ML060870452
| ML060870452 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 03/17/2006 |
| From: | Susquehanna |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| 028401, TRM1 | |
| Download: ML060870452 (68) | |
Text
Mar. 17, 2006 Page 1
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it SSES MA&NUAL
- Manual Name
TRM1 Manual
Title:
TECHNICAL REQUIREMENTS MANUAL UNIT 1 Table Of Contents Issue Date:
03/16/2006 Procedure Nane Rev TEXT LOES 26
Title:
LIST OF EFFECTIVE SECTIONS Issue Date 03/16/2006 Change ID Change Number TEXT TOC
Title:
6 01/06/2006 TABLE OF CONTENTS I
i I of TEXT 1.1 0
11/18/2002
Title:
USE AND APPLICATION DEFINITIONS TEXT 2.1 1
02/04/2005
Title:
PLANT PROGRAMS AND SETPOINTS PLANT PROGRAMS TEXT 2.2 4
11/22/2005
Title:
PLANT PROGRAMS AND SETROINTS INSTRUMENT TRIP SETPOINT TABLE TEXT 3.0 1
01/06/2006
Title:
TECHNICAL REQUIREMENT FOR OPERATION (TRO)
APPLICABILITY & SURVEILLANCE (TRS)
APPLICABILITY TEXT 3.1.1 0
11/18/2002
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 2
11/22/2005
Title:
REACTIVITY CONTROL SYSTEMS CONTROL ROD BLOCK INSTRUMENTATION TEXT 3.1.4 0
11/18/2002
Title:
REACTIVITY CONTROL SYSTEMS CONTROL ROD SCRAM CHECK VALVE ACCUMULATORS INSTRUMENTATION &
TEXT 3.2.1 6
03/16/2006
Title:
CORE OPERATING LIMITS REPORT (COLR)
Page 1 of 1
Report Date: 03/16/06 Page 1 of 15 Report Date: 03/16/06
SSES MANUAL Manual Name:
TRM1 Manual
Title:
TECHNICAL REQUIREMENTS MANUAL UNIT 1 TEXT 3.3.1
Title:
INSTRUMENTATION TEXT 3.3.2
Title:
INSTRUMENTATION TEXT 3.3.3
Title:
INSTRUMENTATION TEXT 3.3.4
Title:
INSTRUMENTATION TEXT 3.3.5
Title:
INSTRUMENTATION TEXT 3.3.6
Title:
INSTRUMENTATION TEXT 3.3.7
Title:
INSTRUMENTATION TEXT 3.3.8
Title:
INSTRUMENTATION TEXT 3.3.9
Title:
INSTRUMENTATION TEXT 3.3.10
Title:
INSTRUMENTATION TEXT 3.3.11
Title:
INSTRUMENTATION TEXT 3.4.1
Title:
11/18/2002 RADIATION MONITORING INSTRUMENTATION 0
11/18/2002 SEISMIC MONITORING INSTRUMENTATION 0
11/18/2002 METEOROLOGICAL MONITORING INSTRUMENTATION 1
07/06/2005 TRM POST-ACCIDENT MONITORING INSTRUMENTATION 0
11/18/2002 THIS PAGE INTENTIONALLY LEFT BLANK 2
10/19/2005 TRM ISOLATION ACTUATION INSTRUMENTATION 0
11/18/2002.
MAIN TURBINE OVERSPEED PROTECTION SYSTEM 1
10/22/2003 TRM RPS INSTRUMENTATION 1
11/22/2004 LPRM UPSCALE ALARM INSTRUMENTATION 1
12/14/2004 REACTOR RECIRCULATION PUMP MG SET STOPS 1
10/22/2003 MVP ISOLATION INSTRUMENTATION 0
11/18/2002 SYSTEM REACTOR COOLANT SYSTEM CHEMISTRY U
Page 2 of 15 Report Date: 03/16/06 Page 2 of 15 Report Date: 03/16/06
74 SSES MANUAL
) Manual Name:
TRM1 Manual
Title:
TECHNICAL REQUIREMENTS MANUAL UNIT 1 TEXT 3.4.2
Title:
REACTOR TEXT 3.4.3
Title:
REACTOR TEXT 3.4.4
Title:
REACTOR TEXT 3.4.5
Title:
REACTOR TEXT 3.5.1 0
11/18/2002 COOLANT SYSTEM STRUCTURAL INTEGRITY 0
11/18/2002 COOLANT SYSTEM HIGH/LOW PRESSURE INTERFACE LEAKAGE MONITORS 1
12/14/2004 COOLANT SYSTEM REACTOR RECIRCULATION FLOW AND ROD LINE LIMIT 0
11/18/2002 COOLANT SYSTEM REACTOR VESSEL MATERIALS 1
02/04/2005
Title:
EMERGENCY CORE COOLING AND RCIC ADS MANUAL INHIBIT TEXT 3.5.2 0
11/18/2002
Title:
EMERGENCY CORE COOLING AND RCIC ECCS AND RCIC SYSTEM MONITORING INSTRUMENTATION TEXT 3.5.3 0
11/18/2002.
Title:
EMERGENCY CORE COOLING AND RCIC LONG TERM NITROGEN SUPPLY TO ADS TEXT 3.6.1 0
11/18/2002
Title:
CONTAINMENT VENTING OR PURGING TEXT 3.6.2 0
11/18/2002
Title:
CONTAINMENT SUPPRESSION CHAMBER-TO-DRYWELL VACUUM BREAKER POSITION INDICATION TEXT 3.6.3 0
11/18/2002
Title:
CONTAINMENT SUPPRESSION POOL ALARM INSTRUMENTATION TEXT 3.6.4 0
11/18/2002
Title:
CONTAINMENT PRIMARY CONTAINMENT CLOSED SYSTEM BOUNDARIES TEXT 3.7.1 0
11/18/2002
Title:
PLANT SYSTEMS EMERGENCY SERVICE WATER SYSTEM (ESW)
SHUTDOWN Page 3 of 1!
Report Date: 03/16/06 Page 3 of 15)
Report Date: 03/16/06
SSES MANUAL Manual Name:
TRM1 Manual
Title:
TECHNICAL REQUIREMENTS MANUAL UNIT 1 TEXT 3.7.2
Title:
PLANT TEXT 3.7.3.1
Title:
PLANT TEXT 3.7.3.2
Title:
PLANT TEXT 3.7.3.3
Title:
PLANT TEXT 3.7.3.4
Title:
PLANT TEXT 3.7.3.5
Title:
PLANT TEXT 3.7.3.6
Title:
PLANT TEXT 3.7.3.7
Title:
PLANT TEXT 3.7.3.8
Title:
PLANT TEXT 3.7.4
Title:
PLANT TEXT 3.7.5.1
Title:
PLANT TEXT 3.7.5.2
Title:
PLANT 0
11/18/2002 SYSTEMS ULTIMATE HEAT SINK (UHS)
AND GROUND WATER LEVEL 0
11/18/2002 SYSTEMS FIRE SUPPRESSION WATER SUPPLY SYSTEM 1
08/24/2005 SYSTEMS SPRAY AND SPRINKLER SYSTEMS 2
08/18/2005 SYSTEMS'CO2 SYSTEMS 0
11/18/2002 SYSTEMS HALON SYSTEMS 0
11/18/2002 SYSTEMS FIRE HOSE STATIONS 0
11/18/2002.
