ML043370108
| ML043370108 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 11/23/2004 |
| From: | Susquehanna |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| Download: ML043370108 (90) | |
Text
Nov. 23, 2004 Page 1 of 1 MANUAL HARD COPY DISTRIBUTION DOCUMENT TRANSMITTAL 2004-48740 USER INFORMATION/_
Name CH*R E M EMPL#:028401 CA#:0363 Address: N Phone#: 25 3194 TRANSMI AL INFORMATION:
TO:
11/23/2004 LOCATION:
USNRC FROM:
NUCLEAR RECORDS DOCUMENT CONTROL CENTER (NUCSA-2)
THE FOLLOWING CHANGES HAVE OCCURRED TO THE HARDCOPY OR ELECTRONIC MANUAL ASSIGNED TO YOU:
TRM1 -
TECHNICAL REQUIREMENTS MANUAL UNIT 1 REMOVE MANUAL TABLE OF CONTENTS DATE: 11/08/2004
'D MANUAL TABLE OF CONTENTS DATE: 11/22/2004 CATEGORY: DOCUMENTS TYPE: TRM1 ID:
TEXT 2.2 REMOVE:
REV:1 ADD:
REV: 2 CATEGORY: DOCUMENTS TYPE: TRM1 ID:
TEXT 3.2.1 REMOVE:
REV:3 ADD:
REV: 4 CATEGORY: DOCUMENTS TYPE: TRM1 ID:
TEXT 3.3.9 REMOVE:
REV:0 ADD:
REV:
1 CATEGORY:
DOCUMENTS TYPE:
TRM1 ID:
TEXT B3.3.9 REMOVE:
REV:0 ADD:
REV: 1 CATEGORY: DOCUMENTS TYPE: TRM1 ID:
TEXT LOES REMOVE:
REV:9 kj D:
REV: 10 CATEGORY: DOCUMENTS TYPE:
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TEXT TOC REMOVE:
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Nov. 23, 2004 Page 2 of 2 ADD:
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PLEASE MAKE ALL CHANGES AND ACKNOWLEDGE COMPLETE IN YOUR NIMS INBOX UPON RECEIPT OF HARD COPY.
FOR ELECTRONIC MANUAL USERS, ELECTRONICALLY REVIEW THE APPROPRIATE DOCUMENTS AND ACKNOWLEDGE COMPLETE IN YOUR NIMS INBOX.
SSES MANUAL i
Manual Name:
TRM1 ktanual
Title:
TECHNICAL REQUIREMENTS MANUAL UNIT 1 Table Of Contents Issue Date:
11/22/2004 Procedure Name Rev Issue Date Chan TRM1 N/A 08/01/2003
Title:
TECHNICAL REQUIREMENTS MANUAL UNIT 1 (07/28/2003)
LDCN ge ID Change Number 3748 TEXT LOES
Title:
TEXT TOC
Title:
10 11/22/2004 LIST OF EFFECTIVE SECT'l.
- ANb, 3
11/22/2004 TABLE OF CONTENTS TEXT 1.1 0
11/18/2002
Title:
USE AND APPLICATION DEFINITIONS TEXT 2.1
Title:
0 PLANT PROGRAMS AND SETPOINTS TEXT 2.22 2/
112l/2004
Title:
PLANT PROGRAMS AND SETPOINTS INSTRUMENT TRIP SETPOINT TABLE TEXT 3.0 0
11/18/2002
Title:
TECHNICAL REQUIREMENTFOR OPERATION (TRO)
APPLICABILITY & SURVEILLANCE (TRS)
APPLICABILITY.'!
TT 3.1.2
'0 11/18/2002
Title:
REACTIVITY CONTROL SYSTEMS CONTROL ROD DRIVE (CRD)
HOUSING SUPPORT TEXT 3.1.3 0
Title:
REACTIVITY CONTROL SYSTEMS 11/18/2002 CONTROL ROD BLOCK 1..................
INSTRUMENTATION TEXT 3.1.4 0
11/18/2002
Title:
REACTIVITY CONTROL SYSTEMS CONTROL ROD SCRAM ACCUMULATORS INSTRUMENTATION &
CHECK VALVE TEXT 3.2.1 4
11/22/2004
Title:
CORE OPERATING LIMITS REPORT (COLR)
Page 1 of 15 Report Date: 11/22/04 Page I of 15 Report Date: 11/22/04
I I SSES MANUAL Manual Name: TRM1 Manual
Title:
TECHNICAL REQUIREMENTS MANUAL UNIT 1 TEXT 3.3.1 0
11/18/2002
Title:
INSTRUMENTATION RADIATION MONITORING INSTRUMENTATION TEXT 3.3.2 0
11/18/2002
Title:
INSTRUMENTATION SEISMIC MONITORING INSTRUMENTATION TEXT 3.3.3 0
11/18/2002
Title:
INSTRUMENTATION METEOROLOGICAL MONITORING INSTRUMENTATION TEXT 3.3.4
Title:
INSTRUMENTATION TEXT 3.3.5
Title:
INSTRUMENTATION TEXT 3.3.6
Title:
INSTRUMENTATION TEXT 3.3.7
Title:
INSTRUMENTATION TEXT 3.3.8
Title:
INSTRUMENTATION TEXT 3.3.9
Title:
INSTRUMENTATION TEXT 3.3.10
Title:
INSTRUMENTATION 0
11/18/2002 TRM POST-ACCIDENT MONITORING INSTRUMENTATION 0
11/18/2002 THIS PAGE INTENTIONALLY LEFT BLANK 1
10/22/2003 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 0
11/18/2002 REACTOR RECIRCULATION PUMP MG SET STOPS TEXT 3.3.11 1
10/22/2003
Title:
INSTRUMENTATION MVP ISOLATION INSTRUMENTATION TEXT 3.4.1
Title:
11/18/2002 SYSTEM REACTOR COOLANT SYSTEM CHEMISTRY Page 2 of 15 Report Date: 11/22/04
I 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 STRUCTURALiINTEGRITY 0
11/18/2002.
COOLANT SYSTEM HIGH/LOW PRESSURE INTERFACE LEAKAGE MONITORS 0
11/18/2002.
COOLANT SYSTEM REACTOR 'RECIRCULATION FLOW AND ROD LINE LIMIT 0
11/18/2002 COOLANT SYSTEM REACTOR VESSEL MATERIALS 0
11/18/2002
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 15 Report Date: 11/22/04
.Page 3 of 15 Report Date: 11/22/04
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 0
11/18/2002 SYSTEMS ULTIMATE HEAT SINK (UHS)
AND GROUND WATER LEVEL 0
11/18/2002 SYSTEMS FIRE SUPPRESSION WATER SUPPLY SYSTEM 0
11/18/2002 SYSTEMS SPRAY AND SPRINKLER SYSTEMS 0
11/18/2002 SYSTEMS C02 SYSTEMS 0
11/18/2002 SYSTEMS HALON SYSTEMS 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 SYSTEMS 0
11/18/2002 FIRE HOSE STATIONS 0
11/18/2002 SYSTEMS YARD FIRE HYDRANTS AND HYDRANT HOSE HOUSES 0
11/18/2002 SYSTEMS FIRE RATED ASSEMBLIES 1
01/12/2004 SYSTEMS FIRE DETECTION INSTRUMENTATION LDCN 0
11/18/2002 SYSTEMS SOLID RADWASTE SYSTEM 3503 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 MAIN CONDENSER OFFGAS HYDROGEN MONITOR 0
11/18/2002 SYSTEMS MAIN CONDENSER OFFGAS EXPLOSIVE GAS MIXTURE Page 4 of 15 Report Date: 11/22/04 Page 4 of 15 Report Date: 11/22/04
SSES MANUAL
, Manual Name:
TRM1 Manual
Title:
TECHNICAL REQUIREMENTS MANUAL UNIT 1 TEXT 3.7.5.3 0
11/18/2002
Title:
PLANT SYSTEMS LIQUID HOLDUP.TANKS TEXT 3.7.6 0
11/18/2002
Title:
PLANT 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 0
11/18/2002
Title:
PLANT SYSTEMS SNUBBERS TEXT 3.7.9 0
11/18/2002
Title:
PLANT SYSTEMS CONTROL STRUCTURE HVAC-TEXT 3.7.10 0
11/18/2002
Title:
PLANT SYSTEMS SPENT FUEL STORAGE POOLS -(SFSPS)
TEXT 3.8.1 0
11/18/2002
Title:
ELECTRICAL POWER PRIMARY CONTAINMENT PENETRATION CONDUCTOR OVERCURRENT PROTECTIVE DEVICES TEXT 3.8.2.1 0
11/18/2002
Title:
ELECTRICAL POWER MOTOR OPERATED VALVES (MOV)
THERMAL OVERLOAD PROTECTION -
CONTINUOUS TEXT 3.8.2.2 1
09/17/2004
Title:
ELECTRICAL POWER MOTOR OPERATEDXVALVES-(MOV)
THERMAL OVERLOAD PROTECTION AUTOMATIC TEXT 3.8.3 0
11/18/2002:
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 -
Page 5 of 15 Report Date: 11/22/04 Page 5 of 15 Report Date: 11/22/04
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
11/18/2
Title:
REFUELING OPERATIONS DECAY TIME TEXT 3.9.2 0
11/18/2
Title:
REFUELING OPERATIONS COMMUNICATIONS 002 002 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
Title:
MISCELLANEOUS LEADING TEXT 3.11.1.1
Title:
RADIOACTIVE EFFLUENTS TEXT 3.11.1.2
Title:
RADIOACTIVE EFFLUENTS 0
11/18/2002 EDGE FLOW METER (LEFM) 0 11/18/2002 LIQUID EFFLUENTS CONCENTRATION 0
11/18/2002 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 0
11/18/2002 LIQUID RADWASTE EFFLUENT MONITORING INSTRUMENTATION of 15 Report Date: 11/22/04 of 15 Report Date: 11/22/04 '
SSES -MANUAL
' Manual Name:
TRM1 Manual
Title:
TECHNICAL REQUIREMENTS MANUAL UNIT 1 TEXT 3.11.1.5
Title:
RADIOACTIVE EFFLUENTS 0
11/18/2002 RADIOACTIVE LIQUID PROCESS.MONITORING INSTRUMENTATION TEXT 3.11.2.1 1
01/27/2004.
Title:
RADIOACTIVE EFFLUENTS DOSE-.RATE-TEXT 3.11.2.2 0
11/18/2002'
Title:
RADIOACTIVE EFFLUENTS DOSE -
NOBLE GASES TEXT 3.11.2.3
Title:
RADIOACTIVE EFFLUENTS FORM TEXT 3.11.2.4
Title:
RADIOACTIVE EFFLUENTS 0
11/18/2002 DOSE -
IODINE; TRITIUM, AND RADIONUCLIDES IN PARTICULATE 0
11/18/2002 GASEOUS RADWASTE TREATMENT SYSTEM _' '
TEXT 3.11.2.5 k
Title:
RADIOACTIVE EFFLUENTS TEXT 3.11.2.6
Title:
RADIOACTIVE EFFLUENTS 0
11/18/2002 VENTILATION. EXHAUST 1
01/27/2004.
RADIOACTIVE GASEOUS TREATMENT SYSTEM EFFLUENT MONITORING INSTRUMENTATION LDCN 3592 TEXT 3.11.3
Title:
RADIOACTIVE EFFLUENTS TEXT 3.11.4.1 0
11/18/2002' TOTAL DOSE'-.- I.- :
0 11/18/2002
Title:
RADIOACTIVE EFFLUENTS MONITORING PROGRAM.
TEXT 3.11.4.2 0
11/18/2002
Title:
RADIOACTIVE EFFLUENTS LAND USE CENSUS TEXT 3.11.4.3 0
11/18/2002:
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 Page 7 of 15.
Report Date: 11/22/04 Page 7 of 15 Report Date: 11/22/04
SSES MANUAL Manual Name:
TRM1 Manual
Title:
TECHNICAL REQUIREMENTS MANUAL UNIT 1 TEXT 3.12.2 0
11/19/2002
Title:
LOADS CONTROL PROGRAM HEAVY LOADS REQUIREMENTS TEXT 3.12.3 0
11/19/2002
Title:
LOADS CONTROL PROGRAM LIGHT LOADS REQUIREMENT TEXT B3.0 0
11/19/2002
Title:
APPLICABILITY 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 0
11/19/2002
Title:
REACTIVITY CONTROL SYSTEMS BASES CONTROL ROD BLOCK INSTRUMENTATION TEXT B3.1.4 0
11/19/2002
Title:
REACTIVITY CONTROL SYSTEMS BASES CONTROL ROD SCRAM ACCUMULATORS INSTRUMENTATION AND CHECK VALVE TEXT B3.2.1
Title:
CORE OPERATING LIMITS TEXT B3.3.1
Title:
INSTRUMENTATION BASES TEXT B3.3.2
Title:
INSTRUMENTATION BASES TEXT B3.3.3
Title:
INSTRUMENTATION BASES TEXT B3.3.4
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 0
11/19/2002 METEOROLOGICAL MONITORING INSTRUMENTATION 0
11/19/2002 TRM POST ACCIDENT MONITORING (PAM)
INSTRUMENTATION Page 8 of 15 Report Date: 11/22/04 Page 8 of 15 Report Date: 11/22/04
SSES-MANUAL Manual Name:
- TRM, 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 1
10/22/2003'
Title:
INSTRUMENTATION BASES TRM-ISOLATION ACTUATION INSTRUMENTATION TEXT B3.3.7 0
11/19/2002
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
Title:
-INSTRUMENTATION TEXT B3.3.10
Title:
INSTRUMENTATION TEXT B3.3.11
Title:
INSTRUMENTATION 1
11/22/2004 BASES LPRM UPSCALE ALARM INSTRUMENTATION 0
11/19/2002 BASES REACTOR RECIRCULATION PUMP MG SET STOPS 1
10/22/2003 BASES MVP ISOLATION INSTRUMENTATION TEXT B3.4.1
Title:
REACTOR 0
11/19/2002' COOLANT SYSTEM-BASES REACTOR.COOLANT SYSTEM CHEMISTRY TEXT B3.4.2
Title:
REACTOR TEXT B3.4.3
Title:
REACTOR 0
11/19/2002' COOLANT SYSTEM BASES STRUCTURAL INTEGRITY 0
11/19/2002 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
Title:
REACTOR 0
11/19/2002 COOLANT SYSTEM BASES REACTOR VESSEL MATERIALS Page 9 of 15 Report Date: 11/22/04 Page 9 of 15 -_
Report Date: 11/22/04.
