ML12110A115
| ML12110A115 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 04/11/2012 |
| From: | Susquehanna |
| To: | Gerlach R Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| 028401 | |
| Download: ML12110A115 (81) | |
Text
Apr. 11, 2012 Page 1 of 2 MANUAL HARD COPY DISTRIBUTION DOCUMENT TRANSMITTAL 2012-21776 USER INFORMATION-GERLACH*ROSE M EMPL#:028401 CA#: 0363 Address: NUCSA2 Phone#: 254-3194 TRANSMITTAL INFORMATION:
TO: GERLACH*ROSE M 04/11/2012 LOCATION: USNRC FROM: NUCLEAR RECORDS DOCUMENT CONTROL CENTER (NUCSA-2)
THE FOLLOWING CHANGES HAVE OCCURRED TO THE HARDCOPY OR ELECTRONIC MANUAL ASSIGNED TO YOU. HARDCOPY USERS MUST ENSURE THE DOCUMENTS PROVIDED MATCH THE INFORMATION ON THIS TRANSMITTAL. WHEN REPLACING THIS MATERIAL IN YOUR HARDCOPY MANUAL, ENSURE THE
- UPDATE DOCUMENT ID IS THE SAME DOCUMENT ID YOU'RE REMOVING FROM YOUR MANUAL. TOOLS FROM THE HUMAN PERFORMANCE TOOL BAG SHOULD BE UTILIZED TO ELIMINATE THE CHANCE OF ERRORS.
ATTENTION: "REPLACE" directions do not affect the Table of Contents, Therefore no TOC will be issued with the updated material.
TRMI - TECHNICAL REQUIREMENTS MANUAL UNIT 1 REMOVE MANUAL TABLE OF CONTENTS DATE: 12/09/2011 ADD MANUAL TABLE OF CONTENTS DATE: 04/10/2012 CATEGORY: DOCUMENTS TYPE: TRMI cp I
ý-, vu
Apr. 11, 2012 Page 2 of 2 ID: TEXT 3.2.1 ADD: REV: 13 REMOVE: REV:12 CATEGORY: DOCUMENTS TYPE: TRMI1 ID: TEXT LOES ADD: REV: 71 REMOVE: REV:70 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: 04/10/2012 Procedure Name Rev Issue Date Change ID Change Number TEXT LOES 71 04/10/2012
Title:
LIST OF EFFECTIVE SECTIONS TEXT TOC 21 12/08/2011
Title:
TABLE OF CONTENTS 7>.,
TEXT 1.1 0 11/18/2002
Title:
USE AND APPLICATION DEFINITIONS "
TEXT 2.1 1 02/04/20095>'
Title:
PLANT PROGRAMS AND SETPOINTS PLANT PROGRAMS TEXT 2.2 9 01/13/2011
Title:
PLANT PROGRAMS AND SETPOINTS iNSTRUMENT TRIP SETPOINT TABLE LDCN 4414 TEXT 3.0 > 4 05/23/2008
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 13 04/10/2012
Title:
CORE OPERATING LIMITS REPORT (COLR)
Report Date: 04/11/12 Page 1 1 of of 16 16 Report Date: 04/11/12
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 3 03/31/2-011
Title:
INSTRUMENTATION SEISMIC MONITORING INSTRUMENTATION TEXT 3.3.3 2 11/09/2007
Title:
INSTRUMENTATION METEOROLOGICAL MONITORING INSTRUMENTATION TEXT 3.3.4 6 07/09/2010
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 3 01/13/2011
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: 04/11/12 Page2 Page 2 of 16 of .16 Reportbgte: 04/11/12
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 3.4.6 1 06/15/2010
Title:
REACTOR RECIRCULATION SINGLE LOOP OPERATION SLO FLOW RATE RESTRICTION 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 1 08/23/2011
Title:
SUPPRESSION CHAMBER TO DRYWELL VACUUM BREAKER POSITION INDICATION TEXT 3.6.3 0 11/18/2002
Title:
CONTAINMENT SUPPRESSION POOL ALARM INSTRUMENTATION Report Date: 04/11/12 Page~
Page 3 of of ~16 Report Date: 04/11/12
SSES MANUAL Manual Name: TRMI Manual
Title:
TECHNICAL REQUIREMENTS MANUAL UNIT 1 TEXT 3.6.4 0 11/18/2002
Title:
CONTAINMENT PRIMARY CONTAINMENT CLOSED SYSTEM BOUNDARIES 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 9 11/30/2011
Title:
PLANT SYSTEMS FIRE DETECTION INSTRUMENTATION LDCN 3503 TEXT 3.7.4 1. 04/26/2006
Title:
PLANT SYSTEMS SOLID RADWASTE SYSTEM Report Data: ~04/11/12 Page 44 of 16 of. 16 R61ý6iýý Date: '04/11/12
SSES -MANUAL Manual Name: TRM1 Manual
Title:
TECHNICAL REQUIREMENTS MANUAL UNIT 1 TEXT 3.7.5.1 0 11/18/2002
Title:
PLANT SYSTEMS MAIN CONDENSER OFFGAS HYDROGEN MONITOR 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 2 04/05/2010
Title:
ELECTRICAL POWER PRIMARY CONTAINMENT PENETRATION CONDUCTOR OVERCURRENT PROTECTIVE DEVICES 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 RportDate 04/1/1 Page of ~.
Page 5 of 16 Report Date: 04/11/12
SSES MANUAL Manual Name: TRMI Manual
Title:
TECHNICAL REQUIREMENTS MANUAL UNIT 1 TEXT 3.8.3 1 04/05/2010
Title:
ELECTRICAL POWER DIESEL GENERATOR (DG) MAINTENANCE ACTIVITIES 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 1 12/08/2011
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 2 06/15/2010
Title:
MISCELLANEOUS INDEPENDENT SPENT FUEL STORAGE INSTALLATION (ISFSI)
TEXT 3.10.4 2 04/17/2008
Title:
MISCELLANEOUS LEADING EDGE FLOW METER (LEFM)
.,. Page 6 of -.16 Repoiýt Date: '04/11/12
SSES MANUTAL Manual Name: TRM1 Manual
Title:
TECHNICAL REQUIREMENTS MANUAL UNIT 1 TEXT 3.11.1.1 1 04/26/2006
Title:
RADIOACTIVE EFFLUENTS LIQUID EFFLUENTS CONCENTRATION 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 1 12/14/2004 TEXT 3.11.1.4
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 3.11.3 104/26/2006
Title:
RADIOACTIVE EFFLUENTS TOTAL DOSE Report Date: 04/11/12 Page2 Page I of of 16.