SYSTEMS YARD FIRE HYDRANTS AND HYDRANT HOSE HOUSES 0
11/18/2002 SYSTEMS FIRE RATED ASSEMBLIES 4
09/08/2005 SYSTEMS FIRE DETECTION INSTRUMENTATION 0
11/18/2002 SYSTEMS SOLID RADWASTE SYSTEM 0
11/18/2002 SYSTEMS MAIN CONDENSER OFFGAS HYDROGEN MONITOR 0
11/18/2002 SYSTEMS MAIN CONDENSER OFFGAS EXPLOSIVE GAS MIXTURE I
K1~
Page 4 of 15 Report Date: 03/16/06 Page 4 of 15 Report Date: 03/16/06
SSES MANUAL
) Manual Name:
TRM1 Manual
Title:
TECHNICAL REQUIREMENTS MANUAL UNIT 1 TEXT 3.7.5.3
Title:
PLANT TEXT 3.7.6
Title:
PLANT 0
11/18/2002 SYSTEMS LIQUID HOLDUP TANKS 1
03/01/2005 SYSTEMS ESSW PUMPHOUSE VENTILATION TEXT 3.7.7 0
11/18/2002
Title:
PLANT SYSTEMS MAIN CONDENSER OFFGAS PRETREATMENT LOGARITHMIC RADIATION MONITORING TEXT 3.7.8 1
12/14/2004
Title:
PLANT SYSTEMS SNUBBERS TEXT 3.7.9 0
11/18/2002
Title:
PLANT SYSTEMS CONTROL STRUCTURE HVAC TEXT 3.7.10.
1 12/14/2004 Si449
Title:
PLANT SYSTEMS SPENT FUEL STORAGE POOLS (SFSPS)
TEXT 3.8.1 1
02/04/2005.
Title:
ELECTRICAL POWER PRIMARY.CONTAINMENT PENETRATION CONDUCTOR OVERCURRENT PRCTECTIVE DEVICES TEXT 3.8.2.1
Title:
ELECTRICAL CONTINUOUS 1
12/14/2004 POWER MOTOR OPERATED VALVES (MOV)
THERMAL OVERLOAD PROTECTION -
TEXT 3.8.2.2
Title:
ELECTRICAL AUTIOMATIC TEXT 3.8.3
Title:
ELECTRICAL TEXT 3.8.4
Title:
ELECTRICAL TEXT 3.8.5
Title:
ELECTRICAL 2
12/14/2004 POWER MOTOR OPERATED VALVES (MOV)
THERMAL OVERLOAD PROTECTION 0
11/18/2002 POWER DIESEL GENERATOR (DG)
MAINTENANCE ACTIVITIES 0
11/18/2002 POWER 24 VDC ELECTRICAL POWER SUBSYSTEM 0
11/18/2002 POWER DEGRADED VOLTAGE PROTECTION Page 5 of 15 Report Date: 03/16/06 Page 5 of 1'5 Report Date: 03/16/06
SSES MANUAL Manual Name:
TRM1 Manual
Title:
TECHNICAL REQUIREMENTS MANUAL UNIT 1 TEXT 3.8.6 0
11/18/2002
Title:
ELECTRICAL POWER EMERGENCY SWITCHGEAR ROOM COOLING 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 0
11/18/2002
Title:
MISCELLANEOUS SEAL SOURCE CONTAMINATION TEXT 3.10.2 0
11/18/2002
Title:
MISCELLANEOUS SHUTDOWN MARGIN TEST RPS INSTRUMENTATION TEXT 3.10.3 0
11/18/2002.
Title:
MISCELLANEOUS INDEPENDENT SPENT FUEL STORAGE INSTALLATION (ISFSI)
TEXT 3.10.4 0
11/18/2002
Title:
MISCELLANEOUS LEADING EDGE FLOW METER (LEFM)
TEXT 3.11.1.1 0
11/18/2002
Title:
RADIOACTIVE EFFLUENTS LIQUID EFFLUENTS CONCENTRATION TEXT 3.11.1.2 0
11/18/2002
Title:
RADIOACTIVE EFFLUENTS LIQUID EFFLUENTS DOSE TEXT 3.11.1.3 0
11/18/2002
Title:
RADIOACTIVE EFFLUENTS LIQUID WASTE TREATMENT SYSTEM TEXT 3.11.1.4
Title:
RADIOACTIVE EFFLUENTS 1
12/14/2004 LIQUID RADWASTE EFFLUENT MONITORING INSTRUMENTATION Page 6 of 15 Report Date: 03/16/06 Page 6 of 15 Report Date: 03/16/06
SSES MANUAL Manual Name:
TRM1 Manual
Title:
TECHNICAL REQUIREMENTS MANUAL UNIT 1 TEXT 3.11.1.5
Title:
RADIOACTIVE 1
12/14/2004 RADIOACTIVE LIQUID EFFLUENTS PROCESS MONITORING INSTRUMENTATION TEXT 3.11.2.1
Title:
RADIOACTIVE TEXT 3.11.2.2
Title:
RADIOACTIVE TEXT 3.11.2.3
Title:
RADIOACTIVE FORM TEXT 3.11.2.4
Title:
RAD)IOACTIVE EFFLUENTS EFFLUENTS EFFLUENTS EFFLUENTS 2
08/24/2005 DOSE RATE 0
11/18/2002 DOSE - NOBLE GASES 0
11/18/2002 DOSE -
IODINE, TRITIUM, AND RADIONUCLIDES IN PARTICULATE 0
11/18/2002 GASEOUS RADWASTE TREATMENT SYSTEM TEXT 3.11.2.,
< %)
Title:
RADIOACTIVE TEXT 3.11.2.5
Title:
RADIOACTIVE EFFLUENTS EFFLUENTS 1
05/20/2005 VENTILATION EXHAUST 2
12/14/2004.
RADIOACTIVE GASEOUS TREATMENT SYSTEM EFFLUENT MONITORING INSTRUMENrATION TEXT 3.11.3
Title:
RA2DIOACTIVE TEXT 3.11.4.1
Title:
RADIOACTIVE TEXT 3.11.4.2
Title:
RADIOACTIVE TEXT 3.11.4.3
Title:
RADIOACTIVE EFFLUENTS EFFLUENTS EFFLUENTS EFFLUENTS 0
11/18/2002 TOTAL DOSE 2
01/06/2006 MONITORING PROGRAM 1
12/14/2004 LAND USE CENSUS 0
11/18/2002 INTERLABORATORY COMPARISON PROGRAM TEXT 3.12.1
Title:
LOADS CONTROL PROGRAM 0
11/19/2002 CRANE TRAVEL-SPENT FUEL POOL STORAGE POOL Page 7 of
- .5 Report Date: 03/16/06 Page 7 of :a5 Report Date: 03/16/06
SSES MANUAL Manual Name:
TRM1 Manual
Title:
TECHNICAL REQUIREMENTS MANUAL UNIT 1 TEXT 3.12.2
Title:
LOADS CONTROL 0
11/19/2002 PROGRAM HEAVY LOADS REQUIREMENTS TEXT 3.12.3 0
11/19/2002
Title:
LOADS CONTROL PROGRAM LIGHT LOADS REQUIREMENT TEXT B3.0 1
01/06/2006
Title:
APPLICABI-LITY BASES TECHNICAL REQUIREMENT FOR OPERATION (TRO)
APPLICABILITY TEXT B3.1.1 0
11/19/2002
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 2
11/22/2005
Title:
REACTIVITY CONTROL SYSTEMS BASES CONTROL ROD BLOCK INSTRUMENTATION UJ TEXT B3.1.4 0
11/19/2002.
