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
References
Download: ML100890542 (80)

Text

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. WHEN REPLACING THIS MATERIAL IN YOUR HARDCOPY MANUAL, ENSURE THE

. UPDATE DOCUMENT ID IS THE SAME DOCUMENT ID YOU'RE REMOVING FROM YOUR MANUAL.

FROM THE HUMAN PERFORMANCE TOOL BAG SHOULD BE UTILIZED TO ELIMINATE THE CHANCE OF ERRORS.

TOOLS ATTENTION: "REPLACE" directions do not affect the Table of Contents, Therefore no TOC will be issued with the updated material.

TRM1 - TECHNICAL REQUIREMENTS MANUAL UNIT 1 REMOVE MANUAL TABLE OF CONTENTS DATE: 03/11/2010 ADD MANUAL TABLE OF CONTENTS DATE: 03/16/2010 CATEGORY: DOCUMENTS TYPE: TRMl

Mar. 17, 2010 Page 2 of 2 ID: TEXT 3.2.1 REMOVE: REV:10 ADD: REV: 11 CATEGORY: DOCUMENTS TYPE: TRMI ID: TEXT LOES REMOVE: REV:55 ADD: REV: 56 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: TRMI Manual

Title:

TECHNICAL REQUIREMENTS MANUAL UNIT 1 Table Of Contents Issue Date e C3/16/2010 Procedure Name Rev Issue Date Change ID Change Number TEXT LOES 56 03/16/2010

Title:

LIST OF EFFECTIVE SECTIONS TEXT TOC 16 . 04/16/2009

Title:

TABLE OF CONTENTS TEXT 1.1 0 11/18/2002

Title:

USE AND APPLICATION DEFINITIONS TEXT 2.1 1 02/04/2005

Title:

PLANT PROGRAMS AND E TEXT 2.2 8

Title:

PLANT PROGRAMS AND S 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 INJECTION* (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)

Report Date: 03/16/10 Page 11 of of 15 15 Report Date: 03/16/10

SSES MANUAL Manual Name: TRMI Manual

Title:

TECHNICAL REQUIREMENTS MANUAL UNIT 1 TEXT 3.3.1 0 11/18/2002

Title:

INSTRUMENTATION 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 5 05/23/2008

Title:

INSTRUMENTATION TRM POST-ACCIDENT MONITORING INSTRUMENTATION TEXT 3.3.5 0 11/18/2002

Title:

INSTRUMENTATION THIS PAGE INTENTIONALLY LEFT BLANK TEXT 3.3.6 2 10/19/2005

Title:

INSTRUMENTATION TRM ISOLATION ACTUATION INSTRUMENTATION TEXT 3.3.7 1 11/09/2007

Title:

INSTRUMENTATION. MAIN TURBINE OVERSPEED PROTECTION SYSTEM TEXT 3.3.8 1 10/22/2003

Title:

INSTRUMENTATION TRM RPS INSTRUMENTATION TEXT 3.3.9 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 Report Date: 03/16/10 Page 2Z of of 15 15 Report Date: 03/16/10

SSES MANUAL Manual Name: TRMI Manual

Title:

TECHNICAL REQUIREMENTS MANUAL UNIT 1 TEXT 3. 4.1 1 04/26/2006

Title:

REACTOR COOLANT SYSTEM REACTOR COOLANT SYSTEM CHEMISTRY TEXT 3.4.2 1 04/16/2009

Title:

REACTOR COOLANT SYSTEM STRUCTURAL INTEGRITY TEXT 3.4.3 1 11/09/2007

Title:

REACTOR COOLANT SYSTEM HIGH/LOW PRESSURE INTERFACE LEAKAGE MONITORS TEXT 3.4.4 2 04/17/2008

Title:

REACTOR COOLANT SYSTEM REACTOR RECIRCULATION FLOW AND ROD LINE LIMIT TEXT 3.4.5 1 04/26/2006

Title:

REACTOR COOLANT SYSTEM REACTOR VESSEL MATERIALS TEXT 3.5.1 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

Title:

0 11/18/2002 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 0 11/18/2002

Title:

PLANT SYSTEMS EMERGENCY SERVICE WATER SYSTEM (ESW) SHUTDOWN TEXT 3.7.2 0 11/18/2002

Title:

PLANT SYSTEMS ULTIMATE HEAT SINK (UHS) AND GROUND WATER LEVEL TEXT 3.7.3.1 2 04/16/2009

Title:

PLANT SYSTEMS FIRE SUPPRESSION WATER SUPPLY SYSTEM TEXT 3.7.3.2 3 04/16/2009

Title:

PLANT SYSTEMS SPRAY AND SPRINKLER SYSTEMS TEXT 3.7.3.3 3 04/16/2009

Title:

PLANT SYSTEMS C02 SYSTEMS TEXT 3.7.3.4 2 04/16/2009

Title:

PLANT SYSTEMS HALON SYSTEMS

'TEXT 3.7.3.5 2 04/16/2009

Title:

PLANT SYSTEMS FIRE HOSE STATIONS TEXT 3.7.3.6 2 04/16/2009

Title:

PLANT SYSTEMS YARD FIRE HYDRANTS AND HYDRANT HOSE HOUSES TEXT 3.7.3.7 1 04/26/2006

Title:

PLANT SYSTEMS FIRE RATED ASSEMBLIES TEXT 3.7.3.8 7 01/20./2010

Title:

PLANT SYSTEMS FIRE DETECTION INSTRUMENTATION LDCN 3503 TEXT 3.7.4 1 04/26/2006

Title:

PLANT SYSTEMS SOLID RADWASTE SYSTEM TEXT 3.7.5.1 0 11/18/2002

Title:

PLANT SYSTEMS MAIN CONDENSER OFFGAS HYDROGEN MONITOR Report Date: 03/16/10 Page 4 Page4 of of 15 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 0 04/16/2009

Title:

STRUCTURAL INTEGRITY TEXT 3.8.1 1 02/04/2005

Title:

ELECTRICAL POWER PRIMARY CONTAINMENT PENETRATION CONDUCTOR OVERCURRENT PROTECTIVE DEVICES LDCN 4760 TEXT 3.8.2.1 2 11/09/2007

Title:

ELECTRICAL POWER MOTOR OPERATED VALVES (MOV) THERMAL OVERLOAD PROTECTION -

CONTINUOUS TEXT 3.8.2.2 2 12/14/2004

Title:

ELECTRICAL POWER MOTOR OPERATED VALVES (MOV) THERMAL OVERLOAD PROTECTION -

AUTOMATIC TEXT 3.8.3 0 11/18/2002

Title:

ELECTRICAL POWER DIESEL GENERATOR (DG) MAINTENANCE ACTIVITIES Report Date: 03/16/10 Page5 Page ~ of 15 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 1 04/26/2006

Title:

RADIOACTIVE EFFLUENTS LIQUID EFFLUENTS DOSE.