16 Report Date: 04/11/12
.SSES MANUAL Manual Name: TRMI Manual
Title:
TECHNICAL REQUIREMENTS MANUAL UNIT 1 TEXT 3.11.4.1 4 08/08/2006
Title:
RADIOACTIVE EFFLUENTS MONITORING PROGRAM 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 L IGHT LOADS REQUIREMENT.
TEXT 4.1 0 08/31/1998
Title:
ADMINISTRATIVE CONTROLS ORGANIZATION TEXT 4.2 0 08/31/1998
Title:
ADMINISTRATIVE CONTROLS REPORTABLE EVENT ACTION TEXT 4.3 0 08/31/1998
Title:
ADMINISTRATIVE CONTROLS SAFETY LIMIT VIOLATION TEXT 4.4 1 12/18/2008
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 Report Date: 04/11/12 Page88 Page of 16
.16 Report Date':'04/11/12
SSES MANTJAL Manual Name: TRM1 Manual
Title:
TECHNICAL REQUIREMENTS MANUAL UNIT 1 TEXT 4.7 0 08/31/1998
Title:
ADMINISTRATIVE CONTROLS TRAINING 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 RODBLOCK 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 RADIATIbN'MONITORING INSTRUMENTATION TEXT B3.3.2 2 03/31/2011
Title:
INSTRUMENTATION BASES SEISMIC MONITORING INSTRUMENTATION TEXT B3.3.3 3 12/18/2008
Title:
INSTRUMENTATION BASES METEOROLOGICAL MONITORING INSTRUMENTATION TEXT B3.3.4 4 07/09/2010
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 Page 9 of 16 Report Date: 04/11/12
SSE$ MANUJAL Manual Name: TRM1 Aý
. I.' .1 Manual
Title:
TECHNICAL REQUIREMENTS MANUAL UNIT 1 0 TEXT B3.3.6 4 01/13/2011
Title:
INSTRUMENTATION BASES TRM ISOLATION ACTUATION INSTRUMENTATION 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 3 08/09/2010
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 Report Date: 04/11/12 10 Page 10 of. 2i of a kep6rt*bat6':' W11/12
SSES MANUAL Manual Name: TRM1 Manual
Title:
TECHNICAL REQUIREMENTS MANUAL UNIT 1 TEXT B3.4.6 1. 06/15/2010
Title:
REACTOR RECIRCULATION SINGLE LOOP OPERATION SLO FLOW RATE RESTRICTION TEXT B3.5.1 0 11/19/2002
Title:
ECCS AND RCIC BASES ADS MANUAL INHIBIT 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 0.4/17/2008
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 3 06/15/2010
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 Page 11 of 16 Report Date: 04/11/12
SSES MANUAL Manual Name: TRMI Manual
Title:
TECHNICAL REQUIREMENTS MANUAL UNIT 1 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 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 2' 11/30/2011
Title:
PLANT SYSTEMS BASES FIRE DETECTION INSTRUMENTATION TEXT B3.7.4 0 11/19/2002
Title:
PLANT SYSTEMS BASES 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 Report Date: 04/11/12 12 Page 12 of of 16 16 Report Date: 04/11/12
SSES MANUAL Manual Name: TRMI1 Manual
Title:
TECHNICAL REQUIREMENTS MANUAL UNIT 1 TEXT B3.7.8 3 06/21/2007
Title:
PLANT SYSTEMS BASES SNUBBERS TEXT B3.7.9 2 12/08/2011
Title:
PLANT SYSTEMS BASES CONTROL STRUCTURE HVAC TEXT B3.7.10 1 12/14/2004
Title:
PLANT SYSTEMS BASES SPENT FUEL STORAGE POOLS TEXT B3.7.11 1 04/14/2010
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) THERMAL 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 2 12/08/2011
Title:
ELECTRICAL POWER BASES EMERGENCY SWITCHGEAR ROOM COOLING TEXT B3.8.7 1 06/15/2009 7
Title:
BATTERY MAINTENANCE AND MONITORING PROGRAM Page 1-3 of 16 Report Date:.04/11/12
SSES MANUAL Manual Name: TRMI Manual
Title:
TECHNICAL REQUIREMENTS MANUAL UNIT 1 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 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
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 Rpor Dae: 4/1/1 Pag 14 of 6 Paýre 14 of .16 Report Date: 04/11/12
SSEq MANUAL Manual Name: TRM1 Manual
Title:
TECHNICAL REQUIREMENTS MANUAL UNIT 1 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 -7 NOBLE GASES 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 3 07/09/2010
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 1 12/03/2010
Title:
LOADS CONTROL PROGRAM BASES HEAVY LOADS REQUIREMENTS Report Date: 04/11/12 Pagei5 Page 15 'of of 16 16 Report Date: 04/11/12
SSES MANUAL Manual Namen: TRMI Manual
Title:
TECHNICAL REQUIREMENTS MANUAL UNIT 1 TEXT B3.12.3 0 11/19/2002
Title:
LOADS CONTROL PROGRAM BASES LIGHT LOADS REQUIREMENTS Report Date: 04/11/12 Page 16 Page 16 of of ii16 Report Date: 04/11/12
SUSQUEHANNA STEAM ELECTRIC STATION PPL Rev. 71 LIST OF EFFECTIVE SECTIONS (TECHNICAL REQUIREMENTS MANUAL)
Section Title Effective Date TOC TABLE OF CONTENTS 11/30/2011 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 Pages TRM / 2.0-8 and TRM / 2.0-9 01/07/2011 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 04/09/2012 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 03/10/2011 Page TRM / 3.3-7 10/31/2007 Page 3.3-8 08/31/1998 Pages TRM / 3.3-9 and TRM / 3.3-9a 06/30/2010 SUSQUEHANNA - UNIT 1 TRM / LOES-1 EFFECTIVE DATE 04/09/2012
SUSQUEHANNA STEAM ELECTRIC STATION PPL Rev. 71 LIST OF EFFECTIVE SECTIONS (TECHNICAL REQUIREMENTS MANUAL)
Section Title Effective Date Page TRM / 3.3-10 10/31/2007 Pages TRM / 3.3-11 and TRM / 3.3-11 a 06/30/2010 Page TRM / 3.3-12 03/30/2001 Page TRM / 3.3-13 01/07/2011 Page TRM / 3.3-14 12/14/1998 Pages TRM / 3.3-15 and TRM / 3.3-16 01/07/2011 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 Pages TRM / 3.4-14 and TRM / 3.4-15 06/10/2010 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 Page 3.6-1 08/31/1998 Pages TRM / 3.6-2 and TRM / 3.6-2a 08/11/2011 Page 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 TRM I LOES-2 EFFECTIVE DATE 04/09/2012 SUSQUEHANNA SUSQUEHANNA - UNIT