SSES MANUAL Manual Name: TRMl Manual
Title:
TECHNICAL REQUIREMENTS MANUAL UNIT 1 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 0
11/19/2002
Title:
CONTAINMENT BASES PRIMARY CONTAINMENT CLOSED SYSTEM BOUNDARIES TEXT B3.7.1
Title:
PLANT TEXT B3.7.2
Title:
PLANT TEXT B3.7.3.1
Title:
PLANT TEXT B3.7.3.2
Title:
PLANT SYSTEMS BASES SYSTEMS BASES SYSTEMS BASES SYSTEMS BASES 0
11/19/2002 EMERGENCY SERVICE WATER SYSTEM (SHUTDOWN) 0 11/19/2002 ULTIMATE HEAT SINK (UHS)
GROUND WATER LEVEL 0
11/19/2002 FIRE SUPPRESSION WATER SUPPLY SYSTEM 0
11/19/2002 SPRAY AND SPRINKLER SYSTEMS TEXT B3.7.3.3
Title:
PLANT SYSTEMS 0
11/19/2002 BASES C02 SYSTEMS Page 10 of 15 Report Date: 11/22/04 Page 10 of 15 Report Date: 11/22/04
SSES MANUAL
, Manual Name:
TRM1 Manual
Title:
TECHNICAL REQUIREMENTS MANUAL UNIT 1 TEXT B3.7.3.4
Title:
PLANT SYSTEMS TEXT B3.7.3.5
Title:
PLANT SYSTEMS TEXT B3.7.3.6
Title:
PLANT SYSTEMS TEXT B3.7.3.7
Title:
PLANT-SYSTEMS TEXT B3.7.3.8
Title:
PLANT SYSTEMS 0
11/19/2002 BASES HALON SYSTEMS 0
11/19/2002
BASES FIRE HOSE STATIONS 0
11/19/2002 BASESYARD'FIRE.HYDRANTS AND HYDRANT HOSE HOUSES 0
11/19/2002 BASES FIRE RATED ASSEMBLIES 1
01/12/2004:
BASES FIRE DETECTION INSTRUMENTATION TEXT B3.7.4 KJ'
Title:
PLANT TEXT B3.7.5.1
Title:
PLANT TEXT B3.7.5.2
Title:
PLANT TEXT B3.7.5.3
Title:
PLANT TEXT B3.7.6
Title:
PLANT SYSTEMS BASES SYSTEMS BASES SYSTEMS BASES SYSTEMS BASES SYSTEMS BASES 0
11/19/2002' SOLID RADWASTE SYSTEM 0
11/19/2002 MAIN CONDENSER OFFGAS HYDROGEN MONITOR 0
11/19/2002-'
MAIN CONDENSER OFFGAS EXPLOSIVE GAS MIXTURE 0
11/19/2002 LIQUID HOLDUP-TANKS 0
11/19/2002 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 0
11/19/2002
Title:
PLANT SYSTEMS BASES SNUBBERS -
Page 11 of 15 Report Date: 11/22/04 Page 11 of 15 Report Date: 11/22/04
SSES MANUAL Manual Name:
TRM1 Manual
Title:
TECHNICAL REQUIREMENTS MANUAL UNIT 1 TEXT B3.7.9
Title:
PLANT SYSTE TEXT B3.7.10
Title:
PLANT SYSTE TEXT B3.8.1
Title:
ELECTRICAL PROTECTIVE MS 0
11/19/2002 BASES CONTROL STRUCTURE HVAC 0
11/19/2002 MS BASES SPENT FUEL STORAGE POOLS 0
11/19/2002 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 0
11/19/2002 POWER BASES EMERGENCY SWITCHGEAR ROOM COOLING 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 Page 12 of 15 Report Date: 11/22/04 Page 12 of 15 Report Date: 11/22/04
SSES -MANUAL
, Manual Name:
TRM1 manual
Title:
TECHNICAL REQUIREMENTS MANUAL UNIT 1 TEXT B3.10.1 0
11/19/2002r
Title:
MISCELLANEOUS BASES SEALED SOURCE CONTAMINATION TEXT B3.10.2
Title:
MISCELLANEOUS TEXT B3.10.3
Title:
MISCELLANEOUS 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 0
11/19/2002
Title:
MISCELLANEOUS BASES LEADING EDGE FLOW METER (LEFM)
TEXT B3.11.1.1
Title:
RADIOACTIVE EFFLUENTS TEXT B3.11.1.2 V_
Title:
RADIOACTIVE EFFLUENTS 0
11/19/2002 BASES LIQUID EFFLUENTS CONCENTRATION 0
11/19/2002-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
Title:
RADIOACTIVE EFFLUENTS INSTRUMENTATION TEXT B3.11.2.1 0
11/19/2002:-
BASES RADIOACTIVE LIQUID PROCESS MONITORING 0
11/19/2002.
Title:
RADIOACTIVE EFFLUENTS BASES DOSE RATE TEXT B3.11.2.2 0
11/19/2002
Title:
RADIOACTIVE EFFLUENTS BASES DOSE -
NOBLE 'GASES TEXT B3.11.2.3 0
11/19/2002
Title:
RADIOACTIVE EFFLUENTS BASES:DOSE:- IODINE, TRITIUM, AND RADIONUCLIDES IN PARTICULATES FORM Page.13 of 15 Report Date: 11/22/04 Page.13 of 15 Report Date: 11/22/04-
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 TEXT B3.11.4.1
Title:
RADIOACTIVE EFFLUENTS TEXT B3.11.4.2
Title:
RADIOACTIVE EFFLUENTS TEXT B3.11.4.3
Title:
RADIOACTIVE EFFLUENTS TEXT B3.12.1
Title:
LOADS CONTROL PROGRAM TEXT B3.12.2
Title:
LOADS CONTROL PROGRAM TEXT B3.12.3
Title:
LOADS CONTROL PROGRAM TEXT 4.1 0
11/19/2002 BASES GASEOUS RADWASTE TREATMENT SYSTEM 2
10/27/2004 BASES VENTILATION EXHAUST TREATMENT SYSTEM 1
01/27/2004 BASES RADIOACTIVE GASEOUS EFFLUENT MONITORING LDCN 3592 0
11/19/2002 BASES TOTAL DOSE 0
11/19/2002 BASES MONITORING PROGRAM 0
11/19/2002 BASES LAND USE CENSUS 0
11/19/2002 BASES INTERLABORATORY COMPARISON PROGRAM 0
11/19/2002 BASES CRANE TRAVEL-SPENT FUEL STORAGE POOL 0
11/19/2002 BASES HEAVY LOADS REQUIREMENTS 0
11/19/2002 BASES LIGHT LOADS REQUIREMENTS 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: 11/22/04 Page 14 of 15 Report Date: 11/22/04
SSES MANUAL
, 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 ADMINISTRATIVE ADMINISTRATIVE ADMINISTRATIVE o
08/31/1998 CONTROLS SAFETY LIMIT VIOLATION o
08/31/1998 CONTROLS PROCEDURES & PROGRAMS 0
08/31/1998 CONTROLS REPORTING REQUIREMENTS o
08/31/1998 CONTROLS RADIATION PROTECTION PROGRAM 0
08/31/1998 CONTROLS TRAINING Page 15 of 15 Report Date: 11/22/04 Page 15 of 15 Report Date: 11/22/04
SUSQUEHANNA STEAM ELECTRIC STATION UST OF EFFECTIVE SECTIONS (TECHNICAL REQUIREMENTS PPL Rev. 10 MANUAL)
Section Title Effective Date TOC TABLE OF CONTENTS' 11/15/2004 I
1.0
. 2.0 3.0 USE AND APPLICATION '
Pages TRM /1.0-1 through TRM /-1.0-3 10/04/2002 PLANT PROGRAMS Pages 2.0-1 through 2.0-2 Page TRM /2.0-3 Page TRM /2.0-4 Page TRM / 2.0-5 Pages TRM /2.0-6 through TRM 12.;0-14 APPLICABILITY Pages TRM / 3.0-1 and TRM I 3.0-2 Pages TRM / 3.0-3 Page TRM / 3.0-4 08/31/1998 08/01/2001 06/25/2002 04/02/1999 11/12/2004 I
K 3.1 REACTIVITY CONTROL SYSTE S' l'
Pages 3.1-1 through 3.1-6 (K>\\
K Pages TRM / 3.1-7 and TRM,03.1-8 Pages TRM / 3.1-9 and, T113. -9a' Page TRM /3.1-10/'
0-3.2 CORE OPERATINGLIMITS REPORT Page TRM / 3.2-1 Pages TRM7 3;2:2 through TRM / 3.2-38 3.3 INSTRUMENTATION
Pages TRM'l J3.3-1 through TRM / 3.3-3 POgeTRM/,3.3-4 Pages3.3-5 through 3.3-8
\\pages TRM / 3.3-9 and TRM / 3.3-9a Pages TRM / 3.3-10 'and TRM / 3.3-11 Page TRM / 3.3-12 Pages TRM / 3.3-13 and TRM / 3.3-14 Page'TRM / 3.3-15 Page TRM / 3.3-16 Pages TRM 13.3-17 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 Pages TRM / 3;3-23 through TRM / 3.3-25 Page TRM / 3.3-26 04/08/1999 03/15/2002 04/08/1999 08/31/1998 I06/05/2002 02/18/1999
- 02/18/1999 07/07/1999 11/12/2004 I
07/1611999 11/2812000 08/31/1998 12/17/1998 12/17/1998 03/30/2001 12/14/1998 1 0122/2003 06127/2001 06/1412002 10122/2003 1 1/12/2004 11/1212004 05/1612003 1 0/22/2003 SUSQUEHANNA - UNIT 1
.TRM / LOES-1 I
EFFECTIVE DATE 11/15/2004
SUSQUEHANNA STEAM ELECTRIC STATION PPL LIST OF EFFECTIVE SECTIONS (TECHNICAL REQUIREMENTS MANUAL)
Rev. 10 Section Title Effective Date 3.4 3.5' 3.6 3.7 3.8 REACTOR COOLANT SYSTEM Pages 3.4-1 through 3.4-5 Pages 3.4-6 through 3.4-13 EMERGENCY CORE COOLING AND RCIC Pages 3.5-1 through 3.5-3, Page TRM /3.5-4 Pages 3.5-5 through 3.5-7
- 1 0/23/1998 08/31/1998 08/31/1998 04/17/2000 08/31/1998 CONTAINMENT Pages 3.6-1 through 3.6-3 Page TRM 13.6-4 Page 3.6-5 Pages TRM 13.6-6 through TRM i 3.6-8 PLANT SYSTEMS Pages 3.7-1 through 3.7-3 Pages TRM I 3.7-4 through TRM / 3.7-10 PageTRM /3.7-11 Pages TRM /3.7-12 through TRM / 3.7-27 Pages TRM I 3.7-28 through TRM / 3.7-32 Page TRM /3.7-33 Page TRM /3.7-34 Page TRM I 3.7-34a Pages TRM /3.7-35 through TRM 13.7-37 Pages 3.7-38 through 3.7-40 Pages TRM /3.7-41 and TRM /3.7-41 a Pages 3.7-42 and 3.7-43 Pages 3.7-44 through 3.7-48 Page TRM 3.7-49
- Pages TRM / 3.7-50 and TRM 13.7-51 Pages TRM 13.7-52 and TRM 13.7-53 Page TRM / 3.7-54 08/31/1998 01/07/2002 08/31/1998 12/31/2002 08/31/1998 08/02/1999 12/2911999 08/02/1999 11/16/2001 0110912004 11/16/2001 10/05/2002 02/01/1999 08/31/1998 08/11/2000 08/31/1998 10/13/1998 03108/2003 03/09/2001 04115/2003 07/29/1999 ELECTRICAL POWER Pages'TRM / 3.8-1 and TRM / 3.8-2 Page 3.8-3 Page TRM / 3:8-4 Pages TRM I 3.8-5 and TRM I 3.8-6 Pages TRM I 3.8-7 through TRM 13.8-9 Page TRM / 3.8-10.