TEXT 3.11.1.3 1 04/26/2006

Title:

RADIOACTIVE EFFLUENTS LIQUID WASTE TREATMENT SYSTEM TEXT 3.11.1.4 1 12/14/2004

Title:

RADIOACTIVE EFFLUENTS LIQUID RADWASTE EFFLUENT MONITORING INSTRUMENTATION TEXT 3.11.1.5 2 05/02/2007

Title:

RADIOACTIVE EFFLUENTS RADIOACTIVE LIQUID PROCESS MONITORING INSTRUMENTATION TEXT 3.11.2.1 3 04/26/2006

Title:

RADIOACTIVE EFFLUENTS DOSE RATE TEXT 3.11.2..2 1 04/26/2006

Title:

RADIOACTIVE EFFLUENTS DOSE - NOBLE GASES TEXT 3.11.2.3 1 04/26/2006

Title:

RADIOACTIVE EFFLUENTS DOSE - IODINE, TRITIUM, AND RADIONUCLIDES IN PARTICULATE FORM TEXT 3.11.2.4 0 11/18/2002

Title:

RADIOACTIVE EFFLUENTS GASEOUS RADWASTE TREATMENT SYSTEM TEXT 3.11.2.5 3 11/14/2006

Title:

RADIOACTIVE EFFLUENTS VENTILATION EXHAUST TREATMENT SYSTEM TEXT 3.11.2.6 4 09/16/2009

Title:

RADIOACTIVE EFFLUENTS RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION TEXT 3.11.3 1 04/26/2006

Title:

RADIOACTIVE EFFLUENTS TOTAL DOSE TEXT 3.11.4.1 4 08/08/2006

Title:

RADIOACTIVE EFFLUENTS MONITORING PROGRAM Report Date: 03/16/10 Page 27 of of 15 15 Report Date: 03/16/10

SSES MANUTAL Manual Name: TRM1 Manual

Title:

TECHNICAL REQUIREMENTS MANUAL UNIT 1 ý.0 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 TEXT 4.1 0 08/31/1998

Title:

ADMINISTRATIVE CONTROLS ORGANIZATION TEXT 4.2 08/31/1998

Title:

ADMINISTRATIVE CONTROLS* REPORTABLE EVENT ACTION TEXT 4.3 0 08/31/1998

Title:

ADMINISTRATIVE CONTROLS SAFETY LIMIT VIOLATION 1 12/18/2008 TEXT 4.4

Title:

ADMINISTRATIVE CONTROLS PROCEDURES & PROGRAMS TEXT 4.5 0 08/31/1998

Title:

ADMINISTRATIVE CONTROLS REPORTING REQUIREMENTS TEXT 4.6 0 08/31/1998

Title:

ADMINISTRATIVE CONTROLS RADIATION PROTECTION PROGRAM TEXT 4.7 0 08/31/1998

Title:

ADMINISTRATIVE CONTROLS TRAINING Report Date: 03/16/10 Page ~8 of of 15 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 0 11/19/2002

Title:

INSTRUMENTATION BASES RADIATION MONITORING INSTRUMENTATION TEXT B3.3.2 1 11/09/2007

Title:

INSTRUMENTATION BASES SEISMIC MONITORING INSTRUMENTATION TEXT B3.3.3 3 12/18/2008

Title:

INSTRUMENTATION BASES METEOROLOGICAL MONITORING INSTRUMENTATION TEXT B3.3.4 3 11/09/2007

Title:

INSTRUMENTATION BASES TRM POST ACCIDENT MONITORING (PAM) INSTRUMENTATION TEXT B3.3.5 2 11/09/2007

Title:

INSTRUMENTATION BASES THIS PAGE INTENTIONALLY LEFT BLANK TEXT B3.3.6 3 10/19/2005

Title:

INSTRUMENTATION BASES TRM ISOLATION ACTUATION INSTRUMENTATION Report Date: 03/16/10 Page ~.

9 of of 15 15 Report Date: 03/16/10

SSES MANUAL Manual Name: TRM1 Manual

Title:

TECHNICAL REQUIREMENTS MANUAL UNIT 1 TEXT B3.3.7 1 11/09/2007

Title:

INSTRUMENTATION BASES MAIN TURBINE OVERSPEED PROTECTION SYSTEM TEXT B3.3.8 1 10/22/2003

Title:

INSTRUMENTATION BASES TRM REACTOR PROTECTION SYSTEM (RPS) INSTRUMENTATION TEXT B3.3.9 '3 04/17/2008

Title:

OPRM INSTRUMENTATION 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 Report Date: 03/16/10 Page ~

10 of of 15 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 0 11/19/2002

Title:

PLANT SYSTEMS BASES EMERGENCY SERVICE WATER SYSTEM (SHUTDOWN)

TEXT B3.7.2 0 11/19/2002

Title:

PLANT SYSTEMS BASES ULTIMATE HEAT SINK (UHS) GROUND WATER LEVEL TEXT B3.7.3.1 2 01/07/2008

Title:

PLANT SYSTEMS BASES FIRE SUPPRESSION WATER SUPPLY SYSTEM TEXT B3.7.3.2 2 04/26/2006

Title:

PLANT SYSTEMS BASES SPRAY AND SPRINKLER SYSTEMS TEXT B3.7.3.3 0 11/19/2002

Title:

PLANT SYSTEMS BASES C02 SYSTEMS TEXT B3.7.3.4 1 04/26/2006

Title:

PLANT SYSTEMS BASES HALON SYSTEMS Report Date: 03/16/10 Page jj Page 11 of of 15

.15 Report Date: 03/16/10

SSES MANUAL Manual Name: TRMI Manual

Title:

TECHNICAL REQUIREMENTS MANUAL UNIT 1 TEXT B3.7.3.5 1 04/26/2006

Title:

PLANT SYSTEMS BASES FIRE HOSE STATIONS TEXT B3.7.3.6 1 04/26/2006

Title:

PLANT SYSTEMS BASES YARD FIRE HYDRANTS AND HYDRANT HOSE HOUSES TEXT B3.7.3.7 0 11/19/2002

Title:

PLANT SYSTEMS BASES FIRE RATED ASSEMBLIES TEXT B3.7.3.8 1 01/12/2004

Title:

PLANT SYSTEMS BASES FIRE DETECTION INSTRUMENTATION TEXT B3.7.4 0 11/19/2002

Title:

PLANT SYSTEMS BASRS SOLID RADWASTE SYSTEM TEXT B3.7.5.1 0 11/19/2002

Title:

PLANT SYSTEMS BASES MAIN CONDENSER OFFGAS HYDROGEN MONITOR TEXT B3.7.5.2 0 11/19/2002

Title:

PLANT SYSTEMS BASES MAIN CONDENSER OFFGAS EXPLOSIVE GAS MIXTURE TEXT B3.7.5.3 0 11/19/2002

Title:

PLANT SYSTEMS BASES LIQUID HOLDUP TANKS TEXT B3.7.6 2 06/27/2008

Title:

PLANT 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 0 04/16/2009

Title:

STRUCTURAL INTEGRITY TEXT B3.8.1 2 03/10/2010

Title:

ELECTRICAL POWER BASES PRIMARY CONTAINMENT PENETRATION CONDUCTOR OVERCURRENT PROTECTIVE DEVICES TEXT B3.8.2.1 0 11/19/2002

Title:

ELECTRICAL POWER BASES MOTOR OPERATED VALVES (MOV) THERMAL OVERLOAD PROTECTION -

CONTINUOUS TEXT B3.8.2.2 1 09/17/2004

Title:

ELECTRICAL POWER BASES MOTOR OPERATED VALVES (MOV) THERMLAL OVERLOAD PROTECTION -

AUTOMATIC TEXT B3.8.3 0 11/19/2002

Title:

ELECTRICAL POWER BASES DIESEL GENERATOR (DG) MAINTENANCE ACTIVITIES TEXT B3.8.4 0 11/19/2002

Title:

ELECTRICAL POWER BASES 24 VDC ELECTRICAL POWER SUBSYSTEM TEXT B3.8.5 0 11/19/2002

Title:

ELECTRICAL POWER BASES DEGRADED VOLTAGE PROTECTION TEXT B3.8.6 1 02/04/2005

Title:

ELECTRICAL 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 Report Date: 03/16/10 Page fl 13 of of 15

.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 0 11/19/2002 0

Title:

RADIOACTIVE EFFLUENTS BASES LIQUID EFFLUENTS CONCENTRATION TEXT B3.11.1.2 0 11/19/2002

Title:

RADIOACTIVE EFFLUENTS BASES LIQUID EFFLUENTS DOSE TEXT B3.11.1.3 0 11/19/2002

Title:

RADIOACTIVE EFFLUENTS BASES LIQUID WASTE TREATMENT SYSTEM TEXT B3.11.1.4 0 11/19/2002

Title:

RADIOACTIVE EFFLUENTS BASES LIQUID RADWASTE EFFLUENT MONITORING INSTRUMENTATION TEXT B3.11.1.5 0 11/19/2002

Title:

RADIOACTIVE EFFLUENTS BASES RADIOACTIVE LIQUID PROCESS MONITORING INSTRUMENTATION TEXT B3.11.2.1 1 12/14/2004

Title:

RADIOACTIVE EFFLUENTS BASES DOSE RATE TEXT B3.11.2.2 0 11/19/2002

Title:

RADIOACTIVE EFFLUENTS BASES DOSE - NOBLE GASES Report Date: 03/16/10 Page 24 Page 14 of of 15 15 Report Date: 03/16/10

SSES MANUAL Manual Name: TRMI.

Manual

Title:

TECHNICAL REQUIREMENTS MANUAL UNIT 1 TEXT B3.11.2.3 0 11/19/2002

Title:

RADIOACTIVE EFFLUENTS BASES DOSE - IODINE, TRITIUM, AND RADIONUCLIDES IN PARTICULATES FORM TEXT B3.11.2.4 0 11/19/2002

Title:

RADIOACTIVE EFFLUENTS BASES GASEOUS RADWASTE TREATMENT SYSTEM TEXT B3.11.2.5 4 11/14/2006

Title:

RADIOACTIVE EFFLUENTS BASES VENTILATION EXHAUST TREATMENT SYSTEM TEXT B3.11.2.6 1 01/27/2004

Title:

RADIOACTIVE EFFLUENTS BASES RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION TEXT B3.11.3 0 11/19/2002

Title:

RADIOACTIVE EFFLUENTS BASES TOTAL DOSE TEXT B3.11.4.1 2 01/06/2006

Title:

RADIOACTIVE EFFLUENTS 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 0 11/19/2002

Title:

LOADS CONTROL PROGRAM BASES HEAVY LOADS REQUIREMENTS TEXT B3.12.3 0 11/19/2002

Title:

LOADS CONTROL PROGRAM BASES LIGHT LOADS REQUIREMENTS Report Date: 03/16/10 15.

Page 15 of of 15 15 Report Date: 03/16/10

SUSQUEHANNA STEAM ELECTRIC STATION PPL Rev. 56 LIST OF EFFECTIVE SECTIONS (TECHNICAL REQUIREMENTS MANUAL)

Section Title Effective Date TOC TABLE OF CONTENTS 04/07/2009 1.0 USE AND APPLICATION Pages TRM / 1.0-1 through TRM / 1.0-3 10/04/2002 2.0 PLANT PROGRAMS Page 2.0-1 08/31/1998 Pages TRM / 2.0-2 and TRM / 2.0-3 01/28/2005 Page TRM / 2.0-4 06/25/2002 Page TRM / 2.0-5 04/02/1999 Page TRM / 2.0-6 03/27/2008 Page TRM / 2.0-7 05/15/2008 Page TRM / 2.0-8 03/27/2008 Page TRM / 2.0-9 11/15/2004