- UNIT I1 TRM / LOES-2 EFFECTIVE DATE 04/09/2012
SUSQUEHANNA STEAM ELECTRIC STATION PPL Rev. 71 LIST OF EFFECTIVESECTIONS (TECHNICAL REQUIREMENTS MANUAL)
Section Title Effective Date 3.7 PLANT SYSTEMS Pages 3.7-1 through 3.7-3 08/31/1998 Page TRM / 3.7-4 03/31/2006 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 11/24/2011 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 09/16/2010 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 06/07/2007 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 SUSQEHANA - NITII LES-3 TR EFFCTIV DAT 040921 SUSQUEHANNA - UNIT 1 TRM / LOES-3 EFFECTIVE DATE 04/09/2012
SUSQUEHANNA STEAM ELECTRIC STATION PPL Rev. 71 LIST OF EFFECTIVESECTIONS (TECHNICAL REQUIREMENTS MANUAL)
Section Title Effective Date 3.8 ELECTRICAL POWER Page TRM / 3.8-1 04/02/2002 Page TRM / 3.8-2 01/28/2005 Pages TRM / 3.8-3 and TRM /3.8-4 03/25/2010 Pages TRM / 3.8-5 and TRM / 3.8-6 04/02/2002 Page TRM / 3.8-7 10/31/2007 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 Page TRM / 3.8-13 03/25/2010 Page TRM / 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 TRM / 3.8-24 and TRM / 3.8-25 11/30/2011 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 06/10/2010 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 TRM / LOES-4 EFFECTIVE DATE 04/09/2012 SUSQUEHANNA - UNIT SUSQUEHANNA - UNIT I1 TRM / LOES-4 EFFECTIVE DATE 04/0912012
SUSQUEHANNA STEAM ELECTRIC STATION PPL Rev. 71 LIST OF EFFECTIVE SECTIONS (TECHNICAL REQUIREMENTS MANUAL)
Section Title Effective Date 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 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 TRM I LOES-5 EFFECTIVE DATE 04/09/2012 SUSQUEHANNA SUSQUEHANNA - UNIT
- UNIT 11 TRM / LOES-5 EFFECTIVE DATE 04109/2012
SUSQUEHANNA STEAM ELECTRIC STATION PPL Rev. 71 LIST OF EFFECTIVE SECTIONS (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 Page TRM / B 3.3-2 03/10/2011 Page 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 Page TRM / B 3.3-4 06/30/2010 Page TRM / B 3.3-5 05/30/2006 Page TRM / B 3.3-6 06/30/2010 Page TRM / B 3.3-7 10/30/2007 Page TRM / B. 3.3-8 .06/30/2010 Page TRM / B 3.3-9 10/31/2007 Pages TRM / B 3.3-10 through TRM / B 3.3-13 01/07/2011 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 TRM / LOES-6 EFFECTIVE DATE 04/09/2012 SUSQUEHANNA - UNIT SUSQUEHANNA -
UNIT 1 1 TRM / LOES-6 EFFECTIVE DATE 04/09/2012
SUSQUEHANNA STEAM ELECTRIC STATION PPL Rev. 71 LIST OF EFFECTIVESECTIONS (TECHNICAL REQUIREMENTS MANUAL)
Section Title Effective Date Pages TRM / B 3.3-17e and TRM / B 3.3-17f 03/22/2006 Pages TRM / B 3.3-18 and TRM / B 3.3-19 08/03/2010 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 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 Pages TRM / B 3.4-7 and TRM / B 3.4-8 06/10/2010 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 Page TRM / B 3.7-3 06/10/2010 Page 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 / B 3.7-10 08/02/1999 Page TRM / B 3.7-10a 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 TRM /.B 3.7-14 08/02/1999 Page TRM / B 3.7-14a 08/02/1999 TRM /LOES-7 EFFECTIVE DATE 04/09/2012 SUSQUEHANNA- UNIT 1 SUSQUEHANNA - UNIT 1' TRM / LOES-7 EFFECTIVE DATE 04/09/2012
SUSQUEHANNA STEAM ELECTRIC STATION PPL Rev. 71 LIST OF EFFECTIVE SECTIONS (TECHNICAL REQUIREMENTS MANUAL)
Section Title Effective Date Page TRM / B 3.7-14b 11/24/2011 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 06/0/2008 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 11/30/2011 Page TRM / B 3.7-32 03/09/2001 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 3.7-39 04/01/2009 Page TRM / B 3.7-40 04/08/2010 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 11/30/2011 Pages TRM / B 3.8-17a and TRM / B 3.8-17b 11/30/2011 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 TRM / LOES-8 EFFECTIVE DATE 04/09/2012 SUSQUEHANNA - UNIT SUSQUEHANNA -
UNIT 11 TRM / LOES-8 EFFECTIVE DATE 04/09/2012
SUSQUEHANNA STEAM ELECTRIC STATION PPL Rev. 71 LIST OF EFFECTIVE SECTIONS (TECHNICAL REQUIREMENTS MANUAL)
Section Title Effective Date 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 3.11-11a 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 11/14/2006 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 06/30/2010 Pages B 3.11-31 and B 3.11-32 08/30/1998 Page TRM / B 3.11-33 06/30/2010 Pages TRM / B 3.11-34 and TRM / B 3.11-35 08/30/1998 Page TRM / B 3.11-36 02/12/1999 B.3.12 LOADS CONTROL PROGRAM BASES Page TRM / B 3.12-1 09/19/2007 Page TRM / B 3.12-2 11/29/2010 Page TRM / B 3.12-3 02/05/1999 TRM1 text LOES 04/09/2012 SUSdUEHANNA - UNIT 1 TRM / LOES-9 EFFECTIVE DATE 04/09/2012
Core Operating Limits Report (COLR)
PPL Rev. 13 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. 13 PL-NF-12-001 Rev. 0 Page 1 of 53 Susquehanna SES Unit I Cycle 18 CORE OPERATING LIMITS REPORT Nuclear Fuels Engineering April 2012 P
SUSQUEHANNA UNIT I TRM/3.2- 2 EFFECTIVE DATE 4/09/2012
PPL Rev. 13 PL-NF-12-001 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 I Cycle 18 operation.