Page TRM / 3.8-11 Pages 3.8-12 through 3.8-14 Pages TRM /3.8-15 through TRM /3.8-17 04/02/2002 08131/1998 12/3112002 04/02/2002 08/31/1998 07/19/2001 08/10/2004 08/31/1998 04/02/2002 SUSQUEHANNA - UNIT 1 TRM / LOES-2 EFFECTIVE DATE 11/15/2004
SUSQUEHANNA STEAM ELECTRIC STATION PPL Rev. 10 USTOFEFFECTIVESECTIONS (TECHNICAL REQUIREMENTS MANUAL)
Section Title Effective Date 3.9 3.10 3.11 Page 3.8-18 Page TRM / 3.8-19 Page 3.8-20 Pages TRM / 3.8-21 through TRM I 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 Page TRM/3.10-6 Page TRM / 3.10-7 Page TRM /3.10-8 RADIOACTIVE EFFLUENTS Pages 3.11-1 through 3.11-12 Pages 3.11-13 through 3.11-16 Pages 3.11-17 and 3.11-18 Page TRM /3.11-19 ' - -
Pages 3.11-20 and 3.11-21 Pages TRM / 3.11-22 through TRM /3.11-24 Page 3.11-25 Pages TRM /3.11-26 through TRM /3.11-32 Pages 3.11-33 through 3.11-47 LOADS CONTROL PROGRAM Pages TRM /3.12-1 throughTRM /3.12-5 ADMINISTRATIVE CONTROLS Pages 4.0-1 through 4.0-8 08/31/1998 04/02/2002 08/31/1998 06/0611999 08/31/1998
.08/31/1998 08/31/1998 03/0812003
- 06/05/2002 04/07/2000 Corrected 04/17/2002 I.
I I
08/31/1998
-09/01/1998 08/31/1998 01/2112004 08/31/1998 04/02/2002
- 09/01/1998 01/21/2004 08/31/1998 3.12 4.0 02105/1999 i,0
/
08131/11998 I
.~ ~
-SUSQUEHANNA - UNIT 1.
-TRM / LOES-3 EFFECTIVE DATE 11/15/2004
StIRMIFHANNARTFAM FLFCTRICIRTATION PPL Re.v-10 UST OF EFFECTIVE SECTIONS (TECHNICAL REQUIREMENTS MANUAL)
- Section B3.0 B3.1
'B3.2 Title APPLICABILITY BASES Pages B 3.0-1 through B 3.0-10 Pages TRM / B 3.0-11 through TRM I B 3.0-15 REACTIVITY CONTROL SYSTEMS BASES Pages TRM B 3.1-1 through TRM I B 3.1-3 Page B3.1-4 Pages TRM / B 3.1-5 through TRM I B 3.1-7 Page TRM I B 3.1-8 CORE OPERATING LIMITS BASES Page B 3.2-1 B 3.3 INSTRUMENTATION BASES, Page TRM I B 3.3-1 Page B 3.3-2 Pages TRM I B 3.3-3 and TRM B 3.3-3A Pages TRM I B 3.3-4 through TRM / B 3.3-6 Pages TRM / B 3.3-7 through TRM / B 3.3-9 Pages B 3.3-10 through 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 I B 3.3-17f Pages TRM / B3.3-18 and TRM I B 3.3-19 Page TRM I B 3.3-20 Page'TRM / B 3.3-21 B 3.4 REACTOR COOLANT SYSTEM BASES Pages B 3.4-1 through B 3.4-4 Page TRM / B 3.4-5' Page B 3.4-6 Effective Date 08131/1998 03/15/2002 07/13/1999-08/31/1998 07/13/1999 02/18/1999 08/31/1998 04/07/2000 0813111998 12/29/2000 03/21/2003 03/30/2001 08/31/1998 10/22/2003 06/25/2002 06/14/2002 06/14/2002 10/22/2003 11/12/2004 11/12/2004 05/16/2003 10/22/2003 05/16/2003 08/31/1998 10/15/1 999 08/31/1998 08/31/1998 07/26/2001 02/01/1999 08/31/1998 09/23/1999 i
B 3.5 B3.6 ECCS AND RCIC BASES Pages B 3.5-1 through B 3.5-5 CONTAINMENT BASES Page TRM / B 3.6-1 Page TRM / B 3.6-2 Page B 3.6-3 Page TRM / B 3.6-4 SUSQUEHANNA - UNIT I
'. TRM / LOES-4 EFFECTIVE DATE 11/15/2004
SUSQUEHANNA STEAM ELECTRIC STATION PPL Rev. 10 UST OF EFFECTIVE SECTIONS (TECHNICAL REQUIREMENTS MANUAL)
Section Title Effective Date Page TRM / B 3.6-5 Pages TRM / B 3.6-6 throughTRM / B 3.6-11 B 3.7 PLANT SYSTEMS BASES Pages B 3.7-1 and B 3.7-2 Pages TRM / B 3.7-3 through TRM / B 3.7-7 Page TRM / B 3.7-7a Pages TRM / B 3.7-8 through TRM / B 3.7-10 Page TRM / B 3.7-10a Pages TRM / B 3.7-11 and TRM i B 3.7-11 a Pages TRM / B 3.7-12 through TRM I B 3.7-14 Page TRM / B 3.7-14a Page TRM / B 3.7-14b Pages TRM / B 3.7-15 and TRM / B 3.7-16 Pages B 3.7-17 through B 3.7-20 Page TRM/B 3.7-21 through TRM/B 3.7-21a
- Pages TRMIB 3.7-22 and TRM/B 3.7-23 Pages B 3.7-24 through B 3.7-30
- Pages TRM / B 3.7-31 and TRM / B 3.7-32 Page TRM / B 3.7-33 Pages TRM B 3.7-34 and TRM B 3.7-35 B 3.8 ELECTRICAL POWER BASES Pages TRM / B 3.8-1 and TRM / B 3.8-2
'Page TRM B 3.8-2a Page TRM / B 3.8-3 Page TRM / B 3.8-3a Page TRM 1 B 3.8-4' Page TRM I B 3.8-4a Page TRM / B 3.8-5 Pages TRM /B 3.8-6 through TRM / B 3.8-17 B.3.9 REFUELING OPERATIONS BASES Pages B 3.9-1 through B 3.9-7 01/07/2002 12/31/2002 08/31/1998 08102/1999 08/02/1999 08/02/1999 08/02/1999 08/02/1999 08/02/1999 08/02/1999 01/09/2004 02/01/1999 08/31/1998 05/11/2001 04/0712000 08/31/1998 03/09/2001 04/15i2003 07/05/2000 04/02/2002 04/02/2002 04/02/2002 04/02/2002 08/10/2004 04/02/2002 08131/1998 04/0212002 08/31/1998 08/31/1998 03/08/2003 08/23/1999 04/17/2002 08/30/1998 02/01/1999 04/07/2000 B 3.10 MISCELLANEOUS BASES Pages B 3.10-1 through B 3.10-2 PageTRM/B3.10-3 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 311 I RADIOACTIVE EFFLUENTS BASES Pages B 3.11-1 through B3.11-9 PageTRM/B3.11-10 Pages TRM/B 3.11-11 and TRM/B 3.11-1 1a SUSQUEHANNA - UNIT 1 -
-.TRM / LOES-5 EFFECTIVE DATE 11/15/2004
SUSQUEHANNA STEAM ELECTRIC STATION PPL Rev. 10 UST OF EFFECTIVE SEC77ONS (TECHNICAL REQUIREMENTS MANUAL)
Section Title 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 /B3.11-20a Page TRM / B 3.11-21 Page TRM / B 3.11-22 PageTRM/B3.11-23 Page TRM / B 3.11-23a Pages TRM / B 3.11-24 and TRM /B 3.11-25 Pages B 3.11-26 through B 3.11-35 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*
02/01/1999 11/01/1999 02/01/1999 08/30/1998 04/0212002 04/02/2002 10115/2004 09/26/2003 04/0212002 04/02/2002 01/21/2004 08/30/1998 02112/1999 02/05/1999 TRM1 te4 LOES 11111/04
, i I
SUSQUEHANNA - UNIT 1
- TRM / LOES-6 QEFFECTIVE DATE 11/15/2004
SUSQUEHANNA STEAM ELECTRIC STATION TABLE OF CONTENTS (TECHNICAL REQUIREMENTS MANUAL)
I PPL Rev. 3 SECTION.
TITLE PAGE 1.0 1.1 2.0 2.1 2.2 3.0 3.0 3.0 3.1 3.1.1 3.1.2 3.1.3 3.1.4 3.2 3.2.1 3.3 3.3.1 3.3.2 3.3.3 3.3.4 3.3.5 3.3.6 3.3.7 3.3.8 3.3.9 3.3.10 3.3.11 3.4 3.4.1 3.4.2 3.4.3 3.4.4 3.4.5 USE AND APPLICATION................
TRM/1.0-1 Definitions.TRM/1.0-2 PLANT PROGRAMS 2.0-1 Plant Programs.........
2.0-1 Instrument Trip Setpoint Table..............................
TRM/2.0-5 APPLICABILITY..........
...... TRM/3.01 TRO) - TR for Operation (TRO) Applicability.................................. :.TRM/3.0-1 (TRS) - TR Surveillance (TRS) Applicability.................................. '.TRM/3.0-3 REACTIVITY CONTROL SYSTEMS........
3.1-1.'
Alternate Rod Injection.
3.1-1 CRD Housing Support.
3.1-4 Control Rod Block Instrumentation.3.1-5 Control Rod Scram Accumulators Instrumentation and Check Valve...........
TRM/3.1-9 CORE OPERATING LIMITS REPORT....................................
TRM/3.2-1 Core Operating Limits Report....................................
TRM/3.2-1 INSTRUMENTATION.............
TRM/3.3-1 Radiation Monitoring.Instrumentation........
TRM/3.3-1 Seismic Monitoring Instrumentation.TRM/3.3-4 Meteorological Monitoring Instrumentation.3.3-7 TRM Post-Accident Monitoring Instrumentation................................ TRM/3.3-9 Section Not Used................................
TRM/3.3-12 TRM Containment Isolation Instrumentation.
TRM'3.3-13 Turbine Overspeed Protection System.TRMI3.3-17 Section Not Used..........
TRM/3.3-19 OPRM Instrumentation.......
TRi/3.3-22 Reactor Recirculation Pump MG Set Electrical and Mechanical Stops.......................
TRM/3.3-23 MVP Isolation Instrumentation.TRM13.3-25 REACTOR COOLANT SYSTEM...
3.4-1 Reactor Coolant System Chemistry........................
3.4-1 Structural Integrity..................................
.3.44 6
High/Low Pressure Interface Leakage Monitors 3.4-9 Reactor Recirculation Flow and Rod Line Limit........................
......... 3.4-12 Reactor Vessel Material Surveillances Program.
3.4-13 i
I J
I 3-SUSQUEF-IANNA
- UNIT I TRM/TOC-1 EFFECTIVE DATE 11/1512004 SUSQUEHANNA - UNIT 1
. TRM / TOC-1 I
EFFECTIVE DATFi 11/15/2004
SUSQUEHANNA STEAM ELECTRIC STATION TABLE OF CONTENTS (TECHNICAL REQUIREMENTS MANUAL)
PPL Rev. 3 7,
I i
SECTION 3.5 3.5.1 3.5.2 3.5.3 3.6 3.6.1 3.6.2 3.6.3 3.6.4 3.7 TITLE PAGE EMERGENCY CORE COOLING AND RCIC
......................... 3.5-1 ADS Manual Inhibit.3.5-1 ECCS and RCIC System Monitoring Instrumentation................................. 3.5-3 Long Term Nitrogen Supply to ADS.3..-
CONTAINMENT........
.. 3.6-1 VENTING or PURGING..
3.6-1 Suppression Chamber-to-Drywell Vacuum Breaker Position Indication....
3.6-2 Suppression Pool Alarm Instrumentation.
3.6-3 Primary Containment Closed System Boundaries.......
TRM/3.6-6 PLANT SYSTEMS...........
3.7-1 3.7.1 3.7.2 3.7.3.1 3.7.3.2 3.7.3.3 3.7.3.4 3.7.3.5 3.7.3.6 3.7.3.7 3.7.3.8 3.7.4 3.7.5.1 3.7.5.2 3.7.5.3 3.7.6 3.7.7 3.7.8 3.7.9 3.7.10 Emergency Service Water System (Shutdown).................................-.
- .3.7-1 Ultimate Heat Sink and Ground WaterLevel.
.3.7-3 Fire Suppression Water Supply System
......... TRM/3.7-4 Spray and Sprinkler Systems.TRM/3.7-8 C02 systems.TRM/3.7-12 Halon Systems.......
.... TRM/3.7-16 Fire Hose Stations.....................I...................8 Yard Fire Hydrants and Hydrant Hose Houses................................... TRM13.7-22 Fire Rated Assemblies.................
TRM/3.7-24 Fire Detection Instrumentation.TRM/3.7-26 Solid Radwaste System...................
TRM/3.7-35 Main Condenser Offgas Hydrogen Monitor.3.7-38 Main Condenser Explosive Gas Mixture............................
.. 3.7-39 Liquid Holdup Tanks.............
3.7-40 ESSW Pumphouse Ventilation.TRM!3.7-41 Main Condenser Offgas Pretreatment Logarithmic Radiation Monitoring Instrumentation.........................................................................3.7-42 Snubbers.
3.7-44 Control Structure HVAC.TRM/3.7-50 Spent Fuel Storage Poois.TRM/3.7-52 SUSQUEHANNA - UNIT I TRM I TOC-2 EFFECTIVE DATE 11/1512004 SUSQUEHANNA - UNIT I
TRM / TOC-2 I EFFECTIVE DATE 11/15/2004
SUSQUEHANNA STEAM ELECTRIC STATION TABLE OF CONTENTS (TECHNICAL REQUIREMENTS MANUAL)
PPL Rev. 3
=
SECTION PAGE TITLE 3.8 ELECTRICAL POWER TRM13.8-1 3.8.1 Primary Containment Penetration Conductor Overcuirent Protective Devices.
TRM/3.8-1 3.8.2.1 Motor Operated Valves Thermal Overload Protection -
Continuous......
TRM/3.8-5 3.8.2.2
-Motor Operated Valves Thermal Overload Protection -
Automatic...................................
TRM/3.8-11 3.8.3.
Diesel Generator (DG) Maintenance Activities.