-Page TRM / 2.0-10 02/02/2010 Page TRM / 2.0-11 11/15/2004 Page TRM / 2.0-12 03/27/2008 Pages TRM / 2.0-13 and TRM / 2.0-14 11/15/2004 Page TRM / 2.0-15 11/15/2005 3.0 APPLICABILITY Page TRM / 3.0-1 04/14/2008 Page TRM / 3.0-2 04/12/2007 Page TRM / 3.0-3 03/15/2002 Page TRM / 3.0-4 11/30/2005 3.1 REACTIVITY CONTROL SYSTEMS Page TRM / 3.1-1 10/31/2007 Pages TRM / 3.1-2 through TRM / 3.1-5 08/31/1998 Page TRM / 3.1-6 03/22/2006 Page TRM / 3.1-7 04/07/2009 Page TRM / 3.1-8 03/27/2008 Pages TRM / 3.1-9 and TRM / 3.1-9a 02/18/1999 Page TRM / 3.1-10 02/18/1999 3.2 CORE OPERATING LIMITS REPORT Page TRM / 3.2-1 07/07/1999 Pages TRM / 3.2-2 through TRM / 3.2-54 03/11/2010 3.3 INSTRUMENTATION Pages TRM / 3.3-1 through TRM / 3.3-3 07/16/1999 Page TRM / 3.3-4 and TRM / 3.3-5 10/31/2007 Page TRM / 3.3-6 08/31/1998 Page TRM / 3.3-7 10/31/2007 Page 3.3-8 08/31/1998 Page TRM / 3.3-9 04/12/2007 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 Page TRM / 3.3-9a 12/17/1998 Page TRM / 3.3-10 10/31/2007 Page TRM / 3.3-11 06/02/2005 Page TRM / 3.3-1 Ia 04/14/2008 Page TRM / 3.3-12 03/30/2001 Page TRM / 3.3-13 09/13/2005 Page TRM / 3.3-14 12/14/1998 Page TRM / 3.3-15 10/22/2003 Page TRM / 3.3-16 06/27/2001 Page TRM / 3.3-17 06/14/2002 Page TRM / 3.3-18 10/31/2007 Pages TRM / 3.3-19 through TRM / 3.3-21 10/22/2003 Page TRM /.3.3-22 03/27/2008 Page TRM / 3.3-22a 11/15/2004 Pages TRM / 3.3-22b through TRM / 3.3-22d 03/22/2006 Page TRM / 3.3-23 12/03/2004 Pages TRM / 3.3-24 and TRM / 3.3-25 05/16/2003 Page TRM / 3.3-26 10/22/2003 Pages TRM / 3.3-27 and TRM / 3.3-28 04/07/2009 3.4 REACTOR COOLANT SYSTEM Page TRM / 3.4-1 '03/31/2006 Pages 3.4-2 through 3.4-5 10/23/1998 Pages TRM / 3.4-6 through TRM / 3.4-8 04/01/2009 Page TRM / 3.4-9 08/31/1998 Page TRM / 3.4-10 10/31/2007 Page TRM / 3.4-11 08/31/1998 Page TRM / 3.4-12 03/27/2008 Page TRM / 3.4-13 03/31/2006 3-5 EMERGENCY CORE COOLING AND RCIC Page TRM / 3.5-1 01/28/2005 Pages 3.5-2 and 3.5-3 08/31/1998 Pages TRM / 3.5-4 and TRM / 3.5-5 10/31/2007 Pages 3.5-6 and 3.5-7 08/31/1998 3.6 CONTAINMENT Pages 3.6-1 through 3.6-3 08/31/1998 Page TRM / 3.6-4 01/07/2002 Page 3.6-5 08/31/1998 Pages TRM / 3.6-6 through TRM / 3.6-8 12/31/2002 3.7 PLANT SYSTEMS Pages 3.7-1 through 3.7-3 08/31/1998 Page TRM / 3.7-4 03/31/2006 TRM / LOES-2 EFFECTIVE DATE 03/11/2010 SUSQUEHANNA - UNIT SUSQUEHANNA - UNIT 1 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 04/07/2009 Pages TRM / 3.7-6 through TRM / 3.7-8 08/02/1999 Pages TRM / 3.7-9 and TRM / 3.7-10 04/07/2009 Page TRM / 3.7-11 12/29/1999 Page TRM / 3.7-12 08/02/1999 Page TRM / 3.7.13 04/07/2009 Page TRM / 3.7-14 08/09/2005 Pages TRM / 3.7-15 and TRM / 3.7-16 08/02/1999 Page TRM / 3.7-17 04/07/2009 Page TRM / 3.7-18 08/02/1999 Page TRM / 3.7-19 04/07/2009 Pages TRM / 3.7-20 through TRM / 3.7-22 08/02/1999 Page TRM / 3.7-23 04/07/2009 Page TRM / 3.7-24 03/31/2006 Pages TRM / 3.7-25 and TRM 3.7-26 08/02/1999 Page TRM 3.7-27 10/31/2007 Page TRM / 3.7-28 11/29/2006 Page TRM / 3.7-29 08/09/2005 Page TRM / 3.7-30 01/13/2010 Pages TRM / 3.7-31 and TRM / 3.7-32 11/16/2001 Page TRM / 3.7-33 01/09/2004 Page TRM / 3.7-34 11/16/2001 Page TRM / 3.7-34a 10/05/2002 Page TRM / 3.7-35 03/31/2006 Pages TRM / 3.7-36 and TRM / 3.7-37 02/01/1999 Pages 3.7-38 and 3.7-39 08/31/1998 Page TRM / 3.7-40 03/31/2006 Page TRM / 3.7-41 02/14/2005 Page TRM / 3.7-41a 06/20/2008 Page TRM / 3.7-42 09/04/2008 Page TRM / 3.7-43 08/31/1998 Pages TRM / 3.7-44 through TRM / 3.7-46 10/05/2006 Page TRM / 3.7-47 06/07/2007 Page TRM / 3.7-48 10/05/2006 Page TRM / 3.7-49 0610712007 Page TRM / 3.7-50 03/09/2001 Page TRM / 3.7-51 08/16/2006 Page TRM / 3.7-52 12/03/2004 Page TRM / 3.7-53 04/15/2003 Page TRM / 3.7-54 07/29/1999 Pages TRM / 3.7-55 through TRM 3.7-57 04/01/2009 3.8 ELECTRICAL POWER Page TRM / 3.8-1 04/02/2002 Pages TRM / 3.8-2 through TRM 3.8-4 01/28/2005 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 Effective Date Pages TRM / 3.8-5 and TRM / 3.8-6 04/02/2002 Page TRM / 3.8-7 10131/2007 Pages TRM / 3.8-8 through TRM / 3.8-10 12/03/2004 Page TRM / 3.8-11 09/03/2004 Page TRM / 3.8-12 12/03/2004 Pages 3.8-13 and 3.8-14 08/31/1998 Pages TRM / 3.8-15 through TRM / 3.8-17 04/02/2002 Page 3.8-18 08/31/1998 Page TRM / 3.8-19 04/02/2002 Page 3.8-20 08/31/1998 Pages TRM / 3.8-21 through TRM / 3.8-23 06/06/1999 Pages 3.8-24 and 3.8-25 08/31/1998 Page TRM / 3.8-26 05/28/2009 Page TRM / 3.8-27 11/29/2006 Pages TRM / 3.8-28 and TRM / 3.8-29 05/28/2009 3.9 REFUELING OPERATIONS Pages 3.9-1 through 3.9-3 08/31/1998 3.10 MISCELLANEOUS Page TRM / 3.10-1 03/31/2006 Pages 3.10-2 and 3.10-3 08/31/1998 Pages 3.10-2 and 3.10-3 08/31/1998 Page TRM / 3.10-4 08/01/2006 Pages TRM / 3.10-5 and TRM / 3.10-6 03/22/2006 Page TRM / 3.10-7 03/31/2006 3.11 RADIOACTIVE EFFLUENTS Page TRM / 3.11-1 03/31/2006 Pages 3.11-2 and 3.11-3 08/31/1998 Page TRM / 3.11-4 03/31/2006 Page 3.11-5 08/31/1998 Page TRM / 3.11-6 03/31/2006 Pages TRM / 3.11-7 through TRM / 3.11-9 08/31/1998 Page TRM / 3.11-10 12/03/2004 Pages 3.11-11 and 3.11-12 08/31/1998 Page TRM / 3.11-13 04/12/2007 Page TRM / 3.11-14 12/03/2004 Pages 3.11-15 and 3.11-16 09/01/1998 Page TRM /3.11-17 03/31/2006 Page 3.11-18 08/31/1998 Page TRM / 3.11-19 08/15/2005 Pages TRM / 3.11-20 and TRM / 3.11-21 03/31/2006 Page TRM / 3.11-22 04/02/2002 Page TRM /3.11-23 11/14/2006 TRM / LOES-4 EFFECTIVE DATE 03/11/2010 SSUSQUEHANNA -

UNIT I1 SUSQUEHANNA - UNIT 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 Effective Date Page TRM / 3.11-24 05/13/2005 Page TRM / 3.11-25 04/12/2007 Pages TRM / 3.11-26 and TRM / 3.11-27 01/21/2004 Page TRM / 3.11-28 09/08/2009 Page TRM / 3.11-29 12/03/2004 Pages TRM / 3.11.30 through TRM /3.11.32 01/21/2004 Page TRM / 3.11-33 03/31/2006 Page 3.11-34 08/31/1998 Page TRM / 3.11-35 03/31/2006 Pages TRM / 3.11-36 through TRM / 3.11-39 11/30/2005 Pages 3.11-40 through 3.11-43 08/31/1998 Page TRM / 3.11-44 08/01/2006 Page TRM / 3.11-45 03/31/2006 Page 3.11-46 08/31/1998 Page TRM / 3.11-47 03/31/2006 3.12 LOADS CONTROL PROGRAM Pages TRM / 3.12-1 through TRM / 3.12-3 02/05/1999 Page TRM / 3.12-4 " 03/14/2008 Page TRM / 3.12-5 02/05/1999 4.0 ADMINISTRATIVE CONTROLS Pages TRM / 4.0-1 through TRM / 4.0-3 08/31/1998 Page TRM / 4.0-4 12/11/2008 Pages TRM / 4.0-5 through TRM / 4.0-8 08/31/1998

-w SUSQUEHANNA - UNIT 1 TRM / LOES-5 EFFECTIVE DATE 03/11/2010

SUSQUEHANNA STEAM ELECTRIC STATION PPL Rev. 56 LIST OF EFFECTIVESECTIONS (TECHNICAL REQUIREMENTS MANUAL)