FORM NFP-QA-008-2, Rev. 1 SUSQUEHANNA UNIT 1 TRM/3.2-3 EFFECTIVE DATE 4/09/2012
PPL Rev. 13 PL-NF-12-001 Rev. 0 Page 3 of 53 SUSQUEHANNA STEAM ELECTRIC STATION Unit I Cycle 18 CORE OPERATING LIMITS REPORT Table of Contents
(
1.0 INTRO DUCTIO N .................................................................................................... 4 2.0 D EFINITIONS ....................................................................................................... 5 3.0 SHUTDOWN MARGIN,.......................................................................................... 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 REQ UIREM ENTS ................................................................................................... 32 8.0 RECIRCULATION LOOPS - SINGLE LOOP bPERATION .................................... 34 9.0 PoWER I FLOW MAP ............................................................................................ 49 10.0 OPRM SETPOINTS ................................................................................................. 51
11.0 REFERENCES
........................................................................................................ 52 SUSQUEHANNA UNIT 1 TRM/3.2-4 EFFECTIVE DATE 4/09/2012
PPL Rev. 13 PL-NF-12-001 Rev. 0 Page 4 of 53
1.0 INTRODUCTION
This CORE OPERATING LIMITS REPORT for Susquehanna Unit 1 Cycle 18 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 I TRM/3.2-5 EFFECTIVE DATE 4/09/2012
PPL Rev. 13 PL-NF-12-001 Rev. 0 Page 5 of 53 2.0 DEFINITIONS Terms used in this COLR but not defined in Section 1.0 of the TechnicalSpecifications 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 LHGRFAC, is a multiplier 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 RATED THERMAL 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 4/09/2012
PPL Rev. 13 PL-NF-12-001 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 4/09/2012
PPL Rev. 13 PL-NF-12-001 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 ATRIUMTM-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.
SU8QUEHANNA UNIT 1 TIM/3.2-8 EFFECTIVE DATE 4/09/2012
.c, 1SSES 16.0 UNIT 1 CYCLE 18
..................................................................... E E E C 1: :: ......
- ~L2.sCK.~~ [~~~2.5i.1 : :: :: :USED INDETERMINING MAPRAT 8.0* - .. .. l . = = . = I, ...., . . . . .. ... ......1
.-. . ...... . . . . ... . .. . S DI E E M NN A R TI -0 S 10. ......... ........................................
.= .l . . l * .. l [ 6' 7 0 0 * , , (D
-H..-... . . .
.. 0.......................................................................................................' I caa 4- . . . . . . . . . . . .
r*
- - 1 . ........................................................................................................... r-6.0) rn*
.0-------- C)
-~ -6700691
"~~~0 -. , ;"- 60 0 10000 20000 30000 40000 50000 60000 70000 N)
T X -'
Average Planar Exposure (MWD!MTU) (C) (Dr (D Z co0-n AVERAGE PLANAR LINEAR HEAT GENERATION RATE LIMIT VERSUS 0 AVERAGE PLANAR EXPOSURE TWO LOOP OPERATION -hK ATRIUMM 0 FUEL 0 FIGURE 4.2-1
PPL Rev. 13 PL-NF-12-001 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 (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 I EOC-RPT I 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 1 TRM/3.2-10 EFFECTIVE DATE 4/09/2012
PPL Rev. 13 PL-NF-1 2-001 Rev. 0 Page 10 of 53 5.3 Averagqe 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.
SUSQUEHANNA UNIT I TRMI3.2-11 EFFECTIVE DATE 4/09/2012
PPL Rev. 13 PL-NF-12-001 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 4/09/2012
SSES UNIT I CYCLE 18 2.2 (A'-
D> 2.1 2.0 1.9
_1.8 (A
N) 0)
I. 0.
(A (D 0 5A 1.5 m
1.4 m
m 1.3 C-)
1.2 30 40 50 60 70 80 90 100 110 Total Core Flow (MLB!HR) (D
- 0 N)
C)
,0 MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW 0
-4,o MAIN TURBINE BYPASS I EOC-RPT / BACKUP PRESSURE REGULATOR OPERABLE 01 C)
TWO LOOP OPERATION (BOC TO EOC) (A FIGURE 5.2-1
9 SSES UNIT 1 CYCLE 18 c-, 3.6 m
-u CD m
C)
Q0 N) e 20 30 40 50 60 70 80 90 100 Core Power (% RATED) (D .<
X MCPR OPERATING LIMIT VERSUS CORE POWER (0 MAIN TURBINE BYPASS / EOC-RPT / BACKUP PRESSURE REGULATOR OPERABLE TWO LOOP OPERATION (BOC TO EOC)
FIGURE 5.2-2
PPL. Rev. 13 PL-NF-1 2-001 Rev. 0 Page 14 of 53 Main Turbine Bypass Inoperable SUSQUEHANNA UNIT-1 TRM/3.2-15. EFFECTIVE DATE 4/09/2012
VI) SSES UNIT 1 CYCLE 18 cf) 2.2 I' I I I M LEGEND 2.1 CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME C= CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME 2.0 SAFETY ANALYSES ASSUME THAT TWO OR MORE BYPASS VALVES ARE INOPERABLE PER SR 3.7.6.1 OR 3.7.6.2 1.9 USED IN DETERMINING MFLCPR N) ~1.7 CL CD 0.
1l.6 1.5 I
m m
1.4 (0 M
1.3
REFERENCE:
T.S. 3.7.6 and 3.2.2 -
C~)
1.2 30 40 50 60 70 80 90 100 110 Total Core.Flow (MLB/HR) -o (D rI-Co CD
- z 0-I MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW (TI MAIN TURBINE BYPASS INOPERABLE 0
-4, TWO LOOP OPERATION (BOC TO EOC) (yr FIGURE 5.2-3
SSES UNIT I CYCLE 18 V) r-4
-4l P1i Nl E.
Nl 20 30 40 50 60 70 80 90 100 I-Core Power (% RATED) (D r-CD 0 N)
MCPR OPERATING LIMIT VERSUS CORE POWER 01 0)
MAIN TURBINE BYPASS INOPERABLE 01 TWO LOOP OPERATION (BOC to EOC)
FIGURE 5.2-4.
