value determined from BOC to EOC Figure 8.2-5: Power-Dependent MCPR value determined from BOC to EOC c) EOC-RPT Inoperable Figure 8.2-6: Flow-Dependent MCPR value determined from BOO to EOC Figure 8.2-7: Power-Dependent MCPR value determined from BOO to EOC d) Backup Pressure Regulator Inoperable Figure 8.2-8: Flow-Dependent MCPR value determined from BOO to EOC Figure 8.2-9: Power-Dependent MCPR value determined from BOO to EOC SUSOUEHANNA UNIT I TRM/3.2-35 EFFECTIVE DATE 3/11/2010 PPL Rev. 11 PL-NF-10-001 Rev. 0 Page 35 of 53 The MCPR limits in Figures 8.2-2 through 8.2-9 are valid only for Single Loop operation.

Linear Heat Generation Rate Limit The LHGR limits for Single Loop Operation are defined in Section 6.0.RBM Setpoints and Operability Requirements The RBM setpoints and operability requirements for Single Loop Operation are defined in Section 7.0.SUSQUEHANNA UNIT 1 TRM/3.2-36 EFFECTIVE DATE 3/11/2010 1SSES UNIT 1 CYCLE 17 REEENCE T.S. 3.4.1 and 3.2.1 14.0--------------------------------,--------------------------R

::: :::: ::.USED IN DETERMINING MAPRAT 3 w.2 12.0-....r 8 ........ .-711 E 6.* O. C -* Ui i , 0 =CDD 6 .0.... .......................

j.............

,...... .,=j .....t,,.. .=.... j. ., .. j. .....=.....S > 14..............

...-.. ..............

"(67000,5.6)

'-.--i C-'-'4.0 0.0 10000.0 20000.0 30000.0 40000.0 50000.0 60000.0 70000.0 Average Planar Exposure (MWD/MTU) a) cD r-H-(0 <CD (D 'AVERAGE PLANAR LINEAR HEAT GENERATION RATE LIMIT VERSUS 0 AVERAGE PLANAR EXPOSURE SINGLE LOOP OPERATIONINMPP MTMj 0 ATRIUM -0 FUEL nC FIGURE 8.2-1 PPL Rev. 11 PL-NF-10-001 Rev. 0 Page 37 of 53 Main Turbine Bypass / EOC-RPT I Backup Pressure Regulator Operable SUSQUEHANNA UNIT I TRM!3.2- 38 EFFECTIVE DATE 3/11/2010 m 4.6 4.4 4.2 4.0 3.8 3.6 R)= 34 cn 3.2 (D 3.0 0.0 cc 2.8 2.6 SSES UNIT 1 CYCLE 17_LEGEND CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 USED IN DETERMINING MFLCPR--(30, 2.03)A B (108, 1.56) m C-r-CD m CD W mD 2.4 2.2 2.0 1.8 1.6 1.4 30 40 50 60 70 80 90 100 110 Total Core Flow (MLB/HR)MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW MAIN TURBINE BYPASS / EOC-RPT/ BACKUP PRESSURE REGULATOR OPERABLE SINGLE LOOP OPERATION (BOC to EOC)FIGURE 8.2-2 (D (0 cDn 0a CD 0'-u z T1 0 0 0 lp V)-K SSES UNIT 1 CYCLE 17 4.6 4.4 4.2 4.0 (23, 3.83)3.8_______ _______ ____ I I I I____ I ____ I __I LIAJINU-(23, 3.89)E %, (26, 3.72),3.58)_CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME CURVE B: REALISTIC AVERAGE SCRAM TIME CURVE C: CORE POWER < 26% AND CORE FLOW < 50 MLBM/HR 3.6 (26, C= 3.43.2 3.0 0 CC 2.8 0.2.6 2.4 2.2 2.0 1.8 1.6 1.4 i Cr-.___ ____----I SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 USED IN DETERMINING MFLCPR c-)f'-H mD--(26.01, 2.52)2!t- --40,2.15)--(60, 1.99)An