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

UNIT I1 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 REACTOR COOLANT SYSTEM BASES Page B 3.4-1 08/31/1998 Pages TRM / B 3.4-2 and TRM / B 3.4-3 04/01/2009 Pages TRM / B 3.4-4 and TRM / B 3.4-4a 10/31/2007 Page TRM / B 3.4-5 10/15/1999 Page B 3.4-6 08/31/1998 B 3.5 ECCS AND RCIC BASES Pages B 3.5-1 and B 3.5-2 08/31/1998 Pages TRM / B 3.5-3 through TRM / B 3.5-5 10/31/2007 B 3.6 CONTAINMENT BASES Page TRM / B 3.6-1 07/26/2001 Page TRM / B 3.6-2 02/01/1999 Page B 3.6-3 08/31/1998 Page TRM / B 3.6-4 03/27/2008 Page TRM / B 3.6-5 04/04/2007 Page TRM / B 3.6-6 12/03/2004 Pages B.3.6-7 through TRM / B 3.6-11 12/31/2002 B 3.7 PLANT SYSTEMS BASES Pages B 3.7-1 and B 3.7-2 08/31/1998 Pages TRM / B 3.7-3 and TRM / B 3.7-3a 12/27/2007 Page TRM / B 3.7-4 03/31/2006 Page TRM / B 3.7-5 08/02/1999 Page TRM / B 3.7-6 03/31/2006 Pages TRM / B 3.7-7 and TRM / B 3.7-7a 08/02/1999 Page TRM / B 3.7-8 08/02/1999 Page TRM / B 3.7-9 03/31/2006 Page TRM I B 3.7-10 08/02/1999 Page TRM / B 3.7-1Oa 03/31/2006 Page TRM / B 3.7-11 08/02/1999 Page TRM / B 3.7-11a 03/31/2006 Pages TRM / B 3.7-12 through T\RM / B 3.7-14 08/02/1999 Page TRM / B 3.7-14a 08/02/1999 Page TRM / B 3.7-14b 01/09/2004 Pages TRM / B 3.7-15 and TRM / B 3.7-16 02/01/1999 Pages B 3.7-17 through B 3.7-20 08/31/1998 Page TRM / B 3.7-21 02/14/2005 Page TRM / B 3.7-21a 06/20/2008 Page TRM / B 3.7-22 and TRM / B 3.7-23 01/30/2008 Pages TRM / B 3.7-24 through TRM / B 3.7-28 10/05/2006 Pages TRM / B 3.7-29 and TRM / B 3.7-30 06/07/2007 Pages TRM / B 3.7-30a and TRM / B 3.7-30b 10/05/2006 Page TRM / B 3.7-31 12/03/2004 Page TRM / B 3.7-32 03/09/2001 TRM / LOES-7 EFFECTIVE DATE 03/11/2010 SUSQUEHANNA - UNIT SUSQUEHANNA -

UNIT 1 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 Page TRM / B 3.7-33 04/15/2003 Page TRM / B 3.7-34 12/03/2004 Page TRM / B 3.7-35 07/05/2000 Pages TRM / B 3.7-36 through TRM / B 3.7-40 04/01/2009 B 3.8 ELECTRICAL POWER BASES Page TRM / B 3.8-1 04/02/2002 Pages TRM / B 3.8-2 and TRM / B 3.8-2 01/28/2005 Page TRM / B 3.8-2a 03/01/2010 Page TRM / B 3.8-3 04/02/2002 Page TRM / B 3.8-3a 04/02/2002 Page TRM / B 3.8-4 08/10/2004 Page TRM / B 3.8-4a 04/02/2002 Page TRM / B 3.8-5 08/31/1998 Pages TRM / B 3.8-6 through TRM / B 3.8-16 04/02/2002 Page TRM / B 3.8-17 01/28/2005 Pages TRM / B 3.8-18 through TRM / B 3.8-20 11/29/2006 Pages TRM / B 3.8-21 through TRM / B 3.8-24 05/28/2009 B.3.9 REFUELING OPERATIONS BASES Pages B 3.9-1 through-B 3.9-7 08/31/1998 B 3.10 MISCELLANEOUS BASES

-Page B 3.10-1 08/31/1998 Pages TRM / B 3.10-2 and TRM / B 3.10-3 03/22/2006 Pages TRM / B 3.10-4 and TRM / B 3.10-5 08/23/1999 B 3.11 RADIOACTIVE EFFLUENTS BASES Pages B 3.11-1 through B 3.11-9 08/30/1998 Page TRM / B 3.11-10 02/01/1999 Pages TRM/B 3.11-11 and TRM/B 3.11-11 a 04/07/2000 Pages TRM/B 3.11-12 and TRM/B 3.11-13 02/01/1999 Page TRM / B 3.11-14 12/03/2004 Page TRM / B 3.11-15 02/01/1999 Pages B 3.11-16 through B 3.11-19 08/30/1998 Page TRM / B 3.11-20 04/02/2002 Page TRM / B 3.11-20a 04/02/2002 Page TRM / B 3.11-21 05/13/2005 Pages TRM / B 3.11-22 and TRM / B 3.11.23 1.1/14/2006 Page TRM / B 3.11.23a 05/13/2005 Pages TRM / B 3.11-24 and TRM / B 3.11-25 01/21/2004 Pages B 3.11-26 and B 3.11-27 08/30/1998 Pages TRM / B 3.11-28 and TRM / B 3.11-29 11/30/2005 Page TRM / B 3.11-30 12/03/2004 Pages B 3.7-31 through B 3.7-35 08/30/1998 Page TRM / B 3.11-36 02/12/1999 TRM / LOES-8 EFFECTIVE DATE 03/11/2010 SUSQUEHANNA - UNIT SUSQUEHANNA -

UNIT 11 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 09/19/2007 Pages TRM / B 3.12-2 and TRM / B 3.12-3 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)

PPL Rev. 11 3.2.1 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 PS 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 NS ............................................................................................................. 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 NC 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 TM-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

>.-*z. *.. : , . . . . . . .... . *,  ! REFERENCE T'S" 3.2"I. ' .

z ~14.0 " '. ,......r.............. --, - -------- " ".."..".......... "....-.----."..'.'"T"""" , "*. .. , "

. USED IN DETERMININ MAGRAT (0.0, 12.5)"- ' . (15000, 12.5): - .' . . . . . ..- .... ..

~

-- ~ n - . .... ' .. ... ...... . . .. . . . . ."

w -2 1 . .. . .. . . . . . . . . . . .. . . .. . .... ... r-(D

-17~

> .j. . ~.;. .. ., . , .. . ...... .

.... . . .. .. . . ..... -- -. -. .- . . -- -9)-- --- - - - - -

m -- *.. .. . . . . . . . .. . .(67000,69 6 .0 -- - - - - - - - - - - - - -- -- - -- - - - - - - - - - - - -- --

CD 4.0 °, - -m - - -* - ° t - - . , * .* . . . .* .

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 SSES UNIT 1 CYCLE 17 2.2 I 1 I 1 m LEGEND 2.1 CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME 2.0 CURVE B: REAUSTIC AVERAGE SCRAM INSERTION TIME 1.9 SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2

-q 1.8 USED IN DETERMINING MFLCPR

-u

-u

• 1.7 I-0.. :xj 0 (30, 1.61) CD L 1.6 1.5 m

-n

-T-m 1.4

REFERENCE:

T.S. 3.2.12 m 1.3 -(108,1.23)

CD 1.2 Cm 30 40 50 60 70 80 90 100 110 Total Core Flow (MLB/HR) CD r-CD MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW MAIN TURBINE BYPASS! EOC-RPT/ BACKUP PRESSURE REGULATOR OPERABLE 0'

TWO LOOP OPERATION (BOC TO EOC) 0 FIGURE 5.2-1

-1f

0 SSES UNIT 1 CYCLE 17 cz 3.6 II I I . I 3.4 1~ LEGEND c- 3.2 1 ILl

-- CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME (23, 3.06) (23, 3.11)

CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME 3.0 [ " (26, 2.97)

(26, 2.81A)

• CURVE C: CORE POWER 5 26% AND CORE FLOW *50 MLBM/HR 2.8 ý- C ,

.E

-H

-J 2.6 -SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE

_ -jPER SR 3.7.6.1 AND 3.7.6.2 -u I'-

Ed 2.4 0.