................................. 3.8-13 3.8.4 24VDC Electrical PowerSubsystem.................................. TRM/3.8-15 3.8.5 Degraded Voltage Protection..................................
- TRM/3.8-21 3.8.6 Emergency Switchgear Room Cooling.
3.8-24 3.9 REFUELING OPERATIONS.3.9-1 3.9.1 Decay Time.............
3.9-1 3.9.2 Communications.............
3.9-2 3.9.3 Refueling Platform.............
3.9-3 I
i
'3.10 3.10.1 3.10.2 3.10.3 I.
3.10.4 MISCELLANEOUS.....................
3.10-1 Sealed Source Contamination 3.10-1 MODE 5 Shutdown Margin Test RPS Instrumentation
.3.10-4 Independent Spent Fuel Storage Installation (ISFSI)
- .......... TRM/3.10-7 Leading Edge Flow Meter (LEFM)
..................... TRM/3.10-8 3.11 3.11.1.1 3.11.1.2 3.11.1.3 3.11.1.4 3.11.1.5 3.11.2.1 3.11.2.2 3.11.2.3 3.11.2.4 3.11.2.5 3.11.2.6 3.11.3 3.11.4.1 3.11.4.2 3.11.4.3 RADIOACTIVE EFFLUENTS 3.11-1 Liquid Effluents Concentration 3.11-1 Liquid Effluents Dose.
3.11-4 Liquid Waste Treatment System 3.11-6 Liquid Radwaste Effluent Monitoring Instrumentation
.3.11-8 Radioactive Liquid Process Monitoring Instrumentation
.3.11-13 Dose Rate
- .u.... 3.11-17 Dose - Noble Gases...
3.11-20 Dose Iodine, Tritium, and Radionuclides in Particulate Form 3.11-21 Gaseous Radwaste Treatment System........
.................... TRM/3.11-22 Ventilation Exhaust Treatment System............................
TRM/3.11-23 Radioactive Gaseous Effluent Monitoring Instrumentation.............................
3.11-25 Total Dose............................
3.11-33 Monitoring Program............
3.11-35 Land Use Census..........................
3.11-45 Interlaboratory Comparison Program.........................
3.11-47 SUSQUEHANNA - UNIT I
- ' TRM / TOC-3
.EFFECTIVE DATE 11/15/2004 I
SUSQUEHANNA STEAM ELECTRIC STATION TABLE OF CONTENTS (TECHNICAL REQUIREMENTS MANUAL).
I
- I PPL Rev. 3 SECTION.
TITLE PAGE 3.12 LOADS CONTROL PROGRAM...........................
TRM/3.12-1 3.12.1 Crane Travel - Spent Fuel Storage Pool...........................
TRM/3.12-1 3.12.2 Heavy Loads Requirements...........................
TRM/3.12-3 3.12.3 Light Loads Requirements............................. ;.TRM/3.12-5 4.0 ADMINISTRATIVE CONTROLS...........
........... 4.0-1 4.1 Organization................................4...................................................................4.01 4.2 Reportable Event Action.................
4.02 4.3 Safety Limit Violation.
4.0-3 4.4 Procedures and Programs................
4.0-4 4.5 Reporting Requirements................
4.0-5 4.6 Radiation Protection Program
............... 4.0-7 4.7 Training............................................................................................................4.0-8 SUSQUEHANNA-UNIT I TRM/TOC-4 EFFECTIVE DATE 11/1512004 SUSQUEHANNA -UNIT 1
.TRM
/ TOC-4 EFFECTIVE DATEA 11/15/2004
SUSQUEHANNA STEAM ELECTRIC STATION TABLE OF CONTENTS (TECHNICAL REQUIREMENTS MANUAL)
PPL Rev. 3 SECTION B3.0 B 3.0 B3.0 B 3.1.1 B 3.1.2 B 3.1.3 B 3.1.4 TITLE PAGE Applicability.........................................
B 3.0-1 (TRO) - TR for Operation (TRO) Applicability.B 3.0-1
-(TRS) - TR Surveillance '(TRS) Applicability.B 3.0-9 Alternate Rod Injection.................
TRMIB 3.1-1 CRD Housing Support.
TRM/B 3.1-4 Control Rod Block Instrumentation.................
TRMJB 3.1-5 Control Rod Scram Accumulators Instrumentation and Check Valve.................................
TRMIB 3.1-8 i
I B 3.2.1 Core Operating Limits Report (COLR).
B 3.2-1 B 3.3.1
.Radiation Monitoring Instrumentation.TRMIB 3.3-1 B 3.3.2 Seismic Monitoring Instrumentation.B 3.3-2 B 3.3.3 Meteorological Monitoring Instrumentation.TRMB 3.3-3 B 3.3.4 TRM Post-Accident Monitoring Instrumentation.......
TRM/B 3.3-4.
B 3.3.5 Section Not Used...............................
TRM/B 3.3-7 B 3.3.6 TRM Containment Isolation Instrumentation..............................
B 3.3-10 B 3.3.7 Turbine Overspeed Protection System..............................
TRM/B 3.3-14 B 3.3.8 Section Not Used............
' TRM/B 3.3-15 B 3.3.9 OPRM Instrumentation.TRM/B 3.3-17 B 3.3.10 Reactor Recirculation Pump MG Set Electrical and Mechanical Stops..........
.TRMIB 3.3-18 B 3.3.11 MVP Isolation Instrumentation..................................
TRM/B 3.3-20 B 3.4.1 Reactor Coolant System Chemistry.................................
B 3.4-1 B 3.4.2 Structural Integrity.................................
B 3.4-2 B 3.4.3 High/Low Pressure Interface Leakage Monitors..................................
3.4-4 B 3.4.4 Reactor Recirculation Flow and Rod Line Limit................................. TRM'B 3.4-5 B 3.4.5 Reactor Vessel Material Surveillances Program.................................
B 3.4-6 I '
- B 3.5.1 B 3.5.2 B 3.5.3 ADS Manual Inhibit............
B 3.5-1 ECCS and RCIC System Monitoring Instrumentation...................................
B 3.5-3 Long Term Nitrogen Supply to ADS....
B 3.5-4
- C,
'3 I1' SUSQUEHANNA - UNIT 1 I TRM / TOC-5 EFFECTIVE DATE 11/15/2004
SUSQUEHANNA STEAM ELECTRIC STATION TABLE OF CONTENTS (TECHNICAL REQUIREMENTS MANUAL)
PPL Rev. 3 I-)
- TITLE PAGE SECTION B 3.6.1 B 3.6.2 B 3.6.3 B 3.6.4 B 3.7.1 B 3.7.2 B 3.7.3.1 B 3.7.3.2 B 3.7.3.3 B 3.7.3.4 B 3.7.3.5 B 3.7.3.6 B 3.7.3.7 B 3.7.3.8 B 3.7.4 B 3.7.5.1 B 3.7.5.2 B 3.7.5.3 B 3.7.6 B 3.7.7 B 3.7.8 B 3.7.9 VENTING or PURGING.
TRM/B 3.6-1 Suppression Chamber-to-Drywell Vacuum Breaker Position Indication........................................
B 3.6-3 Suppression Pool Alarm Instrumentation.......................................... TRM/B 3.6-4 Primary Containment Closed System Boundaries............................. TRM/B 3.6-6 Emergency Service Water System (Shutdown).......................................... B 3.7-1 Ultimate Heat Sink and Ground Water Level............
B 3.7-2 Fire Suppression Water Supply System...........................
TRM/B 3.7-3 Spray and Sprinkler Systems............................
' :. TRM/B 3.7-5 C02 systems.........
TRM/B 3.7-7 Halon Systems..........
.TRM/B 3.7-8 Fire Hose Stations...........
TRM/B 3.7-10 Yard Fire Hydrants and Hydrant Hose Houses................................ TRM1B 3.7-11 Fire Rated Assemblies................................
TRM/B 3.7-12 Fire Detection Instrumentation....................
TRM/B 3.7-14 Solid Radwaste System....................
TRM/B 3.7-15 Main Condenser Offgas Hydrogen Monitor.............................
B 3.7-17 Main Condenser Explosive Gas Mixture...........................
B 3.7-19 Liquid Holdup Tanks.........
B 3.7-20 ESSW Pumphouse Ventilation............................................
TRM/B 3.7-21 Main Condenser Offgas Pretreatment Logarithmic Radiation Monitoring Instrumentation....................
TRM/B 3.7-22 Snubbers....
B 3.7-24 Control Structure HVAC..................
TRM/B 3.7-31 B 3.7.10 Spent Fuel Storage Pools.
TRM/B 3.7-33
-B 3.8.1 Primary Containment Penetration Conductor Overcurrent Protective Devices.......
TRM1B 3.8-1 B 3.8.2.1 Motor Operated Valves Thermal Overload Protection -
Continuous......
TRM/B 3.8-3 B 3.8.2.2 Motor Operated Valves Thermal Overload Protection -
Automatic.................................
TRMWB 3.8-4 B 3.8.3 Diesel Generator (DG) Maintenance Activities................
................ B 3.8-5 B 3.8.4 24VDC Electrical Power Subsystem................................
B 3.8-6 B 3.8.5 Degraded Voltage Protection................................
TRM/B 3.8-16 B 3.8.6 Emergency Switchgear Room Cooling.............
................... TRM/B 3.8-17 B.3.9.1 B 3.9.2 Decay Time...
B 3.9-1 Communications B 3.9-2
-1
, i SU Q E A N -
N T IT M I T C-F E T V A E 1 / 5 2 0
. SUSQUEHANNA-UNIT1 I
. TRM I TOC-6 I EFFECTIVE DATE 11/15/2004
SUSQUEHANNA STEAM ELECTRIC STATION TABLE OF CONTENTS (TECHNICAL REQUIREMENTS MANUAL)
PPL Rev. 3
-I TITLE SECTION B 3.9.3 B 3.10.1 B 3.10.2 B 3.10.3 B 3.10.4 B 3.11.1.1 B 3.11.1.2 B 3.11.1.3 B 3.11.1.4 B 3.11.1.5 B 3.11.2.1 B 3.11.2.2 B 3.11.2.3 B 3.11.2.4 B 3.11.2.5 B 3.11.2.6 B 3.11.3 B 3.11.4.1 B 3.11.4.2 B 3.11.4.3 B.3.12.1 B.3.12.2 B.3.12.3 PAGE Refueling Platform...........
B 3.9-3 Sealed Source Contamination.
B 3.10-1 MODE 5 Shutdown Margin Test RPS Instrumentation...
B 3.10-2 Independent Spent Fuel Storage Installation (ISFSI).......................... TRM/B 3.10-4 Leading Edge Flow Meter (LEFM).TRM/B 3.10-6 Liquid Effluents Concentration.B 3.11-1 Liquid Effluents Dose..............
B 3.11-4 Liquid Waste Treatment System.........
B 3.11-6 Liquid Radwaste Effluent Monitoring Instrumentation.........
B 3.11-7 Radioactive Liquid Process Monitoring Instrumentation.........
TRM/B 3.11-10 Dose Rate......
TRM/B 3.11-12 Dose - Noble Gases.....
B 3.11-16 Dose - Iodine, Tritium, and Radionuclides in Particulate Form...........................
B 3.11-18 Gaseous Radwaste Treatment System.TRM/B 3.11-20 Ventilation Exhaust Treatment System.TRM/B 3.11-21 i Radioactive Gaseous Effluent Monitoring Instrumentation............
TRM/B 3.11-24 Total Dose.............
B 3.11-26 Monitoring Program............
B 3.11-28 Land Use Census.................
B 3.11-34 Interlaboratory Comparison Program.........
.................. TRM/B 3.11-36 Crane Travel - Spent Fuel Storage Pool........
TRM/B 3.12-1 Heavy Loads'Requirements.
TRM/B 3.12-2 Light Loads Requirements.
TRM/B 3.12-3 TRM1 text TOC 111ii104 SUSQUEHANNA-UNIT1
- TRM / TOC-7A TEFFECTIVE DATE 11/15/2004
F
)- 2 Instrument Trip Setpoint Program
'PL Rev. 2 2.2 W
PLANT PROGRAMS AND SETPOINTS 2.2 Instrument Trip Setpoint Table The Instrument Trip Setpoint Limits in Table 2.2-1 are the Trip Setpoint value limits that were contained in the Instrumentation Setpoint tables for protection systems and other functions important to safety that were included in the scope of the original Standard Technical Specifications. Actual instrument setpoints are established utilizing the Allowable Values specified in the Technical'Specifications and Technical Requirements. Allowable Values are established in the Reference LCOs and TROs identified in this Table. TRO references are enclosed in'square brackets.
Instrumentation process setpoints for the listed subsystems and trip functions are set consistent with the Trip Setpoint Limit Column of Table 2.2-1. Actual setpoints are established in accordance with engineering procedures.
Alarm setpoints and other non-protection system trip settings as may be found in the Technical Specifications or in the Technical Requirements are not included in this table.
Reference NDAP-QA-1 104 Setpoint Change Control I
I
.J, SUSQUEHANNA - UNIT 1 TRM /2.0-5 EFFECTIVE DATE 04/02/1999
PPL Rev. 2 Instrument Trip Setpoint Program 2.2
- TABLE 2.2-1 (Page 1 of 8)
INSTRUMENTATION SETPOINTS
-.' I SYSTEM/REFERENCE LCO [TRO]
TRIP FUNCTION TRIP SETPOINT 2.2.1.1 2.2.1.1 2.2.1.2 2.2.1.3 2.2.1.4 2.2.1.5 2.2.1.6 2.2.1.7 2.2.1.8 2.2.1.9 2.2.1.10 2.2.1.11 2.2.1.12 2.2.1.13 2.2.1.14 2.2.1.15 Reactor Protection 3.3.1.1 3.3.1.1 3.3.1.1 3.3.1.1 3.3.'1.1 3.3.1.1 3.3.1.1 3.3.1.1 3.3.1.1
- 3.3.1.1 3.3.1.1 3.3.1.1 Intermediate Range Monitor, Neutron Flux -
High Average Power Range Monitor, Neutron Flux
- High Setdown Average Power Range Monitor, Flow Biased Simulated Thermal Power-High Two Loop.