PPL Rev. 13 PL-NF-12-001 Rev. 0 Page 17 of 53 EOC-RPT Inoperable SUSQUEHANNA UNIT 1 TRM/3.2-18 EFFECTIVE DATE 4109/2012
(A (A
SSES UNIT 1 CYCLE 18
. 2.2 I I ... . . I .. ..... . . I .. .. . . . .
m LEGEND 2.1 CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME
-H 2.0 CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME 1.9 SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERAB3LE PER SR 3.7.6.1 AND 3.7.6.2 1.8 USED.IN DETERMINING MFLCPR WH
-IJ
- 1.7 (D
0 C-) 1.6 1.5 m
m 1.4 m
REFERENCE:
T.S. 3.3.4.1 and 3.2.2 1.3 N)
C= 1.2 30 40 50 60 70 80 s0 100 110
-U ;Q "v Total Core Flow (MLB/HR) (D r (p
MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW 0
EOC-RPT INOPERABLE -h TWO LOOP OPERATION (BOC TO EOC) (yI C!)
FIGURE 5.2-5
-4
-u CD m
C->
7 m
C=>)
t-4 20 30 40 50 60 70 80 90 100 N.)
Core Power (% RATED) F13 (D<
z MCPR OPERATING LIMIT VERSUS CORE POWER 01 EOC-RPT INOPERABLE 0
,0 TWO LOOP OPERATION (BOC to EOC)
FIGURE 5.2-6
PPL Rev. 13 PL-NF-12-001 Rev. 0 Page 20 of 53 Backup Pressure Regulator Inoperable SUSQUEHANNA UNIT I TRM/3.2-21 EFFECTIVE DATE 4/09/2012
cz SSES UNIT 1 CYCLE 18 C-,)
2.2 1 I .. .. .... . I I ...
P1 LEGEND 2.1 CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME
-H 2.0 CURVE B: REALISTIC 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
_ _ __ __ _ _ _II _ f
-J C.) USED IN DETERMINING MFLCPR
- 1.7 (D
0
.51.6 1.5 P1 1.4
-ni 1.3
REFERENCE:
T.S. 3.7.8 and 3.2.2 108,1.22 1.2 30 40 50 60 70 80 90 100 110 0
Total Core Flow (MLB/HR) (D r-CD
< TI (0 N.
MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW BACKUP PRESSURE REGULATOR INOPERABLE 0
TWO LOOP OPERATION (BOC TO EOC) 0 FIGURE 5.2-7
V) SSES UNIT 1 CYCLE 18 3.6 m
E I--
0..
0a- CJ)
-TI n, m
1.2 20 30 40 50 60 70 80 90 100 Core Power (% RATED) (<
,'a~ -n MCPR OPERATING LIMIT VERSUS CORE POWER BACKUP PRESSURE REGULATOR INOPERABLE 0 Fo 0,i 0 TWO LOOP OPERATION (BOC to EOC) W#
FIGURE 5.2-8
PPL Rev. 13 PL-NF-12-001 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 SUSQUEHANNA UNIT 1 TRM/3.2-24 EFFECTIVE DATE 4/09/2012
PPL Rev. 13 PL-NF-12-001 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 ATRIUM TM-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 1 TRM/3.2-25 EFFECTIVE DATE 4/09/2012
~16.0 1SSES UNIT 1 CYCLE 18 1..............
aESED IN R IN 14.0- [.....8 1R .. RS 3 t.3-
. . . ....................... I...............-------------
........................ .R.EF.E.EN.C. ..... . .............. . . . . . USED IN-DETERMINING FDLRX' - -
N) 14.0 . ...
"tO"t--:---:--:"-,,,,,,,,.. .............;" *"";" . . ;*'"' ........... ",.,........................
12.... j "
-o 80 10.0 ....................................................................... ..
rT11 6.0 rni 4 4.0-0 10000 20000 30000 40000 50000 60000 70000 80000 Pellet Exposure (MWDIMTU) 00-H (13 r') Z LINEAR HEAT GENERATION RATE LIMIT VERSUS PELLET EXPOSURE (n 1 ATRUM1 FUEL %
FIGURE 6.2-1 -
PPL Rev. 13 PL-NF-12-001 Rev. 0 Page 26 of 53 Main Turbine Bypass Operable SUSQUEHANNA UNIT 1 TRM/3.2-27 EFFECTIVE DATE 4/09/2012
SSES UNIT 1 CYCLE 18 1.10
- ........... .. . .... . .. .... .. . ...... .. . ..... *...... ..* . .... .... =., . . . .. .. . .
.J.. - - .- - . . . . . . .
> 100 ..... ---- ------- A-------------- - - - - - - - - - - - -
. 4 - - - - -
0.0 - - - ------------------------ ---- -- - - - - - --. . . . . . .. . ... . .
0 . ...... ..*......* . .... .. . . ............
.60 .. . . I... ...... .. . .. ... . . ... ..... .. . .
- --- ~~~~~-- I------
0.90 ----------------- ------- ------------------- ................. . ..........
0.40 .. . . == === ====
.. . . . .. . .... ==== . ==== . .. === ====. ... ................ ......-- --...... ......
"5 0.0 . ..... ....... T ...... . ........
CA)
I ................... , .. 6 Z 0.3.0 6.2-2M[IN USE~~~IGR D .
ATRI.... F E . .. "Ln MAINATURFIGE 6YPANA-S2ERABLE 0
4D1.10.
10 SSES UNIT I CYCLE 18 1.00 CURVEA: BASE CURVE ......
1 CURVE B: CORE POWER 26% AND CORE FLOW50 ...... ..... .... 0
. .. ,.... A- .. . .... .
ro" .80 . ..... ................ .2-u
.. 4.....I I . d.... ... , . .. -...... .- , . -
N 0.7 -..............
0.
,. 0.60 ... . "....
- t. 0.0
REFERENCE:
T.S. 3.2.3 and 3.7.6 USED IN DETERMINING FDLRX
-r 0.50 ....... ...................... .
m m 04 -,, ............ :........... - - - - - ..--......
23,0.l
-.................................... . *,t*..................
0.30 20 30 40 50 60 70 80 90 100 N) Core Power (% RATED) 0 Co o -,
POWER DEPENDENT LHGR LIMIT MULTIPLIER MAIN TURBINE BYPASS OPERABLE 2, ATRIUMTM-10 FUEL FIGURE 6.2-3
PPL Rev. 13 PL-NF-12-001 Rev. 0 Page 29 of 53 Main Turbine Bypass Inoperable SUSQUEHANNA UNIT I TRM/3.2-30 EFFECTIVE DATE 4/09/2012
SSES UNIT 1 CYCLE 18
.... mIIII 1.10 m ... . ... .........
. ...... . . . .... ........ .* .............. L.........
>:" 1.00 0.90 ..... -. ....- -----
0.80
- .0.70 ........ SAFETYANALYSES ASSUME THATTWO OR MORE BYPASS -o S - . -. ... .VALVES ARE INOPERABLE PER SR 3.7.6.1 OR 3.7.6.2 to CL o0.60 30o,0o601 .....------ ...........