Title:
REACTIVITY CONTROL SYSTEMS BASES CONTROL ROD SCRAM ACCUMULATORS AND CHECK VALVE INSTRUMENTATION TEXT B3.2.1
Title:
CORE OPERATING LIMITS TEXT B3.3.1
Title:
INSTRUMENTATION BASES TEXT B3.3.2
Title:
INSTRUMENTATION BASES 0
11/19/2002 BASES CORE OPERATING LIMITS REPORT (COLR) 0 11/19/2002 RADIATION MONITORING INSTRUMENTATION 0
11/19/2002 SEISMIC MONITORING INSTRUMENTATION TEXT B3.3.3 1
02/04/2005
Title:
INSTRUMENTATION BASES METEOROLOGICAL MONITORING INSTRUMENTATION TEXT B3.3.4 1
07/06/2005
Title:
INSTRUMENTATION BASES TRM POST ACCIDENT MONITORING (PAM) INSTRUMENTATION Page 8 of 15 Report Date: 03/16/06 Page 8 of 15 Report Date: 03/16/06
SSES MANUAL
. Manual Name:
TRM1 Manual
Title:
- TECHNICAL REQUIREMENTS MANUAL UNIT 1 TEXT B3.3.5 0
11/19/2002
Title:
INSTRUMENTATION BASES THIS PAGE INTENTIONALLY LEFT BLANK TEXT B3.3.6
Title:
INSTRUMENTATION TEXT B3.3.7
Title:
INSTRUMENTATION TEXT B3.3.8
Title:
INSTRUMENTATION TEXT B3.3.9
Title:
INSTRUMENTATION TEXT B3.3.10
)
Title:
INSTRUMENTATION 3
10/19/2005 BASES TRM ISOLATION ACTUATION INSTRUMENTATION 0
11/19/2002 BASES MAIN TURBINE OVFRSPEED PROTECTION SYSTEM 1
10/22/2003 BASES TRM REACTOR PROTECTION SYSTEM (RPS)
INSTRUMENTATION 1
11/22/2004 BASES LPRM UPSCALE ALARM INSTRUMENTATION 0
11/19/2002 BASES REACTOR RECIRCULATION PUMP MG SET STOPS TEXT B3.3.11 1
10/22/2003.
Title:
INSTRUMENTATION BASES MVP ISOLATION INSTRUMENTATION TEXT B3.4.1
Title:
REACTOR TEXT B3.4.2
Title:
REACTOR TEXT B3.4.3
Title:
REACTOR TEXT B3.4.4
Title:
REACTOR TEXT B3.4.5
Title:
REACTOR 0
11/19/2002 COOLANT SYSTEM BASES REACTOR COOLANT SYSTEM CHEMISTRY 0
11/19/2002 COOLANT SYSTEM BASES STRUCTURAL INTEGRITY 0
11/19/2002 COOLANT SYSTEM BASES HIGH/LOW PRESSURE INTERFACE LEAKAGE MONITCR 0
11/19/2002 COOLANT SYSTEM BASES REACTOR RECIRCULATION FLOW AND ROD LINE LIMIT 0
11/19/2002 COOLANT SYSTEM BASES REACTOR VESSEL MATERIALS Page 9 of 2.5 Report Date: 03/16/06 Page 9 o f 3.5 Report Date: 03/16/06
SSES MANUAL Manual Name:
TRM1 Manual
Title:
TECHNICAL REQUIREMENTS MANUAL UNIT 1 K>
TEXT B3.5.1
Title:
11/19/2002 BASES ADS MANUAL INHIBIT TEXT B3.5.2 0
11/19/2002
Title:
ECCS AND RCIC BASES ECCS AND RCIC SYSTEM MONITORING INSTRUMENTATION TEXT B3.5.3
Title:
11/19/2002 BASES LONG TERM NITROGEN SUPPLY TO ADS 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 0
11/19/2002
Title:
CONTAINMENT BASES SUPPRESSION POOL ALARM INSTRUMENTATION 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 0
11/19/2002
Title:
PLANT SYSTEMS BASES FIRE SUPPRESSION WATER SUPPLY SYSTEM.
TEXT B3.7.3.2 1
08/24/2005
Title:
PLANT SYSTEMS BASES SPRAY AND SPRINKLER SYSTEMS TEXT B3.7.3.3 0
11/19/2002
Title:
PLANT SYSTEMS BASES C02 SYSTEMS Page 10 of 15 Report Date: 03/16/06 Page 10 of 15 Report Date: 03/16/06
SSES MANUAL
. Manual Name:
TRM1 Manual
Title:
TECHNICAL REQUIREMENTS MANUAL UNIT 1 TEXT B3.7.3.4
Title:
PLANT TEXT B3.7.3.5
Title:
PLANT 0
11/19/2002 HALON SYSTEMS SYSTEMS BASES SYSTEMS BASES 0
FIRE 11/19/2002 HOSE STATIONS TEXT B3.7.3.E;
Title:
PLANT 0
YARD 11/19/2002 FIRE HYDRANTS AND SYSTEMS BASES HYDRANT HOSE HOUSES TEXT B3.7.3.7
Title:
PLANT TEXT B3.7.3.8
Title:
PLANT v'EXT B3.7.4
(.
Title:
PLANT SYSTEMS BASES SYSTEMS BASES SYSTEMS BASES 0
11/19/2002 FIRE RATED ASSEMBLIES 1
01/12/2004 FIRE DETECTION INSTRUMENTATION 0
11/19/2002 SOLID RADWASTE SYSTEM TEXT B3.7.5.:.
Title:
PL.NT TEXT B3.7.5.2
Title:
PLANT SYSTEMS BASES SYSTEMS BASES 0
11/19/2002.
MAIN CONDENSER OFFGAS 0
11/19/2002 MAIN CONDENSER OFFGAS HYDROGEN MONITOR EXPLOSIVE GAS MIXTURE TEXT B3.7.5.3
Title:
PLANT TEXT B3.7.6
Title:
PLANT SYSTEMS BASES SYSTEMS BASES 0
11/19/2002 LIQUID HOLDUP TANKS 1
03/01/2005 ESSW PUMPHOUSE VENTILATION TEXT B3.7.7 0
11/19/2002
Title:
PLANT SYSTEMS BASES MAIN CONDENSER OFFGAS PRETREATMENT LOGARITHMIC RADIATION MONITORING INSTRUMENTATION TEXT B3.7.8 1
12/14/2004
Title:
PLANT SYSTEMS BASES SNUBBERS Page 11 of 1.3 Report Date: 03/16/06 Page 11 of 1.5 Report Date: 03/16/06
SSES MANUAL Manual Name:
TRM1 Manual
Title:
TECHNICAL REQUIREMENTS MANUAL UNIT 1 TEXT B3.7.9 1
12/14/2004
Title:
PLANT SYSTEMS BASES CONTROL STRUCTURE HVAC TEXT B3.7.10 1
12/14/2004
Title:
PLANT SYSTEMS BASES SPENT FUEL STORAGE POOLS TEXT B3.8.1
Title:
ELECTRICAL PROTECTIVE 1
02/04/2005 POWER BASES PRIMARY CONTAINMENT PENETRATION CONDUCTOR OVERCURRENT DEVICES TEXT B3.8.2.1
Title:
ELECTRICAL CONTINUOUS TEXT B3.8.2.2
Title:
ELECTRICAL AUTOMATIC 0
11/19/2002 POWER BASES MOTOR OPERATED VALVES (MOV)
THERMAL OVERLOAD 1
09/17/2004 POWER BASES MOTOR OPERATED VALVES (MOV)
THERMAL OVERLOAD PROTECTION -
PROTECTION -
TEXT B3.8.3
Title:
ELECTRICAL TEXT B3.8.4
Title:
ELECTRICAL TEXT B3.8.5
Title:
ELECTRICAL TEXT B3.8.6
Title:
ELECTRICAL TEXT B3.9.1 0
11/19/2002 POWER BASES DIESEL GENERATOR (DG) MAINTENANCE ACTIVITIES 0
11/19/2002.
POWER BASES 24 VDC ELECTRICAL POWER SUBSYSTEM 0
11/19/2002 POWER BASES DEGRADED VOLTAGE PROTECTION 1
02/04/2005 POWER BASES EMERGENCY SWITCHGEAR ROOM COOLING 0
11/19/2002 K)
Title:
REFUELING OPERATIONS BASES DECAY TIME TEXT B3.9.2 0
11/19/2002
Title:
REFUELING OPERATIONS BASES COMMUNICATIONS TEXT B3.9.