Operation Average Power Range Monitor, Flow Biased Simulated Thermal Power-High Single Loop Operation Average Power Range Monitor, Flow Biased Simulated Thermal Power - High Flow Clamped Average Power Range Monitor, Fixed Neutron Flux-High Reactor Vessel Steam Dome Pressure - High Reactor Vessel Water Level - Low, Level 3 Main Steam Isolation Valve - Closure This Section Not Used Drywell Pressure - High Scram Discharge Volume Water Level - High
- Level Transmitter Scram Discharge Volume Water Level - High
- Float Svitch Turbine Stop Valve - Closure Turbine Control Valve Fast Closure, Trip Oil Pressure - Low
- 120/125 divisions of full scale
- 1 13.5% of RATED THERMAL
'POWER
- 118% of RATED THERMAL POWER
- 1087 psig 2 13.0 inches (a)
- 10% closed
- 1.72 psig
- '65 gallons
- 61 gallons
- 5.5% closed
- 500 psig (continued)
(a) See Figure 22-1 ISUSQUEHANNA -UNIT 1 TRM /2.0-6 EFFECTIVE DATE 11/15/2004
Instrument Trip Setpoint Program 2.2 PPLRev.2 TABLE 2.2-1 (Page 2 of 8)
INSRTRI UMENTATIO)N SETPOINTS 1.
SYSTEM/REFERENCE LCO [TRO]
TRIP FUNCTION TRIP SETPOINT 2.2.1.16 OPRM Instrumentation 2.2.1.16.1 3.3.1.3 Sp Cell Signal Amplitude See COLR - TRO 3.2 2.2.1.16.2 3.3.1.3 N2 Confirmation Count Permissive See COLR-TRO 3.2 2.2.1.16.3
[3.3.9]
TOL Period Confirmation Tolerance 0.10 sec 2.2.1.16.4
[3.3.9]
Ta Averaging Filter 5 sec 2.2.1.16.5
[3.3.9]
Fc Conditioning Filter Cutoff Frequency 1.5 Hz 2.2.1.16.6-
[3.3.9]
Tmin Minimum Oscillation Period 1.0sec 2.2.1.16.7
[3.3.9]
Tmax Maximum Oscillation Period 3.5 sec 2.2.1.16.8
[3.3.9]
Noise Floor Peak Discrimination Threshold 1
2.2.1.16.9
[3.3.9]
Minimum LPRM/Cell Cell Operability 2
Requirement 2.2.1.16.10
[3.3.9]
S1 Peak Threshold Setpoint 1.20 2.2.1.16.11
[3.3.9]
S2 Valley Threshold Setpoint 0.85 2.2.1.16.12
[3.3.9]
Smax Max. Amplitude Trip Setpoint
.1.50 2.2.1.16.13
[3.3.9]
DR3 Growth Rate Factor Setpoint 1.60 2.2.1.16.14
[3.3.9]
TI lo Si to S2 Timer Range 0.5 sec 2.2.1.16.15
[3.3.9]
TI hi SI to S2 Timer Range 1.75 sec 2.2.1.16.16
[3.3.9]
T2lo S2 to(S3 or Smax) Timer Range 0.5 sec 2.2.1.16.17
[3.3.9]
T2 hi S2 to(S3 or Smax) Timer Range 1.75 sec 2.2.2 Isolation Actuation Instrumentation 2.2.2.1 Primary Containment Isolation 2.2.2.1.1 3.3.6.1 Reactor Vessel Water Level Low, Level 3
' 13.0 inches(a) 2.2.2.1.2 3.3.6.1 Reactor Vessel Water Level Low Low, Level 2 2 -38.0 inches"'
2.2.2.1.3 3.3.6.1 Reactor Vessel Water Level Low Low Low,
-129 inches°a)
Level I 2.2.2.1.4 3.3.6.1 Drywell Pressure - High 1.72 psig 2.2.2.1.5 3.3.6.143.3.6]
SGTS Exhaust Radiation - High s 23.0 rr7/hr 2.2.2.1.6
[3.3.6]
Main Steam Line Radiation - High High s 15 x full power background without hydrogen injection (continued)
I
I SUSQUEHANNA - UNIT 1 TRM / 2.0-7 EFFECTIVE DATE 11/15/2004
PPL Rev. 2 Instrument Trip Setpoint Program 2.2
.. i I
TABLE 2.2-1 (Page 3 of 8)
INSTRUMENTATION SETPOINTS I
SYSTEM/REFERENCE LCO
[TRO]
TRIP FUNCTION TRIP SETPOINT secondary.containment Isolation 2.2.2.2.1 3.3.6.2 2.2.2.2.2 2.2.2.2.3 2.2.2.24 2.2.2.2.5 3.3.6.2 3.3.6.2 3.3.6.2 3.3.6.2 Reactor Vessel Water Level - Low Low, Level 2 Drywell Pressure - High Refuel Floor High Exhaust Duct Radiation -
High_
Railroad Access Shaft Exhaust Duct Radiation - High Refuel FloorWall Exhaust Duct Radiation -
High 2-38.0 inchesfa)
- 1.72 psig
- 18 mR/hr
-smR/hr
- 21 mR/hr 2.2.2.3 Main Steam Line Isolation 2.2.2.3.1 3.3.6.1 Reactor Vessel Water Level - Low Low Low, Level I 2.2.2.3.2 3:3.6.1 Main Steam Line Pressure - Low 2.2.2.3.3 3.3.6.1 Main Steam Line Flow-High 2.2.2.3.4 3.3.6.1 Condenser Vacuum - Low 2.2.2.3.5 3.3.6.1 Reactor Building Main Steam Line Tunnel Temperature - High 2.2.2.3.6 This Section Not Used 2.2.2.3.7
. [3.3.6]
Reactor Building Main Steam Line Tunnel A Temperature - High 2.2.2.3.8
[3.3.6.1]
Turbine Building Main Steam Tunnel Temperature - High 2.2.2.4 Reactor Water Cleanup System Isolation 2-129 inches(a) 2 861 psig l 113 psid 2 9.0 inches Hg vacuum
- 177 0F
- 990F
- 197OF 2.2.2.4.1 2.2.2.4.2 2.2.2.4.3 2.2.2.4.4 2.2.2.4.5 3.3.6.1 3.3.6.1 3.3.6.1 3.3.6.1
[3.3.6]
Reactor Vessel Water Level - Low Low, Level 2 RWCU ~ Flow - High RWCU Flow - High RWCU Penetration Area Temperature - High RWCU Penetration Room Area A Temperature
- High RWCU Pump Area Temperature - High RWCU Pump Room Area A Temperature -
High RWCU Heat Exchanger Area Temperature -
High-RWCU Heat Exchanger Room Area A Temperature - High 2.2.2.4.6 3.3.6.1 2.2.2.4.7
[3.3.6]
- -38 inches(a) 59 gpm
- 462 gpm s 131°OF s 69°F
's 147°F s 69°F
. 147°F s69°F 2.2.2.4.8 2.2.2.4.9 3.3.6.1
[3.3.6]
(continued)
-a) See Figure 2.2-1
.SUSQUEHANNA - UNIT i
-~ TRM / 2.0 EFFECTIVE DATE 11/15/2004
Instrument Trip Setpoint Program 2.2 PPL Rev. 2
-I TABLE 2.2-1 (Page 4 of 8)
INSTRUMENTATION SETPC)INTS SYSTEM/REFERENCE LCO
[TRO]
TRIP FUNCTION TRIP SETPOINT 2.2.2.5 Reactor Core Isolation Cooling System Isolation 2.2.2.5.1 3.3.6.1 RCIC Steam Une A Pressure - High 2.2.2.5.2 3.3.6.1 RCIC Steam Supply Line Pressure - Low 2.2.2.5.3 3.3.6.1 RCIC Turbine Exhaust Diaphragm Pressure
- High 2.2.2.5.4 3.3.6.1 RCIC Equipment Room Temperature - High 2.2.2.5.5 3.3.6.1 RCIC Pipe Routing Area Temperature - High 2.2.2.5.6 3.3.6.1 RCIC Emergency Area Cooler Temperature -
High 2.2.2.5.7 3.3.6.1 Drywell Pressure - High 2.2.2.5.8
[3.3.6]
RCIC Equipment Room A Temperature - High 2.2.2.5.9
[3.3.6]
RCIC Pipe Routing Area A Temperature -
High 2.2.2.6 High Pressure Coolant Injection System Isolation s 188 inches H20 2 60 psig s 10.0 psig s 1670F s 1670F s 1670F
- 1.72 psig
-s890 F
- 890 F s 370 inches H20
- 2. 104 psig S 10 psig s 167!F s 167°F s 1670 F s 1.72 psig
' 890F s 89°F i
I 2.2.2.6.1 2.2.2.6.2 2.2.2.6.3 2.2.2.6.4 2.2.2.6.5 2.2.2.6.6 2.2.2.6.7 2.2.2.6.8 2.22.6.9 2.2.7 2.2.2.7.1 2.22.7.2 2.2.2.7.3 2.2.3 3.3.6.1 HPCI Steam Lrie A Pressure - High 3.3.6.1 HPCI Steam Supply Line Pressure - Low 3.3.6.1 HPCI Turbine Exhaust Diaphragm Pressure -
High 3.3.6.1 HPCI Equipment Room Temperature - High 3.3.6.1 HPCI Emergency Area Cooler Temperature -
High' 3.3.6.1 HPCI Pipe Routing Area Temperature - High 3.3.6.1 Drywell Pressure - High
[3.3.6]
HPCI Equipment Room A Temperature - High
[3.3.6]
'HPCI Pipe Routing Area A Temperature -
High Shutdown Cooling/System Isolation
' 3.3.6.1 3.3.6.1
[3.3.6]
ECCS Actuation Reactor Vessel Water Level - Low, Level 3 Reactor Vessel Steam Dome Pressure - High RHR Flow - High
- ~,13.0 imrneP)~
. <98 ~sig
- 5 25,020~ gpm 2.23.1 Core Spray System 2.2.3.1.1 3.3.5.1 2.2.3.1.2 2.2.3.1.3 3.3.5.1 3.3.5.1 Reactor Vessel Water Level - Low Low Low, Level I Drywell Pressure - High Reactor Vessel Steam Dome Pressure - Low injection permissive 2 ;-129 inches')
- 1.72 psig 413,* 427 psig (continued)
') See Figure 2.2-1
. SUSQUEHANNA - UNIT1 TRM / 2.0-9 EFFECTIVE DATE 11/15/2004 II
Instrument Trip Setpoint Program PPL Rev. 2 I
I 2.2 I, )
TABLE 2.2-1 (Page 5 of 8)
IM.QTPI ]RIAM rTATIMN.ITD(tlKITQ
.I
- I Vr s II %%,fowl 6_`
r-% II W I II
%.rIII `1 a SYSTEMIREFERENCE LCO
[TRO)
TRIP FUNCTION TRIP SETPOINT 2.2.3.2 LPCI Mode of RHR System 2.2.3.2.1 3.3.5.1 Reactor Vessel Water Level - Low Low Low, 2 -129 inches(')
Level I 2.2.3.2.2 3.3.5.1 Drywell Pressure - High 1.72 psig 2.2.3.2.3 3.3.5.1 Reactor Vessel Steam Dome Pressure - Low, 2 413,
- 427 psig injection permissive 2.2.3.2.4 3.3.5.1 Reactor Vessel Steam Dome Pressure - Low, 2 236 psig, decreasing Recirculation Discharge Valve permissive 2.2.3.3 HPCI System 2.2.3.3.1 3.3.5.1 Reactor Vessel Water Level --Low Low,
-38 inches(')
Level2 2.2.3.3.2 3.3.5.1 Drywell Pressure - High 1.72 psig 2.2.3.3.3 3.3.5.1 Condensate Storage Tank Level - Low 2 36.0 inches above tank bottom 2.2.3.3.4-3.3.5.1 Reactor Vessel Water Level - High, Level 8
- 54 inches 2.2.3.4 Automatic Depressurization System (ADS) 2.2.3.4.1 3.3.5.1 Reactor Vessel Water Level - Low Low Low, 2 -129 inches Level 1 2.2.3.4.2 3.3.5.1 Drywell Pressure - High
- 1.72 psig 2.2.3.4.3 3.3.5.1 ADS Timer 102 seconds 2.2.3.4.4 3.3.5.1 Core Spray Pump Discharge Pressure - High' 135, 5 155 psig 2.2.3.4.5 3.3.5.1 Low Pressure Coolant Injection Pump 2 121, *129 psig Discharge Pressure - High 2.2.3.4.6 3.3.5.1 Reactor Vessel Water Level - Low, Level 3 2 13 inches Confirmatory 2.2.3.4.7 3.3.5.1 ADS Drywell Pressure Bypass Timer
- 420 seconds 2.2.3.5 Loss of Power - ECCS Actuation 2.2.3.5.1 4.16kv ESS Bus Undervoltage (Loss of Voltage < 20%)
2.2.3.5.1.1 3.3.8.1 Bus Undervoltage 2 823.2, 5 856.8 Volts 2.2.3.5.1.2 3.3.8.1 Time delay 2 0.4, at 0.6 seconds (continued)
(a) See Figure 2.2-1 V_~
SUSQUEHANNA - UNIT I TRM / 2.0-10 I
I.