009 CD

' ]JUSED IN DETERMINING MFLCPR 2.2 (26.01, 2.00)

,*_ I (26.01, 1.91) F- 4 4. 4 I 4 +

m 1.8 -

4. 4 F 4 +

m (40, 1.70)

F 4. -4 F 4 +

- . a A

m 1.6 F 4 -........~4- - 4 F +

(40, 1.63)

- - (80, 1.45) m 4. 10 -- (94.46,1.37)" (100, 1.36)

CD)

WH 1.4 CD 1.2 II

REFERENCE:

T.S. 3.2.21

4. 4 F (80, 1.41) (85, 1.39).

(94.46, 1.33)

(100,1.33) 20 30 40 50 60 70 80 90 00 "o

Core Power (% RATED) CD CD MCPR OPERATING LIMIT VERSUS CORE POWER "0

MAIN TURBINE BYPASS / EOC-RPT/ BACKUP PRESSURE REGULATOR OPERABLE 0 0 TWO LOOP OPERATION (BOC TO EOC) cn 0 co FIGURE 5.2-2

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/) SSES UNIT 1 CYCLE 17 c/) 2.2 m7 LEGEND 2.1 CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME 2:

(30, 2.00) CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME 2.0 SAFETY ANALYSES ASSUME THA'T TWO OR MORE BYPASS VALVES AR 1.9 INOPERABLE PER SR 3.7.6.1 OR 3.7.6.2 USED IN DETERMINING MFLCPR E 1.8

-J A

CO F B Cu r-1.7 0.

1 CD cc

,.o1.6 1.5 mT m

1.4 m T.S. 3.7.6 1

REFERENCE:

C) 1.3

__ _ _ I1__ _ _ _ _ _ _ _ _ _ __ _ _ _ _ _ _ _ _ _

CD 1.2 30 40 50 60 70 80 90 100 110

-u Total Core Flow (MLB/HR) z

-Il MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW (n MAIN TURBINE BYPASS INOPERABLE 0 0 0

TWO LOOP OPERATION (BOC TO EOC) cn 0 CIO FIGURE 5.2-3

SSES UNIT 1 CYCLE 17 3.6 23, 3.51) 3.4

-CD (26, 3.23)

.: MAXIMUM ALLOWABLE AVERAGE SCRAM tiz_

3.2 INSERTION TIME (23, 3.06

REALISTIC AVERAGE SCRAM INSERTION TIME 3.0 (26, 2.86)- 4. 1o %%I -

CORE POWER <26% AND CORE FLOW 5 50 MLBM/HR 2.8 I _C I4

-4It4

• J 2.6 0)

.S= SAFETY ANALYSES ASSUME THAT TWO OR MORE BYPASS VALVES ARE Ul) 2.4 INOPERABLE PER SR 3.76.1 OR 3.7.6.2 r-0 (D mr (L 2.2 (26.01, 2.03) USED IN DETERMINING MFLCPR 2.0

4. 4- I (40, 1.74) I m 1.8 + - 4 4

-n A m 4- 1 ~ I B (70, 1.56)'

C-)

1.6 I I100.00,1.56)

+/ ______

4 1 .1. .1 REFERENCE

• 4 T.S3.7.6and 32.2 m

CD 1.4 1.2 20 30 40 50 60 70 80 90 100 C-)

Core Power (% RATED)

(0<

CD~ '

MCPR OPERATING LIMIT VERSUS CORE POWER c) -n MAIN TURBINE BYPASS INOPERABLE o)

TWO LOOP OPERATION (BOC to EOC) -4 c C.0 FIGURE 5.2-4

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

SSES UNIT 1 CYCLE 17 c( 2.2 m 3END .- -i i 2.1 RVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME 2.0 4-ILUE WE B: REALISTIC AVERAGE SCRAM INSERTION TIME 1.9 4 4-!

SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2

_E

-H 1.8

.. USED IN DETERMINING MFLCPR 4-a-

1.7 I, CD (30, 1.61) .- L a-1.6 1.5 m

m A B m

m 1.4 C-)

-H m

REFERENCE:

T.S. 3.3.4.1 and 3.2.21 ci 1.3 _ _ _ _I--(108,1.23)-

-H m

ci 1.2 30 40 50 60 70 80 90 100 110 R) ci Total Core Flow (MLB/HR) T I'

CD CD MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW -C) n1 00 EOC-RPT INOPERABLE 0p TWO LOOP OPERATION (BOC TO EOC) 0 FIGURE 5.2-5

SSES UNIT 1 CYCLE 17 3.6 I I iD 3.4 3.2 -(23, 3.1)-

I I "A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME (23, 3.06) 1 CURVE. B: REALISTIC AVERAGE SCRAM INSERTION TIME 3.0 (26,2.97)

(26, 2.86) CURVE C: CORE POWER *26% AND CORE FLOW <50 MLBM/HR 2.8 -C --

E

-J 2.6 SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 CD 2.4 0 F* USED IN DETERMINING MFLCPR (D cL 2.2 (26.01, 2.00) 2.0 mr 1.8 %4;;;:zz(40, l.-jn-7vil I 1 .5. .4.

m A 4

1.6 (80, 1.45) 4.

m I _ _ _ I _

-J I s (94.46, 1.43)-(100, 1.43)

CD 1.4 REFERENCE T ad322 CD 1.2 20 30 40 50 60 70 80 90 100 Core Power (% RATED) (D (D

(.0 0 MCPR OPERATING LIMIT VERSUS CORE POWER EOC-RPT INOPERABLE (0 0

TWO LOOP OPERATION (BOC to EOC) CD) i FIGURE 5.2-6

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)

SSES UNIT 1 CYCLE 17 CD1 2.2 I I I I LEGEND 2.1 CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME 2.0 1~ 1- 1 CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME

[

1.9 + + 4 4 SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2

-N ..J 1.8 l USED IN DETERMINING MFLCPR

-tJ 03 I-CD 0~ (30, 1.61) 5 C.) 1.6 1.5 C-) 1.4 CD 1.3

_ _ I

REFERENCE:

T.S. 3.7.8 and 3.2.2

_ _- _ _0_ _,_1__2_ _ _

1.23)-

1.2 30 40 50 60 70 80 90 100 110 Total Core Flow (MLB/HR) WD CD r-CD CD

• MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW o -n BACKUP PRESSURE REGULATOR INOPERABLE TWO LOOP OPERATION (BOC TO EOC)

CA) I~

FIGURE 5.2-7

c/)

SSES UNIT 1 CYCLE 17 3.6 I I m I D

3.4 I A: MAXIMUM ALLOWABLE AVERAGE SCRAM 3.2 [-(23, 3.11) INSERTION TIME (23, 3.0

,306) 1 (26,2.97)

CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME (26, 2.86) CURVE C: CORE POWER <26% AND CORE FLOW < 50 MLBM/HR 2.8 H C" E

-' 2.6 SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES

-(26.01,2.40) ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 -u 7-1 I-

-I, 2.4 0 USED IN DETERMINING MFLCPR CD 5

a. 2.2 2.0 0A 1.8 m

m (80, 1.48) 1.6 (100, 1.36) m C~)

N) mR 1.4 1.2

_ _ _ I

REFERENCE:

T.S. 3.7.8 and 3.2.2 (94.46,1 1.37)

_.4

-D 20 30 40 50 60 70 80 90 100 Core Power (% RATED) CD CD z 0

MCPR OPERATING LIMIT VERSUS CORE POWER N)

BACKUP PRESSURE.REGULATOR INOPERABLE 0 0 TWO LOOP OPERATION (BOC to EOC) 0Q1 WA FIGURE 5f2-8

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 i I .I ,i ,l i l.i ll O ~ a 14.0 (0.0, 13.4)-------(189oo, 13.4)-:-------------EFERENCE: T.S. 3.2.3 USED INIETERMINING Ii FDLIRXIi E

8.0. .... ... .... ...... . .. .. . .. ... ....