Title:
.3 0
11/19/2002 REFUELING OPERATIONS BASES REFUELING PLATFORM I
I Page 12 of 15 Report Date: 03/16/06 Page 12 of 15 Report Date: 03/16/06
SSES MANUAL
'. Manual Name:
TRM1 Manual
Title:
TECHNICAL REQUIREMENTS MANUAL UNIT 1 TEXT B3.10.1
Title:
MISCELLANEOUS TEXT B3.10.2
Title:
MISCELLANEOUS TEXT B3.10.3
Title:
MISCELLANEOUS 0
11/19/2002 BASES SEALED SOURCE CONTAMINATION 0
11/19/2002 BASES SHUTDOWN MARGIN TEST RPS INSTRUMENTATION 0
11/19/2002 BASES INDEPENDENT SPENT FUEL STORAGE INSTALLATION (ISFSI)
TEXT B3.10.4
Title:
MISCELLANEOUS 0
BASES LEADING 11/19/2002 EDGE FLOW METER (LEFM)
TEXT B3.11.1.1
Title:
RADIOACTIVE EFFLUENTS 0
11/19/2002 BASES LIQUID EFFLUENTS CONCENTRATION tmEXT B3.11.1.2 0
Title:
RADIOACTIVE EFFLUENTS BASES TEXT B3.11.1.3 0
Title:
RADIOACTIVE EFFLUENTS BASES 11/19/2002 LIQUID EFFLUENTS DOSE 11/19/2002.
LIQUID WASTE TREATMENT SYSTEM 11/19/2002 LIQUID RADWASTE EFFLUENT MONITORING INSTRUMENTATION 11/19/2002 RADIOACTIVE LIQUID PROCESS MONITORING TEXT B3.11.1.4 0
Title:
RADIOACTIVE EFFLUENTS BASES TEXT B3.11.1.5
Title:
RADIOACTIVE EFFLUENTS INSTRUMENTATION TEXT B3.11.2.1
Title:
RADIOACTIVE EFFLUENTS TEXT B3.11.2.2
Title:
RADIOACTIVE EFFLUENTS TEXT B3.11.2.3
'Title: RADIOACTIVE EFFLUENTS if PARTICULATES FORM 0
BASES 1
12/14/2004 BASES DOSE RATE 0
11/19/2002 BASES DOSE -
NOBLE GASES 0
11/19/2002 BASES DOSE -
IODINE, TRITIUM, AND RADIONUCLIDES IN Page 13 of 15 Report Date: 03/16/06 Page 13 of 15 Report Date: 03/16/06
SSES MANUAL Manual Name:
TRMI Manual
Title:
TECHNICAL REQUIREMENTS MANUAL UNIT 1 TEXT B3.11.2.4
Title:
RADIOACTIVE EFFLUENTS TEXT B3.11.2.5
Title:
RADIOACTIVE EFFLUENTS TEXT B3.11.2.6
Title:
RADIOACTIVE EFFLUENTS INSTRUMENTATION TEXT B3.11.3
Title:
RADIOACTIVE EFFLUENTS 0
BASES 3
BASES 1
BASES 11/19/2002 GASEOUS RADWASTE TREATMENT SYSTEM 05/20/2005 VENTILATION EXHAUST TREATMENT SYSTEM 01/27/2004 RADIOACTIVE GASEOUS EFFLUENT MONITORING 0
11/19/2002 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 K-)
TEXT B3.11.4.3 0
11/19/2002.
Title:
RADIOACTIVE EFFLUENTS BASES INTERLABORATORY COMPARISON PROGRAM TEXT B3.12.1 0
Title:
LOADS CONTROL PROGRAM BASES TEXT B3.12.2 0
Title:
LOADS CONTROL PROGRAM BASES TEXT B3.12.3 0
Title:
LOADS CONTROL PROGRAM BASES 11/19/2002 CRANE TRAVEL-SPENT FUEL STORAGE POOL 11/19/2002 HEAVY LOADS REQUIREMENTS 11/19/2002 LIGHT LOADS REQUIREMENTS TEXT 4.1 0
08/31/1998
Title:
ADMINISTRATIVE CONTROLS ORGANIZATION TEXT 4.2 0
08/31/1998
Title:
ADMINISTRATIVE CONTROLS REPORTABLE EVENT ACTION Page 14 of 15 Report Date: 03/16/06 Page 14 of 15 Report Date: 03/16/06
SSES MANUAL I Manual Name:
TRM1 Manual
Title:
- TECHNICAL REQUIREMENTS MANUAL UNIT 1 TEXT 4.3
Title:
TEXT 4.4
Title:
TEXT 4.5
Title:
TEXT 4.6
Title:
TEXT 4.7
Title:
ADMINISTRATIVE ADMINISTRATIVE ADMINI STRATIVE ADMINISTRATIVE ADMINISTRATIVE 0
CONTROLS 0
CONTROLS 0
CONTROLS 0
CONTROLS 0
CONTROLS 08/31/1998 SAFETY LIMIT VIOLATION 08/31/1998 PROCEDURES & PROGRAMS 08/31/1998 REPORTING REQUIREMENTS 08/31/1998 RADIATION PROTECTION PROGRAM 08/31/1998 TRAINING Page 15 of 15 Report Date: 03/16/06 Page 15 of 1!5 Report Date: 03 /16/06
SUSQIJEHANNA STEAM ELECTRIC STATION PPL Rev. 26 LIST OF EFFECTIVE SECTIONS (TECHNICAL REQUIREMENTS MANUAL)
Section Title TOC TABLE OF CONTENTS 1.0 USE AND APPLICATION Pages TRM / 1.0-1 through TRM / 1.0-3 Effective Date 01/28/2035 2.0 PLANT PROGRAMS Page 2.0-1 Pages TRM / 2.0-2 and TRM / 2.0-3 Page TRM / 2.0-4 Page TRM / 2.0-5 Pages TRM / 2.0-6 and TRM / 2.0-7 Page TRM / 2.0-8 Pages TRM / 2.0-9 through TRM / 2.0-11 Pages TRM / 2.0-12 through TRM / 2.0-15 3.0 10/04/2002 08131/1998 01/28/200)5 06/25/20102 04/02/1999 11/15/2004 12/03/2004 11/15/2004 11/15/2035 04/08/1999 03/15/2032 11/30/2005 08/31/1998 11/15/2005 02/18/1999 02/18/1999
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, ~
jL Page TRM / 3.0-4 REACTIVITY CONTROL SYSTEMS Pages 3.1-1 through 3.1-6 Pages TRM / 3:1-7 and TRM / 3.1-8' ]
Pages TRM / 3.1-9 snd TRM 'i 3.1-9a Page TRM / 3.1-1Q CORE OPERATING LIMITS REPORT Page TRM / 3.2-1',,
Pages TRM /[3.2-2 through TRM / 3.2-43 INSTRUMENTATION' PagesTRM / 3.3-1,through TRM / 3.3-3 Page TRM / 3.3-4 tPages 3.3-5 through 3.3-8 Pages TRM / 3.3-9 and TRM / 3.3-9a Page TRM / 3.3-10 Pages TRM / 3.3-11 and TRM /3.3-1 la Page TRM / 3.3-12 Page TRM / 3.3-13 Page TRM / 3.3-14 Page TRM / 3.3-15 Page TRM / 3.3-16 Pages TRM / 3.3-17 and TRM / 3.3-18 Pages TRM / 3.3-19 through TRM / 3.3-21 Page TRM / 3.3-22 Pages TRM / 3.3-22a through TRM / 3.3-22d Page TRM / 3.3-23
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TRM / LOES-1
- ^ EFFECTIVE DATE 03/1 1/2'006
SUSQUEHANNA STEAM ELECTRIC STATION PPL Rev. 26 LIST OF EFFECTIVE SECTIONS (TECHNICAL REQUIREMENTS MANUAL)
Section Title Pages TRM / 3.3-24 and TRM / 3.3-25 Page TRM / 3.3-26 3.4 3.5 3.6 3.7