REFERENCE:

T.S. 3.4.1 and 3.2.21 CD (100,1.99) 20 30 40 50 60 70 80 90 100 Core Power (% RATED)MCPR OPERATING UMIT VERSUS CORE POWER MAIN TURBINE BYPASS / EOC-RPT / BACKUP PRESSURE REGULATOR OPERABLE SINGLE LOOP OPERATION (BOC to EOC)FIGURE 8.2-3 CD 0 (D r-o -0 PPL Rev. 11 PL-NF-10-001 Rev. 0 Page 40 of 53 Main Turbine Bypass Inoperable SUSOUEHANNA UNIT I TRM/3.2-41 EFFECTIVE DATE 3/11/2010

-H 4.6 4.4 4.2 4.0 3.8 3.6-.H 7,J 3.4 o 3.2 cc at 3.0 0.0 1=2.8 0.2.6 0 SSES UNIT 1 CYCLE 17_LEGEND CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME SAFETY ANALYSES ASSUME THAT TWO OR MORE BYPASS VALVES ARE INOPERABLE PER SR 3.7.6.1 OR 3.7.6.2 USED IN DETERMINING MFLCPR (30, 2.52)A_ (108,1.88)_

--

T.S. 341376,and 3.2.2 -3.4.1,3.7._________

_________

_________

_________

_________

____,____I-CD m m m CD)2.4 2.2 2.0 1.8 1.6 1.4 30 40 50 60 70 80 90 100 110 Total Core Flow (MLB/HR)MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW MAIN TURBINE BYPASS INOPERABLE SINGLE LOOP OPERATION (BOC to EOC)FIGURE 8.2-4 (D Cc C.0 (D r-0 J p cz)(-l)m 71 SSES UNIT 1 CYCLE 17 4.6 1 LEGEND 4.4 ---(23, 4.39) CURVE A 4.2 4.0 (26, 4.04)CV (23,383)-CURVE B: 3.8 CURVE C M, 3.58)'T_3.4 -: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME: REALISTIC AVERAGE SCRAM INSERTION TIME: CORE POWER <26% AND CORE FLOW <50 MLBM/HR SAFETY ANALYSES ASSUME THAT TWO OR MORE BYPASS VALVES ARE INOPERABLE PER SR 3.7.6.1 OR 3.7.6.2 3.0 0 mr 2.8 a.2.6 2.4 2.2 2.0 1.8 1.6 1.4 USED IN DETERMINING MFLCPR (26.01, 2.55) -......_ ___(40, 2.19) __ _ _(60, 2.05) -(100, 2.05)B

REFERENCE:

T.S. 3.4.1, 3.7.6, and 3.2.21 I-" (D 5 20 30 40 50 60 70 Core Power (% RATED)MCPR OPERATING LIMIT VERSUS CORE POWER MAIN TURBINE BYPASS INOPERABLE SINGLE LOOP OPERATION (BOC to EOC)FIGURE 8.2-5 80 90 100 CD 0 01 CIO m -u c -n Cl 0)i PPL Rev. 11 PL-NF-10-001 Rev. 0 Page 43 of 53 EOC-RPT Inoperable SUSOUEHANNA UNIT I TRM/3.2- 44 EFFECTIVE DATE 3/11/2010 U c/)c/) 4.6 m 4.4>" 4.2 4.0--H 3.8 3.6_3.4 C4-c 3.0 it 2.8 0-S2.6 2.4.SSES UNIT 1 CYCLE 17 ,LEGEND CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2_USED IN DETERMINING MFLCPR-(30, 2.03) 'A __B-(108,1.56)

-

REFERENCE:

T.S. 3.4.1, 3.3.4.1, and 3.2.2 CD m m m CD m'CD I , CD 2.2 2.0 1.8 1.6 1.4 30 40 50 60 70 80 90 100 110 Total Core Flow (MLB/HR)MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW EOC-RPT INOPERABLE SINGLE LOOP OPERATION (BOC to EOC)FIGURE 8.2-6 CD Co CD C C,, CD r-C V1)_-H SSES UNIT 1 CYCLE 17 4.4 LEGEND 4.2 CURVE A: 4.0 L(2 3 , 3.8 9).(23, 3.83) CURVE B: 3.8 ..3. C -(26, 3.72) CURVE C: 3.6 -(26,3.58)

-E3.4.S I I I I MAXIMUM ALLOWABLE AVERAGE SCRAM NSERTION TIME REALISTIC AVERAGE SCRAM INSERTION TIME CORE POWER <26% AND CORE FLOW < 50 MLBM/HR SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 0 C2.8 a., Q.2.6 2.4 m C-)-W 2.2 2.0 1.8 1.6 1.4 USED IN DETERMINING MFLCPR (26.01, 2.52)2.15)__(60, 1.99) A B

REFERENCE:

T.S. 3.4.1, 3.3.4.1, and 3.2.2 j I--CD (100, 1.99)20 30 40 50 60 Core Power (% RATED)70 80 90 100 MCPR OPERATING LIMIT VERSUS CORE POWER EOC-RPT INOPERABLE SINGLE LOOP OPERATION (BOC to EOC)FIGURE 8.2-7 n0 <c-n 0 z iC 0 0 0..

PPL Rev. 11 PL-NF-10-001 Rev. 0 Page 46 of 53 Backup Pressure Regulator Inoperable SUSQUEHANNA UNIT 1 TRM/3.2-47 EFFECTIVE DATE 3/11/2010 V)cz: V)SSES UNIT 1 CYCLE 17 4.6 4.4 4.2 4.0 3.8 3.6 I I I I_____________

_____________

_____________V.-.

LEGEND CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME I i-.-.-! I.i SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE PER SR 3.76.1 AND 3.7.6.2 CIO S3.4 m 3.2 3.0 0 cc 2.8 a,.C.6~2.6 4 I I-i ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 USED IN DETERMINING MFLCPR Fm n m m CD W N)-H CD 2.4 2.2 2.0 1.8 1.6 1.4--(30, 2.03)- A......_-REERECE:T.S3..1 3..8, _ a 3(108,1.56)

REFERENCE:

T.S. 3.4.1, 3.7.8, and 3.2.2_ _____-U (-CD 30 40 50 60 70 80 Total Core Flow (MLB/HR)90 100 110 MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW BACKUP PRESSURE REGULATOR INOPERABLE SINGLE LOOP OPERATION (BOC to EOC)FIGURE 8.2-8 (D (0 CIO CD r--0 6 0 c -

C/)-71 m C)m CD N)m2 C)SSES UNIT 1 CYCLE 17 4.6 4.4 4.2 1* r -+ 4-LEGEND+ 4- .4--- --4. 4.-+ 4.+ 4- 4.0 ý-(23, 3.89R)(23,3.3)-3.8 i 1(26, 3.72)3.6 -(26, 3.58).3.4 [C -CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME CURVE C: CORE POWER _26% AND CORE FLOW 50 MLBM/HR SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES E 14 ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 1111i 3.2 E Z 2.8 o').S= 2.6 0 2.4 0.U 2.2 2.0 1.8 1.6 1.4 (26.01, 3.01)~_(40, 2.72) " USED IN DETERMINING MFLCPR IS B(60, 2.29)-

REFERENCE:

T.S. 3.4.1,'3.7.8, and 3.2.2IZ-a I'-CD (100, 2.29)20 30 40 50 60 Core Power (% RATED)70 80 90 100 MCPR OPERATING LIMIT VERSUS CORE POWER BACKUP PRESSURE REGULATOR INOPERABLE SINGLE LOOP OPERATION (BOC to EOC)FIGURE 8.2-9 Lo (D 0, CIO CD o -I C)0)