.0EFFECTIVE DATE 11/15/2004.
PPL Rev. 2 Instrui TABLE 2.2-1 (Page 6 of 8)
INSTRIUMENTATICON SqFTP(OINTq I -
=
2.2.3.5.2 2.2.3.5.2.1 2.2.3.5.2.2 2.2.3.5.3 2.2.3.5.3.1 2.2.3.5.3.2 2.2.3.5.3.4 2.2.3.5.4 2.2.3.5.4.1 2.2.3.5.4.2 2.2.3.5.5 2.2.3.5.5.1 2.2.3.5.5.2 2.2.4 2.2.4.1 2.2.4.1 2.2.5 2.2.5.1 2.2.5.2 2.2.6 2.2.6.1 2.2.6.2 2.2.6.3 (a) See Figui SYSTEM/REFERENCE LCO
[TRO]
TRIP FUNCTION 4.16kV ESS Bus Undervoltage (Degraded Voltage < 65%)
3.3.8.1 Bus Undervoltage 3.3.8.1 Time delay 4.16kV ESS Bus Undervoltage (Degraded Voltage, < 93%)
3.3.8.1 Bus Undervoltage 3.3.8.1 Time Delay (Non-LOCA) 3.3.8.1 Time Delay (LOCA) 480V ESS Bus OB565 Undervoltage (Degraded Voltage, < 65%)
[3.8.5]
480V Basis
[3.8.5]
Time Delay 480V ESS Bus OB565 Undervoltage (Degraded Voltage, < 92%)
13.8.5] -
480V Basis
[3.8.5]
Time Delay ATWS Alternate Rod Injection and Recirculation Pump Trip 3.3.4.243.1.1]
Reactor Vessel, Water Level - Low Low, Level 2 3.3.4.243.1.1]
Reactor Vessel Steam Dome Pressure-High End of Cycle Recirculation Pump Trip 3.3.4.1 Turbine Stop Valve-Closure 3.3.4.1 Turbine Control Valve - Fast Closure
-Reactor Core Isolation Cooling System Actuation 3.3.5.2 Reactor Vessel Water Level - Low Low, Level 2 3.3.5.2 Reactor Vessel Water Level - High, Level
.8 3.3.5.2 Condensate Storage Tank Level - Low -
iment Trip Setpoint Program 2.2 TRIP SETPOINT
- 2641.1, *2748.9 Vofts 2 2.7, *3.3 seconds 2 3829.3,
- 3906.7 Volts 2 4 minute, 30 seconds
- 5 minute, 30 seconds 2 9,
- 11 seconds 2 308.9, S315.1 Volts 2 4.5,
- 5.5 seconds 2 437.6, *446.4 Volts 2:9,s11 seconds.
2-38 inches(a)
- 1135 psig
- 5.5% closed
-2500 nsig 2:-35 Inches(*)
- s 54 inches(')
2 36.0 inches above tank bottom (continued)
-e 22-1 SUSQUEHANNA - UNIT I TRM 12.0-11 EFFECTIVE DATE 11/15/2004
Instrument Trip Setpoint Program 2.2 PPL Rev. 2 TABLE 2.2-1 (Page 7 of 8)
INSTRUMENTATION SETPOINTS SYSTEM/REFERENCE LCO
[TRO]
TRIP FUNCTION TRIP SETPOINT 2.2.7 Control Rod Block 2.2.7.1 Rod Block Monitor 2.2.7.1.1 3.3.2 Low Power Range Upscale -Two Loop
- 0.58W-N 52%
-Operation 2.2.7.1.2 3.3.2 Low Power Range Upscale - Single Loop
- 0.58W + 47%
Operation 2.2.7.1.3 Downscale 5%
2.2.7.2 APRM 2.2.7.2.1 13.1.3]
Flow Biased Simulated Thermal Power-High See COLR - TRO 3.2
-Two Loop Operation 2.2.7.2.2 13.1.3]
Flow Biased Simulated Thermal Power High See COLR - TRO 3.2
- Single Loop Operation 2.2.7.2.3 13.1.3]
Flow Biased Simulated Thermal Power High
- 108% of RATED THERMAL POWER
- High Flow Clamped 2.2.7.2.4 13.1.3]
Downscale 5% of RATED THERMAL POWER 2.2.7.2.5
[3.1.3]
Neutron Flux - High Setdown 12% of RATED THERMAL POWER 2.2.7.3 Source Range Monitors 2.2.7.3.1
[3.1.3]
Upscale
- 2E5 cps 2.2.7.3.2
[3.1.3]
Downscale 2 0.7 cps° 2.2.7.4 Intermediate Range Monitors 2.2.7.4.1
[3.1.3]
Upscale
- 1081125 divisions of full scale 2.2.7.4.2
[3.1.3]
Downscale 2 5/125 divisions of full scale 2.2.7.5 Scram Discharge Volume 2.2.7.5.1
[3.1.3]
Water Level - High
- 35.9 ;allons 2.2.7.6 Reactor Coolant System Recirculation Flow 2.2.7.6.1
[3.1.3]
Upscale 114%
2.2.7.6.2
[3.1.3]
Comparator 10% fow deviation (continued)
° Provided signal-to-noise ratio is 2 2. Otherwise, 2 3 cps.
.. TRM / 2.0-12 SUSQUEHANNA 'UNIT 1 EFFECTIVE DATE 11/15/2004
Instrument Trip Setpoint Program 2.2 PPL Rev. 2 I-)J
.TABLE 2.2-1 (Page 8 of 8)
. INSTRUMENTATION SETPOINTS l
SYSTEM/REFERENCE LCO
[TRO]
TRIP FUNCTION TRIP SETPOINT 9 9 A 2.2.8.1
.2.2.8.1.1 LCMREocS 3.3.7.1 3.3.7.1 2.2.8.1.2 2.2.8.1.3 2.2.8.1.4 2.2.8.1.5 3.3.7.1 3.3.7.1 3.3.7.1 3.3.7.1 Main Control Room Outside Air Intake Radiation Monitor Reactor Vessel Water Level - Low Low,
-Level 2 Drywell Pressure - High Refuel Floor High Exhaust Duct Radiation
- - High Railroad Access Shaft Exhaust Duct Radiation - High Refuel FloorWall Exhaust Duct Radiation
- High
- 5 mR/hr 2 -38.0 inches(a)
- 1.72 psig
- 18 mR/hr.
- 5 mR/hr
- 21 mR/hr d-2.2.9 Feedwater/Main Turbine Trip System Actuation.
2.2.9.1 3.3.2.2 Reactor Vessel Level - High 2.2.10 MVP Isolation 2.2.10.1
[3.3.11]
- 54.0 inches(a)
- 15 x full power backgroun without hydrogen injection
- Main Steam Line Radiation - High High (a) See Figure 2.2-1
-TRM / 2.0-13 SUSQUEHANNA - UNIT 1-UTEFFECTIVE DATE 11/15/2004
Instrument Trip Setpoint Table 2.2 PPL Rev. 2 4
3,
- ATER LEVEL WDIECLATURE HEIGHT ABOVE
'NO.
VESSEL ZERO READING (IN.)
(7).
-566.5
+3?
70
-45 VSSL(4) 557.5
+30 E,
cn'5(8)
+6 '21-+60 S*
-3t-566537)*.
.C8 540-
- 7) 13 IRL
- 55.
4' PI&489.5 3 8 O
)
39885
-129.
,, ~ ~
~
~
~
2 INTI, R.C TO
,i
.*;-S*z SIIIIH F
t t-SDS F~UE
- .400
-*8; Sl:
-12
.-4 W
~RANGE
.NOTE S L IN CIES.
5-.-
' 154 7
RBET SSS..S-
- 7)
O 7VE VESE ZERM 300--
RCTYE F
218i.2-1ECI
.RECRCO VE1SE 5
- TEILETEL
. ADR4 i
CORE CONTRI SPRA (2
INTIT.'I TO-ADS
.HP.I*
.RI
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IGtE
.21
~
3 ACTIOR VESSL,AERL~
'.UELNID
~2-i3 250-I SUSQUEHANNA - UNIT I
-TRM / 2.0-14 EFFECTIVE DATE 11/15/2004
Core Operating Limits Report (COLR)
PPL Rev. 4 3.2.1 3.2 Core Operating Limits Report (COLR) 3.2.1 Core Operating Umits Report (COLR)
TRO 3.2.1 APPLICABILiT The Core Operating Limits specified in the attached COLR shall be met.
e:
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 NO_-~
N/A No associated Surveillances. Surveillances are implemented in the applicable Technical Specifications.
SUSQUEHANNA - UNIT 1 TRM /32-1' EFFECTIVE DATE 7/07/1999
PPL Rev. 4 PL-NF-04-001 Rev. 1 Page 1 of 37
.i Susquehanna SES Unit 1 Cycle 14 CORE OPERATING LIMITS REPORT Nuclear Fuels Engineering November 2004
)
/-*M)~~J4 -
ndi
-. ppl,'
.2
.S1 tSOtIFHANNA -UN IT 1 -TRN/3
.2-2 EFFECTIVE DATE 11/15/2004
-PPL Rev. 4 PL-NF-04-001 Rev. 1 Page 2 of 37 CORE OPERATING LIMITS REPORT REVISION DESCRIPTION INDEX Rev.
Affected No.
Sections Description/Purpose of Revision 0
1 ALL TOC 1.0 2.0 I 9.0
, 10.0 11.0 Issuance of this COLR is in support of Unit 1 Cycle 14 operation.
This revision changes the Power I Flow map and adds setpoints for the OPRM system. The change to the Power / Flow map provides direction when the OPRM system is OPERABLE and inoperable. The setpoints for the OPRM system are set to reliably detect and suppress anticipated stability related power oscillations while providing a high degree of confidence that the MCPR safety limit is not violated.
I
FORM NFPOA-008-2, Rev. 1 SUSQUEHANNA UNIT 1 TRM/3.2-3 EFFECTIVE DATE 11/15/2004
PPL Rev. 4 PL-NF-04-001 Rev.1 Page 3 of 37 SUSQUEHANNA STEAM ELECTRIC STATION Unit 1 Cycle 14 CORE OPERATING LIMITS REPORT TAbl of Contents INTRODUCTION.'
2.0 DEFINITIONS........................................................5 3.0
-SHUTDOWN MARGIN..............
6.
-~4.0 AVERAGE PLANAR LINEAR HEAT GENERATION RATE (APLHGR).............
7 5.0 MINIMUM CRITICAL POWER RATIO (MCPi)..................................
9 6.0 LINEAR HEAT GENER4ATION RATE (LHGR)................................
20 7.0 AVERAGE POWER RANGE MONITOR (APIRM) GAIN AND SETPOINTS.........
23 8.0 RECIRCULATION LOOPS - SINGLE'LOOP OPERATION...............
I.......26 9.0 POWER/FLOW MAP....................I..............................33 10.0.
OPRM SETPOINTS....................................................35
- 11.
REFERENCES........................................................
36 I
- A-
.SUSQUEHANNA UNIT 1 TRM/3.2-4 EFFECTIVE DATE 11/15/2004 L
PPL Rev. 4
-PL-NF-04-001 Rev. 1 Page 4 of 37
1.0 INTRODUCTION
This CORE OPERATING LIMITS REPORT (COLR) for Susquehanna Unit 1 Cycle 14 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.
1.
/.
SUSQUEHANNA UNIT 1 D
TRM/3.2-5 I
I 11/15/2004
-EFFECTIVE DATE
PPL Rev. 4 PL-NF-04-001 Rev.1 Page 5 of 37 2.0 DEFINITIONS 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.
2.2 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.
2.3 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 type.
2.4 The FRACTION OF RATED THERMAL POWER (FRTP) shall be the measured THERMAL POWER divided by the RATED THERMAL POWER.
2.5 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.
2.6 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 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.
2.9 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 2.10 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.
2.11 Sp is the OPRM trip setpoint for the peak to average OPRM signal.
)
-2.12 Fp is the core flow below which the OPRM RPS trip is activated.
'SUSQUEHANNA UNIT 1 TRM/3.2-6 EFFECTIVE DATE 11/15/2004
PPL Rev. 4 PL-NF-04-001 Rev. I Page 6 of 37 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% AkIk with the highest worth rod determined by test Since core reactivity will vary during the cycle as a function of fuel depletion and poison bumup, 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, UR", 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 1I TRM/3.2-7 EFFECTIVE DATE 11/15/2004
PPL Rev. 4 PL-NF-04-001 Rev. 1 Page 7 of 37 4.0 AVERAGE PLANAR LINEAR HEAT GENERATION RATE (APLHGR) 4.1 Technical Snecification Reference Technical Specification 3.2.1 4.2 Description The APLHGRs for ATRIUMT7-10 fuel shall not exceed the limit shown in Figure 4.2-1.
The APLHGR limits in Figure 42-1 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.
I SUSQUEHANNA UNIT 1 TRM/3..2-8 IEFFECTIVE DATE 11/15/2004
C).
SSES UNIT 1 CYCLE 14 Ic-i,
.(n JC rn.
-4i
.16 14-
~12
~I toSccw Pri-I
-I,.
a 0J 0
SLJ S
L
~ K v 1. [ ~ iiiliiiI::REFERENCE T.S. 3.2.111
- 6.
66 6
6 6
6 6
6 6
6 6
6 6
I
.I I
I I
I I
I I
I 6 0*
6-00 20006 60 4000 6
6 600 701 l0 I-CD I
iI i
i II iI IIIL i
I I
I
-4i 1-4 ri-1 0n
-P.
6 4
0n on Average Planar Exposure(MWDIMTU)
(D.