REFERENCE:
T.S. 3.2.3 and 3.7.6
.............. I-m 0.50 a - S~DINDTERMINING FDLRX
"-'r n
m CD rm 0.40 ---------------------------------------------------- ------ wA
-* 0.30
-a-30 40 50 60 70 80 90 100 1 N)
Total Core Flow (MLBIHR)
N, 10 041 FLOW DEPENDENT LHGR LIMIT MULTIPLIER 0 CV MAIN TURBINE BYPASS INOPERABLE ATRIUMTM-10 FUEL FIGURE 6.2-4
.CD 1SSES 1-10 UNIT 1 CYCLE 18 C= r-* ~LEGEND. , ,
t)"
1 CURVE A: BASE CURVE -. 7j........
- CURVE B: CORE POWER *< 26% AND CORE FLOW *50 MLBM/HR ------ ------ "... "".".".. ......
0O.80 4
26 0A..:...I... .. ...... ,..
.2.
-* SAFETY ANALYSES ASSUME THAT TWO OR MORE BYPASS VALVES 0.60 - --- . . ARE INOPERABLE PER SR 3.7.6.1 OR 3.7.6.2 i 0.0 0.4-----------------------
REFERENCE:
.......--------------------- T.S.
and 3.7.6 3.2.3----------- "
o 0 . .
... ... .. . .......... .L.USED IN DETERMINING -F.. -.
P I 0.50---------.
,0 44 ...... . .......
0.5 B;
- 20. - 4560-
... . . .. . 1 "r* m ~4 00 23,039..'N . . . . .. ... ....... " .. . . . . . . .. . .
USED~ ~ ~
INDTRINNZDR C
-- *- . ... *u,*, -- - - -- 0.'.:... .. . .. . . ... ...........
110 20 30 40 50 60 70 so 90 100 r* 0.303 ~~~~Core Power (%1o* RATED)-o "
POWER DEPENDENT LHGR LIMIT MULTIPLIER D -n MAIN TURBINE BYPASS INOPERABLE ATRIUMTM-10 FUEL 0 FIGURE 6.2-5
PPL Rev. 13 PL-NF-12-001 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, d) Low Power Range - Upscale, e) Intermediate Power Range - Upscale, and f) 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.
SUSQUEHANNA UNIT 1 TRM/3.2-33 EFFECTIVE DATE 4/09/2012
PPL Rev. 13 PL-NF-12-001 Rev. 0 Page 33 of 53 Table 7.2-1 RBM Setpoints
.0 Function Allowable Nominal Trip Function Value(1 ) 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 (
(% of Rated)
> 28 and < 90 < 1.76
ýt 90 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.
SUSQUEHANNA UNIT I TRM/3.2-34 EFFECTIVE DATE 4/09/2012
PPL Rev. 13 PL-NF-12-001 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 0
The APLHGR limit for ATRIUMTM-10 fuel shall be equal to 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 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 8.2-2: Flow-Dependent MCPR value determined from BOC to EOC Figure 8.2-3: Power-Dependent MCPR value determined from BOC 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 BOC to EOC Figure 8.2-7; Power-Dependent MCPR value determined from BOC to EOC d) Backup Pressure Regulator Inoperable Figure 8.2-8: Flow-Dependent MCPR value determined from BOC to EOC Figure 8.2-9: Power-Dependent MCPR value determined from BOC to EOC SUSQUEHANNA UNIT I TRM/3.2-35 EFFECTIVE DATE 4/09/2012
PPL Rev. 13 PL-NF-12-001 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 I TP, /3.2-36 EFFECTIVE DATE 4/09/2012
c/)
Cm SSES UNIT I CYCLE 18 16.0 . ... .
. .......... ..... .. ...........I . .. ..........
l . i * = . n l . D
- p . . . . . . . . . . . . .. . .
REFERENCE T.S. 3.4.1 and 3.2.1 14.0 USED INDETERMINING MAPRAT 12.0
-U
-D N) 102i.0 I-CD
- ~~ . . . ~
. - - . P 4, C.)
~8.0 CD
-n m 6.0 4.0 0.0 10000.0 20000.0 30000.0 40000.0 50000.0 60000.0 70000.0 N) Average Planar Exposure (MWDIMTU)
AVERAGE PLANAR LINEAR HEAT GENERATION RATE LIMIT VERSUS 0) -
AVERAGE PLANAR EXPOSURE SINGLE LOOP OPERATION 0
ATRIUMTM-10 FUEL C)
FIGURE 8.2-1
PPL Rev. 13 PL-NF-12-001 Rev. 0 Page 37 of 53 Main Turbine Bypass / EOC-RPT I Backup Pressure Regulator Operable SUSQUEHANNA UNIT 1 TRIbM/3.2-38 EFFECTIVE DATE 4/09/2012
(A SSES UNIT 1 CYCLE 18 4.0 (Al I I 1 1 LEGEND 3.8 CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM 3.6 INSERTION TIME CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME 3.4 3.2 SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES 3.0 ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 "2.8 -o 0 2.6 USED IN DETERMINING MFLCPR (I-0L.
2.4 2.2 2,0 mr m 1.8 CD 1.6
REFERENCE:
T.S. 3.4.1 and 3.2.2 C) 1.4 N) 30 40 50 60 70 80 90 100 110 Total Core Flow (MLBIHR) (D 0 -Ti MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW 00 MAIN TURBINE BYPASS I EOC-RPT I BACKUP PRESSURE REGULATOR OPERABLE co N)
W U, 0 SINGLE LOOP OPERATION (BOC to EOC) 0 FIGURE 8.2-2
C,)
C,)
SSES UNIT 1 CYCLE 18 4.6 I I
. -.. I I I m LEGEND 4.4 CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM 4.2 INSERTION TIME 4.0 23, 3.84 CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME
- -26, 3.62 CURVE C: CORE POWER : 26% AND CORE FLOW ; 50 MLBM/HR 3.2 26, 35 E 3.4 SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 3.2 I-N)
USED IN DETERMINING MFLCPR a .O CD 0V IX 2.8 <,
,,. ,,,,44.
,. E.......
i 2.6 2.4 I-An -- .. ............
mr 2.2 ,4.
-A 4. .1- 4. I Ti -B-mr 4. ~~1 J~i.93 2.0 I. F - .tI 1~ t __ _ __ _ _ +/- ___
1.8 1.6 R-*iEFERENCE: T.S. 3.4.1 and 3.2.2[-" _ _____t .....