PPL Rev. 11 PL-NF-10-001 Rev. 0 Page 49 of 53 9.0 POWER / FLOW MAP 9.1 Technical Specification Reference Technical Specification 3.3.1.1 9.2 Description Monitor reactor conditions to maintain THERMAL POWER / core flow outside of Stability Regions I and II of the Power / Flow map, Figure 9.1.If the OPRM Instrumentation is OPERABLE per TS 3.3.1.1, Region I of the Power/ Flow map is considered an immediate exit region.If the OPRM Instrumentation is inoperable per TS 3.3.1.1, Region I of the Power/ Flow map is considered an immediate scram region.Region II of the Power / Flow map is considered an immediate exit region regardless of the operability of the OPRM Instrumentation.

SUSQUEHANNA UNIT 1 TRM/3.2-50 EFFECTIVE DATE 3/11/2010 PPL Rev. 11 PL-NF-10-001 Rev. 0 Page 50 of 53 120 120 Purpose:______________________.

UNIT 1 I__ __ _ J POWER (FLOW MAP APFCM Scram 110--Ti epit T Initial/Date:

110 i ------ _LAPRMV Rod Block SOPRIM INOPERABLE IMMEDIATE Trip Setp.in.100 SCRAM lAW ON-178-002 100 IF OPRM OPERABLE IMMEDIATE EXIT lAW ON-178-002 E L IMMEDIATELY EXrT AW ON-178-002 90 90 (As defined in Atiachment G to L NDAP-GA-0338)

-:FABOVEMELLLA BOUNDARY, I -IMMEDIATELY EXIT lAW ON-178-002

' 9l d 80 80-- --.-,- ----------- : --: ýA I- 70 -70 OR --;* 60 ..... 60 0 060 E Rod____ 50e 4) 50 ' ' ...5 7R7 .. ..--"2 40 Natural Circulation 40 Line --------i- " 30 .. .Apr -30'30-/6 pee30 2 x :.20.:~~~-- -,. .;: ------.-T -.---- --..T ; 10 ;10-'- --- -...----: ---- -' --: --' --" ----- --.. .-...-100 N.. ...: ... ... .' .. ." : ., IX .., : , , " ! : : , : ! ...Se d ,1 , , ; 0 0 10 20 30 40 50 60 70 80 90 100 110 Total Core Flow (Mibm/hr)(for SLO <75% Pump Speed Use Form GO-100-009-2)

Figure 9.1 SSES Unit 1 Cycle 17 Power/ Flow Map SUSQUEHANNA UNIT 1 TRM/3.2-51 EFFECTIVE DATE 3/11/2010 PPL Rev. 11 PL-NF-10-001 Rev. 0 Page 51 of 53 10.0 OPRM SETPOINTS 10.1 Technical Specification Reference Technical Specification 3.3.1.1 10.2 Description Setpoints for the OPRM Instrumentation are established that will reliably detect and suppress anticipated stability related power oscillations while providing a high degree of confidence that the MCPR Safety limit is not violated.

The setpoints are described in Section 2.0 and are listed below: Sp-1.11 Np = 15 Fp = 60 Mlbm / hr SUSQUEHANNA UNIT I TRM/3.2-52 EFFECTIVE DATE 3/11/2010 PPL Rev. 11 PL-NF-10-001 Rev. 0 Page 52 of 53

11.0 REFERENCES

11.1 The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC, specifically those described in the following documents:

1. XN-NF-81-58(P)(A), Revision 2 and Supplements 1 and 2, "RODEX2 Fuel Rod Thermal-Mechanical Response Evaluation Model," Exxon Nuclear Company, March 1984.2. EMF-2361(P)(A), Revision 0, "EXEM BWR-2000 ECCS Evaluation Model," Framatome ANP, May 2001.3. EMF-2292(P)(A), Revision 0, "ATRIUM T M-10: Appendix K Spray Heat Transfer Coefficients," Siemens Power Corporation, September 2000.4. XN-NF-84-105(P)(A), Volume 1 and Volume 1 Supplements 1 and 2,"XCOBRA-T:

A Computer Code for BWR Transient Thermal-Hydraulic Core Analysis," Exxon Nuclear Company, February 1987.5. XN-NF-80-19(P)(A), Volume 1 and Supplements 1 and 2, "Exxon Nuclear Methodology for Boiling Water Reactors:

Neutronic Methods for Desigrnand Analysis," Exxon Nuclear Company, March 1983.6. XN-NF-80-19(P)(A), Volumes 2, 2A, 2B, and 2C "Exxon Nuclear Methodology for Boiling Water Reactors:

EXEM BWR ECCS Evaluation Model," Exxon Nuclear Company, September 1982.7. XN-NF-80-19(P)(A), Volume 3 Revision 2 "Exxon Nuclear Methodology for Boiling Water Reactors Thermex: Thermal Limits Methodology Summary Description," Exxon Nuclear Company, January 1987.8. XN-NF-80-19(P)(A), Volume 4, Revision 1, "Exxon Nuclear Methodology for Boiling Water Reactors:

Application of the ENC Methodology to BWR Reloads," Exxon Nuclear Company, June 1986.9. XN-NF-85-67(P)(A), Revision 1, "Generic Mechanical Design for Exxon Nuclear Jet Pump BWR Reload Fuel," Exxon Nuclear Company, Inc., September 1986.10. ANF-524(P)(A), Revision 2 and Supplements 1 and 2, "Advanced Nuclear Fuels Corporation Critical Power Methodology for Boiling Water Reactors," November 1990.11. NE-092-001A, Revision 1, "Licensing Topical Report for Power Uprate With Increased Core Flow," Pennsylvania Power & Light Company, December 1992 and NRC SER (November 30, 1993).SUSOUEHANNA UNIT I TRM/3.2-53 EFFECTIVE DATE 3/11/2010 PPL Rev. 11 PL-NF-10-001 Rev. 0 Page 53 of 53 12. ANF-89-98(P)(A)

Revision 1 and Supplement 1, "Generic Mechanical Design Criteria for BWR Fuel Designs," Advanced Nuclear Fuels Corporation, May 1995.13. EMF-2209(P)(A), Revision 3, "SPCB Critical Power Correlation," AREVA NP, September 2009.14. EMF-85-74(P)(A), Revision 0, Supplement 1(P)(A) and Supplement 2(P)(A),"RODEX2A (BWR) Fuel Rod Thermal-Mechanical Evaluation Model," Siemens Power Corporation, February 1998.15. EMF-2158(P)(A), Revision 0, "Siemens Power Corporation Methodology for Boiling Water Reactors:

Evaluation and Validation of CASMO-4/Microburn-B2," Siemens Power Corporation, October 1999.16. EMF-CC-074(P)(A), Volume 4, Revision 0, "BWR Stability Analysis -Assessment of STAIF with Input from MICROBURN-B2," Siemens Power Corporation, August 2000.17. NEDO-32465-A, "BWROG Reactor Core Stability Detect and Suppress Solutions Licensing Basis Methodology for Reload Applications," August 1996.18. ANF-913(P)(A), Volume 1 Revision 1 and Volume 1 Supplements 2, 3, and 4,"COTRANSA2:

A Computer Program for Boiling Water Reactor Transient Analyses," Advanced Nuclear Fuels Corporation, August 1990.19. ANF-1358(P)(A), Revision 3, "The Loss of Feedwater Heating Transient in Boiling Water Reactors," Framatome ANP, September 2005.SUSQUEHANNA UNIT I TRM/3.2- 54 EFFECTIVE DATE 3/11/2010