C -D g~ ~~ iII . ~ .I .S.1 .II .I . . .OIi . . I . . iI*J1III 4.0. . .. . . . . . .. . .. . . . .. . . . ../ . .. ..

I l l I lI IUI l l I I ~ ~ l l l l l l l l IIi

. . .. . . . . . . . . . . . .. . . . .. . . . .. .. .. . .. . . . . . . . . . . . . . . . . J . . . . . . . . . . . . . . .CA)'

6.0 - ---- --

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-ATRIUM -.. 1.0 FUEL 0 FIGURE 6.2-1 cn C

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)  :

0 1.0........................

. 0. .........................

. . .. . ...... ... . .-- -- -- --- -- - -- (- 8,.. 00) cc.

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

. . . . S0.7 - - - - . . . . . . . . . . . . . ... - - - - - - - -,I - - - - - - - - -

. . . .. . I----- - .. ...

-j-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............ ................. L ------------

a.----- ----------------------......... ..................

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 ,,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) 0.8  :

.. .U

.1.....

-AREOER I ......

BEPE-R3-.-

I ......

...r.......

AND A---

--- 3.7.6.2 I ----- I - -

4--

I- -

-n

. . . (26.01,0.65)

I I I I II °

• 0 * * * * *

REFERENCE:

T.S. 3.2.3 and 3.7.6 -

USED IN DETERMINING FDLRX 0 .6. . . . . . . . . . . . I. . . .. . . . . . . . .. . . . .I III ""

m* m (26,0.46) 0.4 26.01,05

-- -...... I ...... ................. . .. . .- - -

(,RE)ERENCE: T.S. 32

.. (23 A-R 0343)9 FUE 0263.42 ------------ ----- FI-UR . 2..-- ..... I .... .....

39(... (23 Cor Pwe RAED 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

~~1.10 1SSES UNIT 1 CYCLE 17 (99, 1.00)

I. ...... .....

0.0....--....I- --I- --Io. .. . .. . ... .... .....

.. ... .. .. .. .. . ... ... ..... 4......a...... I ..... .. . ..... ........ .. * . I.. . .

a. .. .. . .. .. .. ................. . a a 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 a a a a a , a

-71 0.60 , . . ....... .....

REFERENCE:

T.S. 3.2.3 and 3.7

..................... a-----------

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

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

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

a..... - -- - ..... .... .....

... 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) .....

0.90 -----------------------------------------------------------------

9 ................... .. . .. . ........ ..... ....--....... .......... - .. . .-----.............

. . . . . . (100,0.93)

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

-- A..

\0.7 0 .6 -. ....----. .... ..... . .....

.. .i . .i . ---. ..

, SAFETY ANALYSES ASSUME THAT TWO OR MORE BYPASS VALVES C CLIARE INOPERABLE PER SR 3.7.6.1 OR 3.7.6.2--

0 (2  :

,,4). (26.01,0.65) , * * * ,

( 60. 46 ................. ..... .. .. . ...... ------ .

REFERENCE:

.. . ....i ............ " T.S. " r........ . . . . .

3.2.3 and 3.7.6 . . . .r m

0 . . . .

0* ~(26.0,0.42) m, 0.4 -..--..... ..... ....... . .-- . .--... ... USED IN DETERMINING FDLRX "5 (23,0.43) B ( 2.. ................................................... . .

---

. -. ----------...... ...... ...... ............. I- - -- I------

(23-n,0.9  :  :  ::  :

CD D C-') 0.3 (2 ,0.9D.... I 20 30 40 50 60 70 80 90 100 CD ~~Core Power (% RATED) CDr 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 < 1.76

Ž90 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 TM-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 14.0--------------------------------,--------------------------R REEENCE T.S. 3.4.1 and 3.2.1

• O. C

:::::::  ::.USED i INDETERMINING MAPRAT

, 0 * = -*Ui 8 . ....... .

-711 3 w.2 12.0-....r 6.0.... ....................... j............. ,...... .,=j .....*... t,,.. .=.... j. ., .. j...... =.....S ,*j E

6.

CDD

> 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 0

ATRIUMMTMj -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

SSES UNIT 1 CYCLE 17 4.6 m _LEGEND 4.4 4.2 CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME 4.0 CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME 3.8 3.6

= 34 SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 cn 3.2 C-r-

R) (D 3.0 USED IN DETERMINING MFLCPR

0. CD 0

cc 2.8 2.6 2.4 2.2 -- (30, 2.03)

A B 2.0 m 1.8 (108, 1.56) m CD W 1.6 1.4 mD 30 40 50 60 70 80 90 100 110

'-u Total Core Flow (MLB/HR) CD (D

0 z T1 MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW (0 0

cDn MAIN TURBINE BYPASS / EOC-RPT/ BACKUP PRESSURE REGULATOR OPERABLE 0 lp 0

SINGLE LOOP OPERATION (BOC to EOC) 0a FIGURE 8.2-2

V)

SSES UNIT 1 CYCLE 17 4.6 _______

____ II_______

____ I____

I LIAJINU I I I 4.4 CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM 4.2 INSERTION TIME 4.0 - (23, 3.89)

CURVE B: REALISTIC AVERAGE SCRAM TIME (23, 3.83) 3.8 E %, (26, 3.72) CURVE C: CORE POWER < 26% AND CORE FLOW < 50 MLBM/HR

-K 3.6 ,3.58)_

(26,

= 3.4 i SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES C

Cr-.__

ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 o* 3.2 3.0 _ ____----I USED IN DETERMINING MFLCPR 0 CD CC2.8 0.

-- (26.01, 2.52) 2.6 2.4 2!t- -- 40,2.15)-

2.2

-(60, 1.99) 2.0 (100,1.99)

An 1.8 c-)

1.6

REFERENCE:

T.S. 3.4.1 and 3.2.21 f'-H mD 1.4 20 30 40 50 60 70 80 90 100 Core Power (% RATED) (D r-CD MCPR OPERATING UMIT VERSUS CORE POWER o -

MAIN TURBINE BYPASS / EOC-RPT / BACKUP PRESSURE REGULATOR OPERABLE 0 0 SINGLE LOOP OPERATION (BOC to EOC)

FIGURE 8.2-3

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

0 SSES UNIT 1 CYCLE 17 4.6

_LEGEND 4.4 4.2 CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME

-H 4.0 CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME 3.8 3.6 SAFETY ANALYSES ASSUME THAT TWO OR MORE BYPASS 3.4 VALVES ARE INOPERABLE PER SR 3.7.6.1 OR 3.7.6.2

-.H 7,J o 3.2 cc at 3.0 USED IN DETERMINING MFLCPR I-0.