~~90W REACTOR COOLANT SYSTEM Pages 3.4-1 through 3.4-5 Pages 3.4-6 through 3.4-11 Page TRM t 3.4-12 Page 3.4-13 EMERGENCY CORE COOLING Page TRM / 3.5-1 Pages 3.5-2 and 3.5-3 Page TRM / 3.5-4 Pages 3.5-5 through 3.5-7 CONTAINMENT Pages 3.6-1 through 3.6-3 Page TRM /3.6-4 Page 3.6-5 Pages TRM / 3.6-6 through TF PLANT SYSTEMS Pages 3:7-1 through 3.7-3 Pages TRM / 3.7-4 through TF Pages TRM / 3.7-9 and TRM I Page TRM / 3.7-11 Pages TRM / 3.7-12 and TRM Page TRM / 3.7-14 Pages TRM / 3.7-15 through 1 Pages TRM / 3.7-28 and TRM Page TRM / 3.7-30 Pages TRM / 3.7-31 and TRM Page TRM / 3.7 Page TRM /3.7-34 Page TRM / 3.7-34a Pages TRM / 3.7-35 through 1 Pages 3.7-38 through 3.7-40 Pages TRM / 3.7-41 and TRM Pages 3.7-42 and 3.7-43 Page TRM / 3.7-44 Pages 3.7-45 through 3.7-48 Page TRM / 3.7-49 Pages TRM / 3.7-50 and TRM Pages TRM / 3.7-52 Paae TRM / 3.7-53 AND RCIC RM / 3.6-8 RM / 3.7-8 13.7-l0
/3.7.13 FRM / 3.7-27
/3.7-29 3.7-32 M
TRM t 3.7-37 Effective Date 05/16/2003 10/22/2003 10/23/1998 08/31/1998 12/03/2004 08/31/1998 01/28/2005 08/31/1998 04/17/2000 08/31/1998 08/31/1998 01/07/2002 08/31/1998 12/31/2002 08/31/1998 08/02/1999 08/16/2005 12/29/1999 08/02/1999 08/09/2005 08/02/1999 08/09/2005 08/25/2005 11/16/2001 01/09/2004 11/16/2001 10/05/2002 02/01/1999 08/31/1998 02/14/2005 08/31/1998 12/03/2004 10/13/1998 03/08/2003 03/09/2001 12/03/2004 04/15/2003 07/29/1999
/ 3.7-41a
/ 3.7-51 Page TRM / 3.7-54 S U Q J E A N
-_NT IT M / L E -
F E T V A E 0 / 1 2 0 SUSQUEHANNA - UNIT 1 TRM / LOES-2 EFFECTIVE DATE 03/11/2006
SUSQIJEHANNA STEAM ELECTRIC STATION PPL Rev 26 LISTC)FEFFECTIVESECTIONS (TECHNICA.L REQUIREMENTS MANUAL)
_j Section Title Effective Date
%ii 3.8 3.9 3.10 ELECTRICAL POWER Page TRM / 3.8-1 Pages TRM / 3.8-2 through TRM / '3.8-4 Pages TRM / 3.8-5 and TRM / 3.8-6 Pages TRM / 3.8-7 through TRM / 3.8-10 Page TRM / 3.8-11 Page TRM / 3.8-12 Pages 3.8-13 and 3.8-14 Pages TRM / 3.8-15 through TRM / 3.8-17 Page 3.8-18 Page TRM / 3.8-19 Page 3.8-20 Pages TRM / 3.8-21 through TRM / 3.8-23 Pages 3.8-24 and 3.8-25 REFUELING OPERATIONS Pages 3.9-1 through 3.9-3 MISCELLANEOUS Pages 3.10-1 through 3.10-4 Page TRM / 3.10-5 04/02/2002 01/28/20)5 04/02/20)2 12/03/2004 08/10/2004 12/03/20)34 08/31/19'38 04/02/20)2 08/31/1938 04/02/20)2 08/31/1998 06/06/1999 08/31/1998 08/31/1998 08/31/i998 03/08/2003 06/05/2002
'04/07/20DO 04/17/2002 3.11 ii i:1
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III Page TRM / 3.10-6 Page TRM / 3.10-7 Page TRM / 3.10-8-I ADIOACTIVE EFFLUENTS Pages 3.11-1 through 3.11-9 Page TRM / 3. 11-10 Pages 3.11-11 and 3.11-12 Page 3.11-13 Page TRM / 3.11-14 Pages 3.11-15 anc 3.11-16 Pages 3.11-17 and 3.11-18 Page TRM / 3.11-19 Pages 3.11-20 and 3.11-21 Page TRM / 3.11-22 Pages TRM / 3.11-23 and TRM / 3 1 -24 Page 3.11-25 l
Pages TRM / 3.11-26 through TRM 3.11-28 Page TRM/3.11-29 Pages TRM / 3.11.30 through TRM /3.11.32 Pages 3.11-33 and 3.11-34 Pages TRM / 3.11-35 through TRM /3.11-39 Pages 3.11-40 through 3.11-44 Page TRM / 3.11-45 Pages 3.11-46 and 3.11-47 08/31/1998 12/03/2004 08/31/1998 09/011998
- 12/0312004 09/01/1998 H 08/31/1998 108115/2005 108/31/1998 04/02/2002 105/13/2005
'09/01/1998
,01/21/2004' 112/03/2004 01/21/2004 08/31/1998 11/30/2005 08/31/1998 12/03/2004 08/31/1998 I 1:;: II i :
SUSQI. IEHANNA - UNIT 1 i
TRM / LOE i
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S-3 EFFECTIVE DATE 03/11/2'006
SUSQIJEHANNA STEAM ELECTRIC STATION PPL Rev. 26 LIST OF EFFECTIVE SECTIONS (TECHNICAL REQUIREMENTS MANUAL)
Section Title Effective Date Ii,.."-
3.12 LOADS CONTROL PROGRAM Pages TRM / 3.12-1 through TRM / 3.12-5 4.0 02/05/1999 08/31/199 ADMINISTRATIVE CONTROLS Pages 4.0-1 through 4.0-8 i
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.SUSQUEHANNA - UNIT 1 II EFFECTIVE DATE 03/ 11/2006
SUSQUEHANNA STEAM ELECTRIC STATION PPL Rev. 26 LIST OF EFFECTIVE SECTIONS (TECHNICAL REQUIREMENTS MANUAL)
Section Title B 3.0 APPLICABILITY BASES Pages B 3.0-1 through B 3.0-10, Pages TRM / B 3.0-11 and TRM / B 3.0-12 Pages TRM / B 3.0-13 and TRM / B 3.0-14 Page TRM / B 3.0-15 B 3.1 REACTIVITY CONTROL SYSTEMS BASES Pages TRM / B 3.1-1 through TRM I B 3.1-3 Page B 3.1-4 Pages TRM / B 3.1-5 through TRM / B 3.1-7 Page TRM / B 3.1-8 Effective Date 08/31/1998 03/15/2002 11/30/2005 03/15/2002 07/13/1999 08/31/1998 11/15/2005 02/18/1999
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B 3.2 B 3.3 B 3.4 B 3.5 B 3.6 INSTRUMENTATION BASES Page TRM / B 3.3-1 Page B 3.3-2 Pages TRM / B 3.3-3 and TRM / B 3.3-3A Pages TRM / B 3.3-4 through TRM / B 3.3-6 Pages TRM / B 3.3-7 through TRM / B 3.3-9 Page B 3.3-10 Pages TRM / B.3.3-11 and TRM / B 3.3-12 Page TRM / B 3.3-13 Page TRM / B 3.3-14 Page TRM / B 3.3-14a Page TRM / B 3.3-14b Pages TRM / B 3.3-15 and TRM I B 3.3-16 Page TRM / B 3.3-17 Pages TRM / B 3.3-17a through TRM / B 3.3-17f Pages TRM / B3.3-18 and TRM / B 3.3-19 Page TRM / B 3.3-20 Page TRM / B 3.3-21 REACTOR COOLANT SYSTEM BASES Pages 83.4-1 through B 3.4-4 Page TRM / B 3.4-5 Page B 3.4-6 ECCS AND RCIC BASES Pages B 3.5-1 through.B 3.5-5,!