.(D AVERAGE PLANAR LINEAR HEAT GENERATION RATE LIMIT VERSUS AVERAGE PLANAR EXPOSURE TWO LOOP OPERATION ATRIUMTm.10 FUEL J
0 FIGURE 4.2-1
PPL Rev. 4 MINIMUM CRITICAL POWER RATIO (MCPR)
I PL-NF-04-001 Rev. 1 Page 9 of 37 5.0 5.1 Technical Specification Reference Technical Specification 32.2, 3.7.6, and 3.3.4.1 5.2 Descrintion 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 (ATRlUM'-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 EO Figure 5.2-2. Power-Dependent MCPR value determined from BOC to EOC b)
Main Turbine Bypass Inoperable / EOC-RPT Operable Figure 52-3: 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 / Main Turbine Bypass Operable Figure 52-5: Flow-Dependent MCPR value determined from BOC to EOC Figure 5.2-6: Power-Dependerit MCPR value determined from BOC to EOC The MCPR limits in Figures 5.2-1 through 5.2-6 are valid for Two Loop operalion.
The MCPR limits for Single Loop operation are provided in Section 8.0.
5.3 Averaae Scram Time Fraction Table 5.3-1 provides the relationship between average scram time to control rod position and scram time fraction. 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/3.2-10 EFFECTIVE DATE 11/15/2004
PPL Rev. 4 PL-NF-04-001 Rev. 1.
Page 10 of 37 I
EOC-RPT and Main Turbine Bypass Operable I
.SUSQUEHANNA UNIT 1 TRM/3. 2-11 EFFECTIVE DATE 11/15/2004
. (j
- 1 0u 0.'.
(A oc 3.
C 1-h SSES UNIT 1 CYCLE 14 2.3 2.2 2.1 2.0 fr.
0=.
) 1.7 1.6 I
I I-LEGEND CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 USED IN DETERMINING MFLCPR
-b
-u
- C I,,-n
-n m
m-4 m
'-A$-a
-S (30,1.52) 1.5 1.4 1.3 (39.9,1.47)_-
. m
_.4 a aa a a.
a al a a a a la a
_t
.I m
a'=
'm m
a a m.m "
a A..
a....
(108,1.47).
I - ----
i i
(108,1.39)
I REFEREiNCEi: Tu.S. 3.2.21I I
L B
I i
(65,1.39) 30 40 50 60 70 80 90.
100 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 5.2-1 110 (a
IJ Co I
in 0
0 co
0~
C0 L/A Ut
)
U' m
R 1-I~
F-4 SSES UNIT 1 CYCLE 14 3.0 2.9 2.8 2.7 2.6
- 2.5 2.4
. 9
- i 2.3 CA1. -
a2.2 3}
- ,l i
<.o 2.1
.2.0 1.9 LEGEND CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES
.ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 (25,2.30)
\\
_USED IN DETERMININtG MFLCPR.
.REFEREN..CE: T.S. 3.2.2 a a a
a m
rn
-I,
. m I,_
n
-C.
i-m m
'--A
$--A
- o
-P.
1.8 1.7 1.6 1.5 1.4 1.3
-u
-r (CD
.4
.4 (100,1.46)
(100,1.39)
I179,1.39)
II 20 30 40.
50 60 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 m (D C
to <
(D.
Z ro o
6.-
co 0
-4
-A
0
PPL Rev. 4 PL-NF-04-001 Rev. 1 Page 13 of 37 I
I K
Main Turbine Bypass Inoperable I EOC-RPT Operable-SUSQUEHANNA UNIT 1 TRM/3.2-14 EFFECTIVE DATE~ 11/15./2004
0)
(ll 0
I (n
C Ln m
CI 0-.
SSES UNIT 1 CYCLE 14 2.3 I
I I
2.2 2.1 I
a a
a IlUt1V D*
A: MAXIMUM ALLOWABLE AVERAGE SCRAM
- INSERTION TIME E B: REALISTIC AVERAGE SCRAM INSERTION TIME I
a I I -II i
lbtr 2.0 'I 4
1 I-SAFETY ANALYSES ASSUME THAT TWO OR MORE BYPASS VALVES ARE INOPERABLE PER SR 3.7.6.1 OR 3.7.6.2 NJ CD
_ i.
C>
- 4~
C~,
-4.
m-E 1.9
.0) c
.I 1.8 0.
CL 0
& 1.7
(
1.6 1.5 1.4 1.3 USED IN DETERMINING MFLCPR
.( 0,.70)
(108,1.7(
.. o
- u I-.
CD -
5 0
~
~
-I
REFERENCE:
T.S. 3.7.6 and 3.2.21
-tt 4
I 4.
r I
I 1
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
&)
0 4
'6 2.
()
SSES UNIT 1 CYCLE 14 U -
(I)
C=
P1
.Jo C=
.'. E.
'l-4
--i I-A 3.0 I*
Y Y
2.9 2.8 2.7 2.6 2.5 9.4 LEGEND CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME (25,2.49)
I I
I
.1
_ II1' -
SAFETY ANALYSES ASSUME THAT TWO OR MORE BYPASS VALVES ARE INOPERABLE PER SR 3.7.6.1 OR 3.7.6.2 1
- 3 2.3 I
c-co
.c 2.2 CA 0
- a 2.0
- 2.
0 1.9
.N I
. I I I
rn-n c
q I-,
0.
M-4 I-
-A L-'.
CD, S.-
1.8 1.7 1.6 1.5 1.4 1.3 USED IN DETERMINING MFLCPR (40,1.94).
__A__.
B
- __(65.5,1.70)
RE E E CE: T.S. 3.7.6....t I
- 10
,.I-( 1 0 0, 1. 7 0 (100,1.70) 20 30.
40 50 60-Core Power (% RATED) 70 80 90 MCPR OPERATING LIMIT VERSUS CORE POWER MAIN TURBINE BYPASS INOPERABLE I EOC-RPT OPERABLE TWO LOOP OPERATION (BOC to EOC)
FIGURE 5.2-4 100I
)
oM u(
o CD.
Z co o
4
PPL Rev. 4 I
PL-NF-04-oo1 Rev. 1 Page 16 of 37.
I.j ie I
I EOC'RPT Inoperable iX' Main Trbine ypass Opera ble I
. SUSQUEHANNA UNIT 1 I
I.
-TRM/3. 2-17 UEFFECTIVE DATE 11/15/2004
Q-)
C)
It t
C (A
Cd)
D 2o C
-i SSES UNIT 1 CYCLE 14
'ii I
1 2.2 2.1 I
1a
.GEND URVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME URVE B: REALISTIC AVERAGE SCRAM INSERTION TIME
.I II I
I c
I1 I,
I
,I I
2.0 SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2
=I c
,0,_
S 1.7 s:1
&E 1.7 0.>
-l____
USEDIN DETERMINING MFLCPR
-u
- 0b 108,1.51)..
1.6 m
-n m
n-C PT1
-i tn
-a)
V
'-a 01-N3 CO a)
C)
(30,1.52)
,(
1.5 1.4 1.3 I_
A B
-I (37,1.51)
I IE C
I 3
IREFERENCE:
T.S. 3.3.4.1 and 32.21 I
I I
30 40 50 60 70 80 90 100
.110
.Total Core Flow (MLB/HR)
MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW EOC-RPT INOPERABLE I MAIN TURBINE BYPASS OPERABLE TWO LOOP OPERATION (BOC TO EOC)
FIGURE 5.2-5 T
MT lb o(D r (D
- Z
.. A -4
(ii
(.
q (A.
C C) m
-H SSES UNIT 1 CYCLE 14 3.0 2.9
. 2.8 2.7 2.6
- 2.5 2.4 i2.3 32.2 i
L 2.1
- 2.0
'1.9 I
'V I
I I
I I
LEGEND a
a a-a CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME I.
I
. I
_ I II I
=
SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 CI9
~-A E
o 1 c
- s I E tL a
- u C
(25,2.30) a a
a I
- . -USED IN DETERMINING MFLCPR
.1 a
4
.N (30,2.13)-
I I
__l_
1.8
-n rri m
3 I-I
. M..,
m F--A o\\3 1.7 1.6
- 1.5 1.4 1.3 (40,1.78)
REFERENCE:
T.S. 3.3.4.1 and 3.2.2 1
~~~~~~(74,1.51)
-. u I -u (100,1.51) 20 30
. 40
- 50 60 70 80 90
-100 Core Power (% RATED)
MCPR OPERATING LIMIT VERSUS CORE POWER EOC-RPT INOPERABLE I MAIN TURBINE BYPASS OPERABLE TWO LOOP OPERATION (BOC to EOC)
FIGURE 5.2-6.
-u Co CD co
.0 co-aI.S CD 7 r
. 6 0
.~~
I
PPL Rev. 4 PL-NF-04-O01 Rev.1 I
Page19 of 37 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 0.480 0..490 0.500 0.510 0.520 39 0.630 0.676 0.722 0.768 0.814 0.860 25 1.500 1.582 1.664 1.746 1.828 1.910 5
2.700 2.848 2.996 3.144 3.292 3.440 Scram Time 0.000 0.200 OAOO 0.600 0.800 1.000 Fraction Average Scram Realistic Maximum Insertion Time Allowable
. SUSQUEHANNA UNIT 1
- TRM/3.2-20 EFFECTIVE DATE
.11/15/2004
IPPL Rev. 4 PL-NF-04-001 Rev. 1 Page 20 of 37 i
6 i
.0 LINEAR HEAT GENERATION RATE (LHGR) 6.1 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.
I I - -
I I
I I
I TRM/3.2-21 SUSQUEHANNA UNIT 1 'E EFFECTIVE DATE 11/15/2004 '
(2 )
SSES UNIT 1 CYCLE 14
(,- I C/)
(f)
C=
P1\\
-1
'-a m
CD 4.-1 16 14
& 12
- E5
- C 0Or
.to
- 0
.s 8 Io I
!6 SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 S
I S
I S
5 I
I I
5 3
5 S
S I
5 6
5 5
3I 0.0,13.4*..
5O0134:
REFERENCE:
T.S. 3.2.3 s
5I 5
,SS IUSED NEERMINING FDLRXj.
.S....
- .,*5
_S.-...........
~--;
- -I-
.- - -*-'----SDNEEMNNFLX.
10.
'U.
6
. 4 0
10000 20000 30000 40000 50000 60000 Average Planar Exposure (MWDIMTU)
LINEAR HEAT GENERATION RATE LIMIT VERSUS AVERAGE PLANAR EXPOSURE MAIN TURBINE BYPASS OPERABLE ATRIUMm-10 FUEL FIGURE 6.2-1
.70000 (D
Z ro 6
-J
r U,
SSES UNIT 1 CYCLE 14 U,
LflI C
I-4
-I CAD.
r%3 N3 CA)-
m
-n
-n m
C,
'-4 I-,,
-I I,,
I-a
'-a
-S (3,
5 16 14 le 12 E
3.
c 0
o
-U I.
8 c
.~
.5
.S
- SAFETY ANALYSES ASSUME THAT TWO OR MORE BYPASS
- VALVES ARE INOPERABLE PER SR 3.7.6.1 OR 3.7.6.2
- .: : ::[
R~EFERENCE:T.S. 3.2.3and3.7.6 :
.*USED INDTRINN DR 0.0,12.0: ::150o0,12.0 5
EEMNN d.....
~~
S~.
.........T I
67000,6.39 S
I!.!..'...!.'......!...!.'......t..
0 4
10 4
0 100100 20000 30000 40000 50000 604 Average Planar Exposure (MWD/MTU)
LINEAR HEAT GENERATION RATE LIMIT VERSUS AVERAGE PLANAR EXPOSURE MAIN TURBINE BYPASS INOPERABLE ATRIUMT -10 FUEL FIGURE 6.2-2 1000 7000i (D.
z Q
Is0 c)
CD
PPL Rev. 4 PL-NF-04-001 Rev. 1 Page 23 of 37 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 flow biased simulated thermal power-upscale scram trip setpoint (S) and flow biased neutron flux-upscale control rod block trip setpoint (SRB) shall be established as specified in Table 7.2-1 and Table 7.2-2, 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 flow biased simulated thermal power-upscale scram trip setpoint and flow biased neutron flux-upscale control rod block trip setpoint for Two Loop and Single Loop operation. The APRM setpoints for Specification 3.2.4 are established in Tables 7.2-1 and 7.2-2.
i SUSQUEHANNA UNIT 1 I.
i TRM/3.2-24 EFFECTIVE DATE 11/15/2004
PPL Rev. 4
-PL-NF-04-001 Rev. 1 Page 24 of 37 Table 7.2-1 APRM Setpoint for Two Loop Operation Trip Setpoint l
Allowable Value S
(0.58W + 59%) T S(0.58W + 62%) T' SRa S (0.58W + 50%) T SR8* <0.58W + 53%) T Table 7.2-2 APRM Setpoint for Single Loop Operation Trip Setpoint Allowable Value S s (0.58W + 54%/)
T Sc(.8W + 57%)O T'I.
SRB 5 (0.58W + 45%) T SRBE5 (0.58W + 48%) T where: S and Sma are in percent of RATED THERMAL POWER W =
Loop recirculation flow as a percentage of the loop recirculation flow which produces a core flow of 100 million lbs/hr T =
Lowest value of the ratio of FRTP divided by the MFLPD.2 The FLPD is the actual LHGR dmided by the applicable LHGR limit for APRM Setpoints. The LHGR limit for APRM setpoints for ATRIUM'-10 fuel 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 Inoperable for both Two and Single Loop operation.
For calculated T-values greater than 1.0, a ratio of 1.0 is used in the above equations.