01=2.8 CD

0. (30, 2.52)

• 2.6 A 2.4 m 2.2 m

• _ (108,1.88)_

2.0 m 1.8 --*

REFERENCE:

T.S. 341376,and 3.2.2 -

CD) 3.4.1,3.7._________ _________ _________ _________ _________ ____,____

1.6 1.4 30 40 50 60 70 80 90 100 110 Total Core Flow (MLB/HR) (D r-(D MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW Cc MAIN TURBINE BYPASS INOPERABLE C.0 0

SINGLE LOOP OPERATION (BOC to EOC)

FIGURE 8.2-4 J p

SSES UNIT 1 CYCLE 17 4.6 1 LEGEND 4.4 --- (23, 4.39) CURVE A

MAXIMUM ALLOWABLE AVERAGE SCRAM 4.2 INSERTION TIME 4.0 (26, 4.04)CV B:: REALISTIC AVERAGE SCRAM INSERTION TIME (23,383)-CURVE cz) 3 .8 CURVE C

CORE POWER <*26% AND CORE FLOW <50 MLBM/HR M, 3.58)

'T_3.4 -

SAFETY ANALYSES ASSUME THAT TWO OR MORE BYPASS o*3.2 VALVES ARE INOPERABLE PER SR 3.7.6.1 OR 3.7.6.2 I-"

(-l) 3.0 0 USED IN DETERMINING MFLCPR (D 5

2 8 mr .

a.

(26.01, 2.55) -

2.6 2.4

...... _ ___(40, 2.19) _

m 2.2 71 _ _ _(60, 2.05) -(100, 2.05) 2.0 B 1.8

REFERENCE:

T.S. 3.4.1, 3.7.6, and 3.2.21 1.6 1.4 20 30 40 50 60 70 80 90 100 m -u Core Power (% RATED)

CD MCPR OPERATING LIMIT VERSUS CORE POWER c -n MAIN TURBINE BYPASS INOPERABLE 0 Cl SINGLE LOOP OPERATION (BOC to EOC) 0) 01 CIO i FIGURE 8.2-5

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/) SSES UNIT 1 CYCLE 17 c/) 4.6 m

4.4 ,LEGEND

>" 4.2 CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME

--H 4.0 CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME 3.8 3.6 SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES

_3.4 ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 C4-

_USED IN DETERMINING MFLCPR c 3.0 CD it 2.8 0-S2.6 2.4 m

2.2 -(30, 2.03) 'A B m 2.0 m 1.8 -(108,1.56)

CD m' 1.6 -

REFERENCE:

T.S. 3.4.1, 3.3.4.1, and 3.2.2 CD 1.4 30 40 50 60 70 80 90 100 110 I ,

Total Core Flow (MLB/HR) CD CD r-CD Co CD MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW EOC-RPT INOPERABLE C SINGLE LOOP OPERATION (BOC to EOC) C C,,

FIGURE 8.2-6

V1)

SSES UNIT 1 CYCLE 17 I I I I 4.4 LEGEND

_-H 4.2 CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM NSERTION TIME 4.0 L( 2 3 , 3 .8 9 ).

(23, 3.83) CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME 3.8 ..

3. C -(26, 3.72)

CURVE C: CORE POWER <26% AND CORE FLOW < 50 MLBM/HR 3.6 -

(26,3.58) -

E3.4

.S o*3.2 SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 I--

0 USED IN DETERMINING CD C2.8 MFLCPR Q.

a.,

2.6 (26.01, 2.52) 2.4 (*40,2.15) 2.2 m __(60, 1.99) A B 2.0 (100, 1.99) 1.8 C-)

-W 1.6

REFERENCE:

T.S. 3.4.1, 3.3.4.1, and 3.2.2 j 1.4 20 30 40 50 60 70 80 90 100 Core Power (% RATED) n0 <

z MCPR OPERATING LIMIT VERSUS CORE POWER c-n EOC-RPT INOPERABLE 0 0iC SINGLE LOOP OPERATION (BOC to EOC) 0 0..

FIGURE 8.2-7

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) SSES UNIT 1 CYCLE 17 cz: 4.6 V) I I I I 4.4 LEGEND CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM 4.2 INSERTION TIME 4.0 CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME 3.8 _____________ _____________

3.6 I i-.-.-! I.

S3.4 4 I I-i i SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE PER SR 3.76.1 AND 3.7.6.2 ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 CIO m 3.2 USED IN DETERMINING MFLCPR -U 3.0 (-

CD 0cc 2.8 a,.

C.6

~2.6 2.4 Fm n 2.2 -- (30, 2.03)- A......

m 2.0 m 1.8 CD _-REERECE:T.S3..1 3..8, a _3(108,1.56)

W 1.6

REFERENCE:

T.S. 3.4.1, 3.7.8, and 3.2.2_ _____

N) 1.4

-H CD 30 40 50 60 70 80 90 100 110 Total Core Flow (MLB/HR) CD r-(D

• -0 MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW (0 BACKUP PRESSURE REGULATOR INOPERABLE CIO c 6-SINGLE LOOP OPERATION (BOC to EOC) 0 FIGURE 8.2-8

C/)

SSES UNIT 1 CYCLE 17 4.6 1* r -

+ 4-LEGEND 4.4 + 4- .4--- --

4. 4.-

4.2 + 4. CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM J*A

• A*l + 4- INSERTION TIME 4.0 ý-(23, 3.89R)

(23,3.3)- CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME 3.8 i 1(26, 3.72)

CURVE C: CORE POWER _26% AND CORE FLOW *50 MLBM/HR 3.6 -

(26, 3.58).

3.4 [C -

3.2 1111i (26.01, 3.01) 14 E

SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 -a

-71 *_3.0 I'-

E CD Z 2.8 ~_(40, 2.72) " USED IN DETERMINING MFLCPR o')

.S

= 2.6 0 2.4 0.

IS B(60,2.29)- (100, 2.29)

U 2.2 m

2.0 C) m 1.8 CD

REFERENCE:

T.S. 3.4.1,'3.7.8, and 3.2.2IZ 1.6 N) 1.4 m2 20 30 C) 40 50 60 70 80 90 100 Core Power (% RATED) CD Lo (D

MCPR OPERATING LIMIT VERSUS CORE POWER o -

BACKUP PRESSURE REGULATOR INOPERABLE I SINGLE LOOP OPERATION (BOC to EOC) 0, C) 0)

FIGURE 8.2-9 CIO

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 110--Ti APFCM epit Scram T Initial/Date: 110 i ------

_LAPRMV Rod Block SOPRIMINOPERABLE IMMEDIATE Trip Setp.in.

100 SCRAM lAWON-178-002 100 IF OPRM OPERABLE IMMEDIATE EXIT lAW ON-178-002 E L IMMEDIATELY EXrT AW ON-178-002 90 90 L

(As defined in Atiachment G to NDAP-GA-0338)

-:FABOVEMELLLA BOUNDARY, I -

EXITlAWON-178-002 ' 9ld IMMEDIATELY 80 80

--- - .- ,-- - - *- - -- - - *-- - - :-'*  : ýA I- 70 - 70 OR -- ;

• 60 ..... 60 0

060 E 4) 50

... .7R7

-"2 Rod____

5 50e 40 Natural Line Circulation - - - - -i- - "-- 40 30 Apr .. . - 30' 30-/6 pee30 2  :.20 x

.:~~~-- .;: -,. - - - - - -.-T -.---- - - . . T ;

• 10 ,*' ;10

. *. : ... 100 .. . " * : .N.., IX. d. , : , , "! : : , : ! . . .Se ,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 TM-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