CONTAINMENT BASES Page TRM / B 3.6-1 PageTRM/B3.6-2 Page B 3.6-3 CORE OPERATING LIMITS BASES Page B 3.2-1 08/31/1998 04/07/2000 08/31/1998 01/31/2005 06/02/2005 03/30/2001 08/31/1998 09/13/2005 12/03/2004 06/25/2002 06/14/2002 06/14/2002 10/22/2003 11/15/2004 11/15/201)4 05/16/2003 10/22/2003 05/16/2003 08/31/1998 10/15/1999 08/31/1998 08/31/1998 07/26/2001 02/01/1999 08/31/1998 II
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- UNIT I TRM I LOES-5 EFFECTIVE DATE 03/11/2006 SUSQUEHANNA - UNIT 1 TRM / LOES-51 EFFECTIVE DATE 03/11/2006
SUSQUEHANNA STEAM ELECTRIC STATION PF LIST C:F EFFECTIVE SECTIONS (TECHNICAL REQUIREMENTS MANUAL)
IL Rev. 26
!iIi Section Title Page TRM / B 3.6-4 Page TRM / B 3.6-5 Pages TRM / B 3.6-6 Pages B.3.6-7 through TRM / B 3.6-11 t*10)
B 3.7 I
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Pages TRM / B 3.8-6 through TRM / B 3.8-16 Page TRM / B 3.8-17 I
Effective Date 09/23/1999 01/07/2002 12/03/2004 12/31/2002 08/31/1998 08/02/1999 08/16/20()5 08/02/1999 08/02/1999 08/02/1999 08/02/1999 08/02/1999 08/02/1999 01/09/2004 02/01/1999 08/31/19'98 02/14/2005 04/07/20C)0 08/31/1998 12/03/2004 08/31/1998 12/03/2004 03/09/2001 04/15/2003 12/03/2004 07/05/2000 I
i 04/02/2002 01/28/2005 04/02/2002 1 04/02/2002 0 08/10/2004 04/02/2002 08/31/1998 04/02/20)2 01/28/2035 08/31/1998 REFUELING OPERATIONS BASES Pages B 3.9-1 through B 3.9-7l I
i SUSQUEHANNA - UNIT 1 TRM / LOES-6 EFFECTIVE DATE 03/11/2006
SUSQUJEHANNA STEAM ELECTRIC STATION PPL Rev. 26 LIST CF EFFECTIVE SECTIONS (TECHNICAL REQUIREMENTS MANUAL)
Section Title B 3.10 MISCELLANEOUS BASES Pages B 3.10-1 through B 3.10-2 Page TRM / B 3.10-3 Pages TRM / B 3.10-4 and TRM / B 3.10-5 Pages TRM / B 3.10-6 and TRM / B 3.10-7 B 3.11 RADIOACTIVE EFFLUENTS BASES Pages B 3.11-1 through B 3.11-9 Page TRM / B 3.11-10 Pages TRM/B 3.11-11 and TRM/B ';.11-1 Ia Pages TRM/B 3.11-12 and TRM/B 3.11-13 Page TRM / B 3.11-14 Page TRM / B 3.11-15 Pages B 3.11-16 through B 3.11-19 Page TRM / B 3.11-20 Page TRM / B 3.11-20a Pages TRM / B 3.11-21 through TRM / B 3.11.23a Pages TRM / B 3.11-24 and TRM /B 3.11-25 Pages B 3.11-26 and B 3.11-27 Pages TRM / B 3.11-28 and TRM I B 3.11-29 Page TRM / B 3.11-30 Pages B 3.7-31 through B 3.7-35 Page TRM / B 3.11-36 B.3.12 LOADS CONTROL PROGRAM BASES Pages TRM / B 3.12-1 through TRM / B 3.12-3 Effective Date 08/31/1998 03/08/20()3 08/23/1999' 04/17/2002 08/30/1998 02/01/1999 04/07/20()0 02/01/1999 12/03/2004 02/01/1999 08/30/1998 04/02/2002 04/02/2002 05/13/2005 01/21/2004 08/30/1998 1 1/30/20()5 12/03/20()4 08130/1998 02/12/1999 02/05/1999 TRMIltext L 3/9/06
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SUSQLI EHANNA - UNIT 1 TRM / LOES-7 EFFECTIVE DATE 03/11/2006
Core Operating Limits Report (COLR) 3.2'.1 PPL Rev. 6 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.
i:
APPLICABILITY:
Specified in the referenced Technical Specifications.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Core Operating Limits A.1 Perform action(s)
Specified in not met.
described in referenced referenced Technical Specification.
Technical Specifications.
TECHNICAL REQUIREMENT SURVEILLANCE SURVEILLANCE.
FREQUENCY
---NOTE--
N/A No associated Surveillances. Surveillances are implemented in the applicable Technical Specifications.
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PPL Rev. 6 PL-NF-06-001 Rev. 0 Page 1 of 43 Susquehanna c I
Unit 1 Cycle 1 CORE O3PERAT"ING
_RIEPR REPORT I
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PPL Rev. 6 PL-NF-06-001 Rev. 0 Page 2 of 43 lIam 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 15 operation.
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FORM NF SUSQU
'-QA-008-2, Rev. 1 7HANNA UNIT 1, TRM/3.2-3 EFFECTIVE DATE 03/11/2C06
PPL Rev. 6 PL-NF-06-001 Rev. 0 Page 3 of 4$;
1.0 2.0 I
3.0 4.0 SUSQUEHANNA STEAM ELECTRIC STATION Unit 1 Cycle 15 CORE OPERATING LIMITS REPORT Table of Contents INTRODUCTION 4...........
.4 DEFINITIONS
.6 AVERAGE PLANAR LINEAR HEAT GENERATION RATE (APLHGR) 7 5.0 6.0 7.0 8.0 9.0 100 11.0 MINII I~M CRTICAL POWER RATIO (MCPR...............................
L.INEAR HEAT GENERATION RATE (LHGR)............................................................. 21 AVERAGE POWER RANGE MONITOR (APRM) GAIN AND SETPOINTS................ 24 RECIRCULATION LOOPS - SINGLE LOOP OPERATION.........................................7 27 POWER 1 FLOW MAP................................................................
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()PRM SETPOINTS.i.................................................................
REFERENCES..
42.......................
42 i114,40KI qi
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j TRM/3.2-4 EFFECTIVE DATE 03/11/2006
PPL Rev. 6 PL-NF-06-001 Rev. 0 Page 4 of 43 ASP i
1.0 INTRODUCTION
This CORE OPERATING LIMITS REPORT for Susquehanna Unit 1 Cycle 15 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, APRM 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.
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SUSQUEHANNA UNIT 1 TRM/3.2-5 EFFECTIVE DATE 03/11/2006
PPL Rev. 6 PL-NF-06-001 Rev. 0 Page 5 of 43 1I t
2.0 I)EFINITIONS Terms used in this COLR but not defined in Section 1.0 of the Technical Specifications or Section 1.1 of the Technical Requirements Manual are provided below.
2.1 The AVERAGE BUNDLE EXPOSURE shall be equal to the total energy produced by the bundle divided by the total initial weight of uranium in the fuel bundle.
'.2 The AVERAGE PLANAR EXPOSURE at a specified height shall be equal to the total energy produ6ed per unit length at the specified height divided by the total initial weigh': of uranium per unit length at that height.
2.3 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.
2.4 The FRACTION OF LIMITING POWER DENSITY (FLPD) shall be the LHGR existing at a given height divided by the applicable LHGR for APRM Setpoint Limit for that bundle t4pe.
2.5 The FRACTION OF RATED THERMAL POWER (FRTP) shall be the measured THERMAL POWER divided by the RATED THERMAL POWER.
- 2.6 FDLRX is the ratio of the maximum LHGR calculated by the core monitoring system fcr each fuel bundle divided by the LHGR limit for the applicable fuel bundle type.
2.7 MFLCPR is the ratio of the applicable M PR operating limit for the applicable fuel bundle type divided by the MCPR calculated by the core monitoring system for each fuel bundle.
2>.8 MAPRAT is the ratio f the maximum APLHGR calculated by the core monitoring system for each fuel bundle divided by the APLGHR limit for the applicable fuel bundle type.