1.4 20 30 40 50 60 70 80 90 100 Core Power (% RATED) r-(0 CD (D
MCPR OPERATING LIMIT VERSUS CORE POWER z.
MAIN TURBINE BYPASS I EOC-RPT i BACKUP PRESSURE REGULATOR OPERABLE (0 -I SINGLE LOOP OPERATION (BOC to EOC)
FIGURE 8.2-3
PPL Rev. 13 PL-NF-1 2-001 Rev. 0 Page 40 of 53 Main Turbine Bypass Inoperable SUSQUEHANNA UNIT 1 TRMI3.2-41 EFFECTIVE DATE 4/09/2012
9 SSES UNIT 1 CYCLE 18 4.6 II I I . .. .
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 SAFETY ANALYSES ASSUME THAT TWO OR MORE BYPASS 3.4 VALVES ARE INOPERABLE PER SR 3.7.6.1 OR 3.7.6.2 o 3;2
-0
" 3.0 USED IN DETERMINING MFLCPR -o 0.
0 CD W 2.8 C.<
2.6 2.4 m 2.2 R
m B 2.0 m 1.8
.]FERENCE.: T.S. 3.4.1, 3.7.6, and 3.2.2 * "*- .- [0,*6*
m 1.6 1.4 C= 30 40 50 60 70 80 90 100 110
-a ý0(D r-Total Core Flow (MLB/HR)
SD "1-I MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW MAIN TURBINE BYPASS INOPERABLE Cb.. 0o 0
SINGLE LOOP OPERATION (BOC to EOC)
FIGURE 8.2-4
SSES UNIT I CYCLE 18 4.6 I I I. . I LEGEND 4.4 CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM 4.2 INSERTION TIME 4.0 CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME 26, 3.88 V)
CURVE C: CORE POWER
- 26% AND CORE FLOW <50 MLBMJHR
- C\
- m II I
_AI
.11 I-.---..------------- 4 L- -
26, 3.5-- I E. 3.4 I-~q 1 1
-3 SAFETY ANALYSES ASSUME THAT TWO OR MORE BYPASS
- 3.2 rzi I 21 VALVES ARE INOPERABLE PER SR 3.7.6.1 OR 3.7.6.2
.3.0 0 USED IN DETERMINING MFLCPR
- a. 2.8 c,)
2.6 2.4 40,21 1.. ..... .
2.2 4. 4 In I nt II 4...4 .....-
m F1OO, 2.071
- 4. 4 .4 =. m -4=.
2.0 I I .L ____________ 4 k 1.8 4 4 4 4 4 4 &
4 4 4 4 4 4 CD, 1.6 ____________ I _____________ t ____________ +/-~. .t t t t
IREFERENCE:
T.S. 3.4.1, 3.7.6, and 3.2.2 4 4 4 4 1.4 20 30 40 50 60 70 80 90 100 Core Power (% RATED) -0 (D F, Q~
MCPR OPERATING LIMIT VERSUS CORE POWER R0 MAIN TURBINE BYPASS INOPERABLE cn SINGLE LOOP OPERATION (BOC to EOC) co 0 FIGURE 8.2-5
PPL Rev. 13 PL-NF-12-001 Rev. 0 Page 43 of 53 EOC-RPT Inoperable SUSQUEHANNA UNIT I TRM/3.2-44 EFFECTIVE DATE 4/09/2012
0 V) SSES UNIT 1 CYCLE 18 4.6 LEGEND C= 4.4 4 4.2 CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME 4.0 Ij CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME 3.8 3.6 SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES o3.2 ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2
'4:,
USED IN DETERMINING MFLCPR
.0 CA 0 (D~
~2.6 2.4 P1 2.2
-n
-nl 30A1.92j ................ ____,,_
C-,) 2.0 P1 1.8 1.6 {
REFERENCE:
T.S. 3.4.1, 3.3.41, and 3.2.2 1 1.....
1.4 30 40 50 60 70 80 90 100 110
-u Total Core Flow (MLB/HR) CD I
- 0) <I (0
MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW 'I, EOC-RPT INOPERABLE 0o SINGLE LOOP OPERATION (BOC to EOC)
FIGURE 8.2-6
SSES UNIT 1 CYCLE 18 C=
CAi t
-U I-.
CD r-n m
m cn) 20 30 40 50 60 70 80 90 100 Core Power (% RATED) -o N) .D CD MCPR OPERATING LIMIT VERSUS CORE POWER C -n EOC-RPT INOPERABLE SINGLE LOOP OPERATION (BOC to EOC) o0 c.n FIGURE 8.2-7
PPL Rev. 13 PL-NF-12-001 Rev. 0 Page 46 of 53 C,
Backup Pressure Regulator Inoperable SUSQUEHANNA UNIT I TRM/3.2-47 EFFECTIVE DATE 4/09/2012
C,-)
SSES UNIT I CYCLE 18 4.6 m I 4.4 4~ ~I-4LEA MN 4.2 I I I I 11 i A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME
- 1
-H 4.0 B: REALISTIC AVERAGE SCRAM INSERTION TIME 3.8 4 4 3.6 i 4 _ _ _ __ _ _1 SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2
-H D i M.,,
o3.2 4 I4I I U E IIN DETERMINING USED MFLCPR C-.)
~;3.0 -D
- 0. CD C.)
- 2.6 2.4 m 2.2
-n
-n m 30,1.92J C~) 2.0 1 4 I.- .4. .1. 1 1
-H m 1.8 A- B c:j II_ -4 4 4
-H 1.6 3.2.2 110, 491 3.7.8, and -.4. .4. 4 REFERENC E: T.S. 3.4.1, 1.4 .1. .L _________ I I 30 40. 50 60 70 80 90 100 110 Total Core Flow (MLB[HR) -D CDCD N) 0 MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW (0 BACKUP PRESSURE REGULATOR INOPERABLE SINGLE LOOP OPERATION (BOC to EOC) 0 Con 0 FIGURE 8.2-8
SSES UNIT I CYCLE 18 4.4 4.2 4.0 3.4 3.2 I-
. 3.0 CD
-J 2.8 C~)
~2.6 0 2.4 0 2.2 m
2.0 1.8 CD) 1.6 1.4 20 30 40 50 60 70 80 90 100 N) Core Power (% RATED)
(D N)
MCPR OPERATING LIMIT VERSUS CORE POWER 12.