- 2.9 FDLRC is the ratio of the maximum LHGR calculated by the core monitoring system for each fuel bundle divided by the LHGR for APRM Setpoint Limit for the applicable fuel bundle type.
2.10 OPRM is the Oscillation Power Range Monitor. The Oscillation Power Range Monitor (OPRM) will. reliably detect and suppress anticipated stability related power oscillations while providirg a high'degree of confidence that the MCPR safety limit is not violated.
2.11 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.
2.12 S, is the OPRM trip setpoint for the peak to average OPRM signal.
2.13 Fp is the core flow, in Mlbm I hr. below which the OPRM RPS trip is activated.
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TRM/3.2-6 EFFECTIVE DATE 03/11/2(106
PPL Rev. 6 PL-NF-06-001 Rev. 0 Page 6 of 43 3.0 ESHUTDOWN MARGIN
',.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,Ilhe 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 03/11/2006
i^;0.
PPL Rev. 6 PL-NF-06-OD1 Rev. 0 Page 7 of 4:3 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 and EOC-RPT Operable and Inoperable in Two Loop operation.
The APLHGR limits for Single Loop operation are provided in Section 8.0.
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.TRM/3.2-8 EFFECTIVE DATE 03/11/2006
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0 10000 20000 30000 40000
- 50000
.600001 70000 Average Planar Exposure (MWD/MTU)
AVERAGE PLANAR LINEAR HEAT GENERATION RATE LIMIT VERSUS AVERAGE PLANAR EXPOSURE TWO LOOP OPERATION ATRIUMTM.1.l0 FUEL FIGURE 4.2-1
PPL Rev. 6 PL-NF-06-OD1 Rev. 0 Page 9 of 4:3 I14"W 5.0 l
i I
iU MINIMUM CRITICAL POWER RATIO ( ICPR) ri.1 Technical Specification Reference Technical Specification 3.2.2, 3.7.6, and 3.3.4.1
';.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)
EOC-RPT and Main Turbine Bypass 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 / EOC-RPT Operable 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 7 Main Turbine Bypass Operable Figure 5.2-5: Flow-Dependent MCPR value determined from BOC to EOC Figure 5.2-6: Power-Dependent MCPR value determined from BOC tb EOC The MCPR limits in Figures 5.2-1 through 5.2-6 are valid for Two Loop operation.
The MCPR limits for Single Loop operation are provided in Section 8.0.
QUEHANNA UNIT 1 TRM/3.2-10 EFFECTIVE DATE 03/11/2006
PPL Rev. 6 PL-NF-06-Cl01 Rev. 0 Page 10 of 43
.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.
SUSQUEHANNA UNIT 1 TRM/3.2-11 EFFECTIVE DATE 03/11/2006
PPL Rev. 6 PL-NF-06-001 Rev. 0 Page 11 of 43 i
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)C-RPT and Main Turbine Bypass I' '
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TRM/3.2-12 EFFECTIVE DATE 03/11/2006
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SSES UNIT 1 CYCLE 15 2.2 2.1 2.0-1.9 r
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I CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME I
4-CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME
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rv 21.7 cr CA)O 1 t.6 1.5 SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 USED IN DETERMINING MFLCPR
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(108,1.37) t 1
1 1
4 4-4" 4
I
- 1.
1 30 40 50 60 70 80 90 100 110 Total Core Flow (MLB/HR)
MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW EOC-RPT AND MAIN TURBINE BYPASS OPERABLE TWO LOOP OPERATION (BOC TO EOC)
FIGURE 5.2-1 o0 c
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2.7 2.6:
2.5:
2.4 25-,2.78)-
- URVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME
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CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME I
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SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2
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70 80 90 100 Core Power (% RATED)
MCPR OPERATING LIMIT VERSUS CORE POWER EOC-RPT AND MAIN TURBINE BYPASS OPERABLE TWO LOOP OPERATION (BOC TO EOC)
FIGURE 5.2-2 T :m _
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PPL Rev. 6 PL-NF-06-001 Rev. 0 Page 14 of 43 (aw) f L
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I CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME 2.1 4
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- 4.
4-4 4
+
I 30 40 50 60 70 80 90 100 110 Total Core Flow (MLB/HR)
MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW MAIN TURBINE BYPASS INOPERABLE I EOC.RPT OPERABLE TWO LOOP OPERATION (BOC TO EOC)
FIGURE 5.2-3 D CD 1 (D
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0 co I
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--i SSES UNIT 1 CYCLE 15 3.0 -
2.9 2.8 2.7 I
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(30,2.65)
LEGEND CURVE A: MAXIMUM ALLoWABLE AVERAGE SCRAM INSERTION TIME CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME 2.6 2.5
-I i
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(I ZIZv--:[ ---
i_-
SAFETY ANALYSES ASSUME THAT TWO OR MORE BYPASS VALVES ARE INOPERABLE PER SR 3.7.6.1 OR 3.7.6.2
,E 2.4 I-
-0 (1.4 (100,1.47)
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ft0 MCPR OPFRATING LIMIT VERSUS CORE POWER MAIN TURBINE BYPASS INOPERABLE / EOC-RPT OPERABLE TWO LOOP OPERATION (BOC to EOC)
FIGURE 5.2-4
PPL Rev. 6 PL-NF-06-001 Rev. 0 Page 17 of 43 I%mwI A
EOC-IRPT Inoperable I Main Turbine Bypass Operable
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2.0 I
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CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM -
INSERTION TIME CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME 4.
-- --- --- L, ---
I IrII 1.9 --
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,E 1.8-N) w f-a a.7 W) a:
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- I 1.3 7
L 1.2 D-3CI 40 50 60 70 80 90 100 110 Total Core Flow (MLB/HR)
MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW EOC-RPT INOPERABLE / MAIN TURBINE BYPASS OPERABLE TWO LOOP OPERAT ION (BOC TO EOC)
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t fr f
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- -2 SSES UNIT 1 CYCLE 15 3.0 I
i I LEGEND 2.9 2.8 2.7 2.6 2.5 I
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_ 2.0 1.9
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20 I
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(100,1.38)
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I 30 40 50 60 70 80 90 100 Core Power (% RATED)
MCPR OPERATING LIMIT VERSUS CORE POWER EOC-RPT INOPERABLE / MAIN TURBINE BYPASS OPERABLE TWO LOOP OPERATION (BOC to EOC)
FIGURE 5.2-6 CD CD r.
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W
PPL Rev. 6 PL-NF-06-001 Rev. 0 Page 20 of 43 Table 5.3-1 Average Scram Time Fraction Table For Use With Scram Time Dependent MACPR Operating Limits Control Rod Average Scram Time to Position (seconds)
Position 45 0.470 0.520 3
0.630 0.860 25 1.500 1.910 iX_
!_ 2.700 3.440 Average Scram Realistic Maximum Insertion Time Allowable t,*101I I
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I; EFFECTIVE DATE 03/11/2006
PPL Rev. 6 PL-NF-06-031 Rev. 0 Page 21 of 43 6.0 LINEAR HEAT GENERATION RATE (LHGR)
E;.l Technical Specification Reference Technical Specification 3.2.3 and 3.7.6 6.2 Description The LHGR limits are specified below as a function of Main Turbine Bypass operability for each fuel type as follows:
Main Turbine Bypass Operable The LHGR for ATRIUM'-10 fuel shall not exceed the LHGR limit determined from Figure 6.2-1.
Main Turbine Bypass Inoperable The LHGR for ATRIUM'-10 fuel shall not exceed the LHGR limit determined from Figure 6.2-2.
The LHGR limits in Figures 6.2-1 and 6.2-2 are valid for Two Loop and Single Loop operation.
UE I
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20000 30000 40000 50000 60000 Pellet Exposure (MWD/MTU) --
LINFAR HEAT GENERATION RATE LIMIT VERSUS PELLET EXPOSURE MAIN TURBINE BYPASS OPERABLE ATRIUMTM-10 FUEL FIGURE 6.2-1 70000 80000 C
D Ir ro a an D
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LINEAR HEAT GENERATION RATE LIMIT VERSUS PELLET EXPOSURE MAIN TURBINE BYPASS INOPERABLE AT RlUT M10 FUEL FIGURE 6.2-2 70000 80000
PPL Rev. 6 PL-NF-06-001 Rev. 0 Page 24 of 43 7.0 AVERAGE POWER RANGE MONITOR (APRM) GAIN AND SETPOINTS 7.1 Technical Specification Reference Technical Specification 3.2.4 and 3.3.1.1 7.2 Description The APRM Simulated Thermal Power-High scram trip setpoint (S) and APRM Simulated Thermal Power-High control rod block trip setpoint (SRB) shall be established as specified in Table 7.2-1, including any adjustments per Technical Specification LCO 3.2.4.
Technical Specification LCO 3.2.4 provides an option to adjust the APRM setpoints when MFLPD is greater than FRACTION OF RATED THERMAL POWER (FRTP). The adjustment applies to both the APRM Simulated Thermal Power-High scram trip setpoint and APRM Simulated Thermal Power-High control rod block trip setpoint for Two Loop and Single Loop operation. The APRM setpoints for Specification 3.2.4 are established in Table 7.2-1.
I SUSQUEHANNA UNIT 1 TRMI3.2-25 EFFECTIVE DATE 03/11/2306
PPL Rev. 6 PL-NF-06-031 Rev. 0 Page 25 of 43 Table 7.2-1 APRM Setpoint Trip Setpoint Allowable Value S5(0.58 (W - AW) + 59%) T S* (0.58 (W - AW) + 62%) T1 SAB < (0.58 (W - AW) + 50%) T SRB < (0.58 (W - AW) + 53%) T where: S and SRB are in percent of RATED THERMAL POWER WY =
Loop recirculation flow as a percentage of the loop recirculation flow which produces a core flow of 100 million Ibs/hr AW =
0.0 for two loop operation; 8.7 for single loop operation. (Note: These values of AW are also valid for the RBM.)
T =
Lowest value of the ratio of FRTP divided by the MFLPD.2 The FLPD is the actual LHGR divided by the applicable. LHGR limit for APRM Setpoints. The LHGR limit for APRM setpoints for ATRIUM -10 fue:
shall be taken from Figure 7.2-1.
The LHGR for APRM setpoint limits in Figure 7.2-1 are valid for Main Turbine Bypass Operable and Inoperable and EOC-RPT Operable and
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For calculated T-values greater than 1.0, a ratio of 1.0 is used in the above equations.
APRM Simulated Thermal Power-High scram allowable value in this table is equal to the value established in Technical Specification 3.3.1.1.
For the calculation of T, he value of MFLPD shall be the maximum value 0:
FDLRC.
SUSQUE.HANNA UNIT 1',
I TRM/3.2-26 EFFECTIVE DATE 03/11/2006
PPL Rev. 6 PL-NF-06-001 Rev. 0 Page 26 of 43 0
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,NNA UNIT 1 TRM/3.2-27 w
I SUSQUEHA EFFECTIVE DATE 03/11/2006
PPL Rev. 6 PL-NF-06-001 Rev. 0 Page 27 of 43 8.0 FRECIRCULATION LOOPS - SINGLE LOOP OPERATION 8.1 Technical Specification Reference Technical Specification 3.2.1, 3.2.2, 3.2.3, 3.2.4, 3.3.4.1, 3.4.1, and 3.7.6 8.2 Description APLHGR 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 and EOC-RPT 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 (ATRIUM'm-1o) shall be the greater of the Flow-Dependent or the Power-Dependent MCPR, i
depending on the applicable equipment operability status.
a)
EOC-RPT and Main Turbine Bypass 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 / EOC-RPT Operable Figure 8.2-4: Flow-Dependent MCPR value determined from BOC to
<EGO Figure 8.2-5: Power-Dependent MCPR value determined from BOC to EQO c)
EOC-RPT Inoperable / Main Turbine Bypass Operable Figure 8.2-6: Flow-Dependent MCPR value determined from BOC to lEOC Figure 8.2-7:! Power-Dependent MCPR value determined from BOC to EOC SUSQUEHANNA UNIT 1:
TRM/3.2-28 EFFECTIVE DATE 03/11/2006 I.S
PPL Rev. 6 PL-NF-06-CO1 Rev. 0 Page 28 of 43 The MCPR limits in Figures 8.2-2 through 8.2-7 are valid only for Single Loop operation.
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I Linear Heat Generation Rate Limit The LHGR limits for Single Loop Operation are defined in Section 6.0.
Average Power Range Monitor (APRM) Gain And Setpoints APRM setpoints and the LHGR limit for APRM setpoints for Single Loop operation are defined in Section 7.0.
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/3.2-37 EFFECTIVE DATE 03/11/2006 SUSQUI:HANNA UNIT 1 TRM
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PPL Rev. 6 PL-NF-06-001 Rev. 0 Page 39 of 43 k.)
9.0 POWER / FLOW MAP 9.1 Technical Specific Technical Specific 9.2 Description cation Reference cation 3.3.1.1 Monitor reactor conditions to maintain THERMAL POWER / core flow outside of Stability Regions I and 11 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.
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1 TRM/3.2-41 EFFECTIVE DATE 03/11/2()06
PPL Rev. 6 PL-NF-06-00 1 Rev. 0 Page 41 of 43
- i1440001, 10.0 OPRM SETPOINTS 10.1 Technical Specification Reference 1
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:
siP 1.11.
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=
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EFFECTIVE DATE 03/11/2006
PPL Rev. 6 PL-NF-06-001 Rev. 0 Page 42 of 43 K,,)
1 1.0 FIEFE 11.1 RENCES 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, "ATRIUMTU1 0: 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 Design and Analysis," Exxon Nuclear Company, March 1983.
- 6. XN-NF-80-19(P)(A), Volumes 2, 2A, 2B, and 2C "Exxon Nuclear Methodolocly for Boiling Water Reactors: EXEIM 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.'
F
- 10. ANF-524(P)(A), Revision 2 and Supplements 1 and 2, "Advanced Nuclear Fuels Corporationi Critical Power Methodology for Boiling Water Reactors,"
November 1990.
l 1. NE-092-001 A, Revision 1, "Licensing Topical Report for Power Uprate With Increased Core Flow!" Pennsylvania Power & Light Company, December 1992 and NRC SER (November 30,1993).
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i SUSQUEHANNA UNIT 1 I
.TRM/3.2-43 EFFECTIVE DATE 03/11/2006
PPL Rev. 6 PL-NF-06-001 Rev. 0 Page 43 of 43
- 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 2, "SPCB Critical Power Correlation," Framatome ANP, September 2003.
- 14. Caldon, Inc., "TOPICAL REPORT: Improving Thermal Power Accuracy and Plant Safety While Increasing Operating Power Level Using the LEFM'm System," Engineering Report - 80P, March 1997.
- 15. Caldon, Inc., uSupplement to Topical Re-port ER-80P: Basis for a Power Uprete with the LEFM' or LEFM CheckPlusT System," Revision 0, Engineering JJu
&LL I-I V
, IVIGLy uu.J
-Jw.
- 16. EMF-85-74(P)(A), Revision 0, Supplement 1(P)(A) and Supplement 2(P)(A'i, "RODEX2A (BWR) Fuel Rod Thermal-Mechanical Evaluation Model,".
Siemens Power Corporation, February 1998.
- 17. 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.
- 18. 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.
- 19. NEDO-32465-A, -BWROG Reactor Core Stability Detect and Suppress Solutions Licensing Basis Methodology for Reload Applications," August 1996.
- 20. ANF-913(P)(A), Volume 1 Revisioni and Volume 1 Supplements 2, 3, and 4, "COTRANSA2: A Computer Program for Boiling Water Reactor Transient Analyses,' Advanced Nuclear Fuels Corporation, August 1 990.
- 21. ANF'1358(P)(A), Revision 3, "The Loss of Feedwater Heating Transient in Boiling-Water Reactors," Framatome ANP, September 2005.
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