BACKUP PRESSURE REGULATOR INOPERABLE 00 0-f 0 SINGLE LOOP OPERATION (BOC to EOC)
FIGURE 8.2-9
PPL Rev. 13 PL-NF-12-001 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 I core flow outside of Stability Regions I and IHof the Power / Flow map, Figure 9.1.
If the OPRM Instrumentation is OPERABLE per TS 3.3.1.1, Region I of the Power I 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 I 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 I TRJM/3.2-50 EFFECTIVE DATE 4/09/2012
PPL Rev. 13 PL-NF-12-001 Rev. 0 Page 50 of 53 120 - 120
Purpose:
"__________________" __" - UNIT 1 itial.....Date:.. I: tilT7-T:~- ',t.LIFT U POWER Il I FLOW l MAP
+/-_1 ---
Trf APRM Scram IrnT 110 _ I , 1 Trip Setpolnt 110 SALIY REGON ....... .. -M Rod*B-"* ok IFOPRMINOPERABLEIMMEDIATE ! I _L1 I Trip Setpoint / /
SCRAMlAW ON478-O.2 I r ". ,
100 IFOPRMOPERABLE IMMEDIATE ' ELILA 100 E drIAW ON-178-Och2 "l i i---i IB d y I
-STABILITY REGON~ I 11FT IMMEDIATELY EXIT IAWON1T8-OO2 -LjT - -A-- 1I4 L .j 1 y_ 9 9..
90 90 RESTRICE0 REGION (AsdelnedinIiRoduiLinoi
- NDAP-QA.0336)
L~t i 98%
-IF ABOVE MEU.LARBOUNDARY.
- MMEEMATELYE-XITIAWON-178-O2 r, ~-rT 4I t1RdL 80 80
- 1i- h4_1_ -'1h4t- h11-iiii- lii-, til l iltF I -!I I- II J -I- L JI2- ILI l I-i--
4--
- l80%
Ii ]
T-r-1-:-
I III 4"1"4 1 --
I I I r'" -r -I Ii1
- - --- t--
_*FT11- iT 70 rT-r- rrir-) ri-T! -r- "I *i i" ir "1t Rod Line .70 n
&.T,4 -i-4-4.4- - . -I I 4 -
- r-FT..
I l I IIll I I ILI I I ll t t I ,-- - 1- t I.I I 112 J0 I I I I I -- I-l-tilt I I I 1 60 -LJ.. LJ.. 11 :
4.4-11 1-.1. 1 ,,* 60 a J .1 -
0 I, -,- -- I - - J- -I.---:1'-:-
-rT, L1 -1
-- ' j _j E. -LIJJ
-- I - +-1--- Li1.-1_
I lI Ro i n 50
{ 3%Sed : 1- I -ItL
.zu o0TI I 1 I I
- "-- 'I- IT t i ll-- -
.7 i i~!iii I It I t i l I II I I I I I t l; iii I TI II I tI
~iii . ;
il 1
II-I 2, -rr i---i-I- I IRo Ilin 40
- T*T 1 Twrp,--t-t
.1 T"-r-t i neI I I -!t I-I-,
-i- I---
~ttr I " :::;
- T 40 -l-i--t~ + -l-t-l--t- 4 -l-t--t 4-i--t--l--t- +
I vrj .I, If I -I-FTA--
L-fT~i I-L I4.
-hit-
!fI ' J'_ .4..
4 :- L- -1-1-. I1t .1._- -
I'Il F-T 1 I1-1--
f-, I - FI T -- FT -
/riT
- &..44 I- .-4--i- -f-.4- 4.-- - t- i- 14.- -1f-4.4-i--
Ill II tillI li iI 4I -1 . r - .r I I I I I I 30- 4- 1- .-kJ. J -- I~*k J.4_-4 1- IJJ 4. 4.J_
30
- L1.1 J - L 1 1.. -L L J.-. IL1 4J - L L.+/-
L I J -3 I 1 -rI tII~ I-I-I - 1l-- 1 -1 I t I I f- r T'
-.LT1 -4. -LIJJ-IýJJ L I 1_ - LL I J -L L 4.
II I I II I I I I I I I I I I - : I I I I II I I I I rr "I r Tr -rT -i--- Ir I I -r"T't'- -, T' 20 "1 I- -r t'i--I l I" t "-I-- * ,i . . . . . ,o *,
I I I
lIltI I. I 20
-11+1 L 1j i--
-i--- -t- -t 11 I I I I I I t tI I I I _L1 I I 'i- I I a I I I _ I
-i"Tii j - -I-'- - L I-I-1 I
-1 t-1 30 SpeLA -1. 1I I I- + - I- +-1 -'t- -I- 4=-4-- - lIltI
/ I j I I "A p- - i - L I I I I l I Hill!I I I ti "lt -iL L 1 FrTT pump I 10 'T - , *-,1 1F 44]-, fT1O. Speed, Speed, I till, I1II Ill I 10
" 4 - -"6r -f-I- - I,- -4l - -rT 4 - T-1-s-
-FT "1-- - FFT-4 4 4-4 I I I I I I I I I I I I I Ill! Il I I FT I I Tm I I -LT.4-
- I-i-I I I I I
-rr mn - Fr ifl'3 IT11
-r"-,- rlIi' Lf 4-i-- -LT 1 - lIl1
.J -1
- JU~* -),, L 1 J1 -1[,-1-, 1_. 1-]- i. a-.- *L &.4 I.
! 11I 0 0 0 10 20 30 40 50 60 70 80 90 100 110 Total Core Flow (Mlbmlhr)
(for SLO <75% Pump Speed Use Form GO-100-009-2)
Figure 9.1 SSES Unit 1 Cycle 18 Power / Flow Map SUSQUEHANNA UNIT 1 TRM/3.2-51 EFFECTIVE DATE 4/09/2012
PPL Rev. 13 PL-NF-12-001 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 1 TRM/3.2-52 EFFECTIVE DATE 4/09/2012
PPL Rev. 13 PL-NF-12-001 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 I 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"*-10: Appendix K Spray Heat Transfer Coefficients," Siemens Power Corporation, September 2000.
- 4. XN-NF-84-105(P)(A), Volume 1 and Volume I 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-I9(P)(A), Volume 1 and Supplements 1 and 2, "Exxon Nuclear Methodology for Boiling Water Reactors: Neutronic Methods for Design and 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).
SUSQUEHANNA UNIT 1 TRM/3.2-53 EFFECTIVE DATE 4/09/2012
PPL Rev. 13 PL-NF-12-001 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 I(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 I Revision I and Volume I 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 TPM/3.2-54 EFFECTIVE DATE 4/09/2012