APRM flow biased simulated thermal power-upscale scram allowable value in
-this table is equal to the value established in Technical Specification 3.3.1.1.
2 For the calculation of T, the value of MFLPD shall be the maximum value of FDLRC.
I SUSQUEHANNA UNIT 1 E
. "TRM/3.2-25 EFFECTIVE DATE 11/15/2004
(-
Jc I16 rrn R
m
- C TC-SSES UNIT 1 CYCLE 14 I I c
- 14' 12 co.
m C
'10 0
a LI m)
CDI-
.6
REFERENCE:
T.S. 3.2.
I..
.I I II I
.I
.I I
- a.
I..
S.
.I..S.a.
S a
a a
a s -I 4 I6-IT Ir S
S-S I
S:
I
.S 10 I-
. I
. bi 0
10000 20000 30000 40000 50000 60000 70000 Average Planar Exposure (MWDIMTU)
CD Z
LINEAR HEAT GENERATION RATE LIMIT FOR APRM SETPOINTS VERSUS AVERAGE PLANAR EXPOSURE 6
ATRIUMTm-10 FUEL o
FIGURE 7.2-1
PPL Rev. 4 PL-NF-04-001 Rev.1I Page 26 of 37 8.0 RECIRCULATION LOOPS - SINGLE LOOP OPERATION 8.1 Technical Specification Reference Technical Specification.32.1, 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 ATRIUMT-1 0 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 Umit The MCPR limit Is specified as a function of core power, core flow, and plant equipment operability status. The MCPR limit for all fuel types (ATRIUMTM-1 0) shall be the greater of:
0 a) Flow-Dependent MCPR value determined from Figure 8.2-2 OR b)
'The Power-Dependent MCPR value determined from one of the following figures, as appropriate:
Figure 82-3: EOC-RPT and Main Turbine Bypass Operable from BOC to EOC Figure 8.2-4: Main Turbine Bypass Inoperable I EOC-RPT Operable from BOC to EOC Figure 82-5: EOC-RPT Inoperable I Main Turbine Bypass Operable from BOC to EOC The MCPR limits in Figures 82-2 through 8.2-5 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.
SUSQUEHANNA UNIT 1 TRM/3.2-27 EFFECTIVE DATE 11/15/2004
PPL Rev. 4 PL-NF-04-OO Rev. 1 Page 27 of 3 Averaae Power Range Monitor (APRM) Gain And Setnoints APRM setpoints and the LHGR limit for APRM setpoints for Single Loop operation are defined in Section 7.0.
1
.i
\\
SUSQUEHANNA UNIT 1 TRMl3.2-28 EFFECTIVE DATE 11115/21
'004
ii L
(9-(-Jr C
1 m
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- 1 I-4
=1
-J o*c r'.
I, 4..'U CI C
m
-ri-n m
m 0
-Im SSES UNIT 1 CYCLE 14 5
a a
a a a
a -S S
S S
- ~
a aREFERa ENa CE aS 3.4*1 ana 3.2.1 4
a.a.....
a S
a a,
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.S S
a Ia a
a a
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.- I (D.m F-s I-a 01 5 -P 0
10000 20000 30000
- 40000 50000 60000 Average Planar Exposure (MWD/MTU)
AVERAGE PLANAR LINEAR HEAT GENERATION RATE LIMIT VERSUS AVERAGE PLANAR EXPOSURE SINGLE LOOP OPERATION
-ATRIUM~m 10 FUEL FIGURE 8.2-1 70000
-a &
U I
()-
(ilC=
o m
-i I.
SSES UNIT 1 CYCLE 14 2.6 2.5 2.4 I
I I
I
- 1 I
-I.
ICURV=
D '
A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME B: REALISTIC AVERAGE SCRAM INSERTION TIME I
I I I
I I:
I.
1.
2.3 0).2.2 S. 2.1 m
. 2.0
'-n m
t-m -
1.9
,_-A
'-.1.
I
- 1.
1.
]
USED IN DETERMINING MFLCPR (-
i.
H-(30,2.19)
- A; B
I
~- ;, I I
2l (108.,2;19)
-a 0~
- 'a m
.P6 1
1.1 1I_
I
___1
REFERENCE:
T.S. 3.4.1 and 3.2.2j I" t
I I
.I I
I I
II o.-
o)
CD 42,A 30 40; 50 60
.70 80 90 100 110 Total Core Flow (MLB/HR)
FIGURE 8.2-2
-o-.
(a)-
Co <
S (D
z.-
(06, R
I o, 8
- 4.
I&
(i'.
J Q(,j SSES UNIT 1 CYCLE 14 3.5 I
1I I
I I
I I
3.4 3.3 3.2 3.1 LEGEND CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME 3.0 1 2.9 E
-I m 2.8 c.a
.E.
r \\i 2.7 L
0.
2.6 0.
M 2.5 2.4 M
2.3 I
I I.._
1-I
.1 SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2
- _(25,2.76)j I
USED IN DETERMINING MFLCPR I.
I.
Y 4
=A'B (38.9,2.1 9)
-.n lur-(D.
..5 4
I.
-nl M-I rnl
.Ei
-S 1.
I -
M o-2.1 2.0
.1.9 I
REFERENCE:
T.S. 3.4.1 and 3.2.2t
-I
- 4.
4
.1 4
- 1
_ (100,2.19) 00 I
I
'1 4
- 4.
- 4.
- 4.
4.
20 30 40 50 60 70 80 90 Core Power (% RATED)
MCPR OPERATING LIMIT VERSUS CORE POWER EOC RPT AND MAIN TURBINE BYPASS OPERABLE SINGLE LOOP OPERATION (BOC to EOC)
FIGURE'8.2-3 0 :., z CA) 4 o
0 2.D. l,
.0
-4.-
I
(6)
I SSES UNIT 1 CYCLE.14
- (_ _]
Ln c
- a.
C=
1 -4 I-aq
.3.5 3.4 3.3 3.2 3.1 3.0 LEGEND
.CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME (25,2.99)-
.. SAFETY ANALYSES ASSUME THAT TWO OR MORE BYPASS VALVES ARE INOPERABLE PER SR 3.7.6.1. OR 3.7.6.2
\\. _
. USED IN DETERMINING MFLCPR
\\
1 1
_ 1-cA)
-,r rri CPO
-Im 0
-Im o
'-a I-4 I--A 0-4
_0
-tg 2.9 m2.8
(-
.. 2.7 I
.0 2.6 1.9 C.,
22.5
-2.4 2.3 2.2 2.1 1.9
\\'\\
J.
=
.5 I
I.
.5
.. '\\
~~~~(40,2.33) 1 (52.8,2.19)
B
REFERENCE:
T.S. 3.4.1, 3.7.6, and 3.2.2 I
-o (100,2.19) 00 (D,
Z CD
-o 20 30 40 S0 60,
70 Core Power (% RATED) 80 90 MCPR OPERATING LIMIT VERSUS CORE POWER MAIN TURBINE BYPASS INOPERABLE I EOC-RPT OPERABLE SINGLE LOOP OPERATION (BOC to EOC)
FIGURE 8.2-4 I
( jI I
(n C=
m c-n CA)
CD)
CD
- n
- ri C,
- -4
'-4 m
C,,
0s 0
- 0l 4
/ 1 SSES UNIT 1 CYCLE 14 3.5 3.4 Y
I I
I I1-I I
3.3 3.2
-3.1 3.0 E 2.9
-im 2.8 2.7 Q
2.7 1 0i
- g 2.6 C.)
m.2.5 2.4
. 2.3 2.2 2.1 2.0 1.9 I
II I nl ic A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME EB: REALISTIC AVERAGE SCRAM INSERTION TIME V1 l I I
I aT
- 4.
.4
- 4.
0-
_(25,2.76).
SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 USED IN DETERMINING MFLCPR -
,.4.
.-I (38.9,2.19).
I-
,a
- 21 D (100,2.19)
-II
--]
REFERENCE:
T.S. 3.4.1, 3.3.4.1, and 3.2.2 k 4.
4 4
.1 I
I 1
1" 1*
20
' 30 40 50 60 Core Power (% RATED) 70 80 o9 100 MCPR OPERATING LIMIT VERSUS CORE POWER- -
EOC-RPT INOPERABLE / MAIN TURBINE BYPASS OPERABLE SINGLE LOOP OPERATION (BOC to EOC)
FIGURE 8.2-5 (g
8 CD Z
co 0
-PPL-Rev.4 PL-NF-04-001 Rev. 1 Page 33 of 37-9.0 POWER / FLOW MAP 9.1 Technical Specification Reference Technical Specification 3.3.1.3 9.2 Description 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 3.3.1.3, Region I of the Power / Flow map is considered an immediate exit region.
If the OPRM Instrumentation is inonerable per TS 3.3.1.3, 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.
I.-
..I I
I SUSQUEHANNA UNIT 1 TRM/3.2-34 EFFECTIVE DATE 11/15/2004
PPL Rev. 4 PL-NF-04-001 Rev. 1 Page 34 of 37 120 I
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- 100,
- 90 80 J
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STABILITY REGION I IF OPRM INOPERABLE, IMUEDIATE SCRAM IAW ON-178-002 IF OPRM OPERABLE, IUMEDIATE EXrr IAW ON-17t7U0 r.
I r n-..
T 9-I.0 -144.4 -
STABILrTY REGION 11 IMMEDIATELY EXIT LAW ON-17&O0 RESTRICTED REGION (As defind In Attachment G to NOAP-GA4a38) 120 110 100 90 80 70 60 50
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- 60.
70 80 90 100 110 Total Core Flow (Mlbrrthr)
LFigure 9.1 PoWer / Flow Map TRM/3.2-35 EFFECTIVE DATE 11/15/2004 SUSQUEHANNA UNIT 1
'PPL Rev. 4 PL-NF-04-001 Rev.1 Page 35 of 37
.10.0 OPRM SETPOINTS
-10.1 Technical SDecification Reference Technical Specification 3.3.1.3 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 1.0 and are listed below:
Sp
=
1.11
-Np 14.
Fp
=
65 Mlbm /hr SUSQUEHANNA UNIT 1 TRMI3.2-36 EFFECTIVE.DATE 11/15/2004
- PPL Rev. 4 IPL-NF-04-001 Rev.1 Page 36 of 37
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. PL-NF-90-001 -A, 'Application of Reactor Analysis Methods for BWR Design and Analysis," July 1992.
- 2. PL-NF-90-001, Supplement 1-A, 'Application of Reactor Analysis Methods for BWR Design and Analysis: Loss of Feedwater Heating Changes and Use of RETRAN MOD 5.1, August 1995.
- 3. PL-NF-90-O01, Supplement 2-A, "Application of Reactor Analysis Methods for BWR Design and Analysis: CASMO-3G Code and ANFB Critical Power Correlation,' July 1996.
- 4. PL-NF-90-001, Supplement 3-A, 'Application of Reactor Analysis Methods for BWR Design and Analysis: Application Enhancements," March 2001.
- 5. XN-NF-80-19(A), Volume 1, and Volume 1 Supplements 1 and 2 (March 1983),
and Volume I Supplement 3 (November 1990), NExxon Nuclear Methodology for Boiling Water Reactors: Neutronic Methods for Design and Analysis,'
Exxon Nuclear Company, Inc.
- 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," September 1982.
- 7. XN-NF-8D-1 9(P)(A), Volume 3 Revision 2 Exxon Nuclear Methodology for Boiling Water Reactors Thermex: Thermal Umits Methodology Summary Description, January 1987.
I I1
- 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, Inc. 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 Supplement 1, Revision 2, 'Advanced Nuclear Fuels Corporation Critical Power Methodology for Boiling Water Reactors,"
November 1990.
- 11. NE-092-OO1A, Revision 1, 'Ucensing Topical Report for Power Uprate With Increased Core Flown Pennsylvania Power & Uight Company, December 1992 and NRC SER (November 30,1993).
SUSQUEHANNA UNIT 1 TRM/3.2-37 EFFECTIVE DATE 11/15/2004
PPL Rev. 4 PL-NF-04-001 Rev. 1
-Page 37 of 37
- 12. ANF-89-98(P)(A) Revision 1 and Revision 1 Supplement 1, OGenedc Mechanical Design Criteria for BWR Fuel Designs," Advanced Nuclear. Fuels Corporation, May 1995.
- 13. ANF-91-048(P)(A), 'Advanced Nuclear Fuels Corporation Methodology for Boiling Water Reactors EXEM BWR Evaluation Model,' January 1993.
- 14. XN-NF-79-71 (P)(A) Revision 2, Supplements 1, 2, and 3, "Exxon Nuclear Plant Transient Methodology for Boiling Water Reactors,* March 1986.
- 15. EMF-1997(P)(A) Revision 0, OANFB-10 Critical Power Correlation," July 1998, and EMF-1997(P)(A) Supplement 1 Revision 0, 'ANFB-10 Critical Power Correlation High local Peaking Results," July 1998.
- 16. Caldon, Inc., 'TOPICAL REPORT: Improving Thermal Power Accuracy and Plant Safety While Increasing Operating Power Level Using the LEFM"
System,' Engineering Report - 80P, March 1997.
- 17. Caldon, Inc., "S4upplement to Topical Report ER-80P: Basis for a Power Uprate with the LEFM" or LEFM CheckPlus System," Revision 0, Engineering Report ER-1 60P, May 2000.
- 18. EMF-85-74(P)(A), -RODEX2A (BWR) Fuel Rod Thermal-Mechanical Evaluation Model," Revision 0, Supplements 1 and 2, February 1998.
- 19. EMF-2158(P)(A), Revision O, "Siemens Power Corporation Methodology for Boiling Water Reactors: Evaluation and Validation of CASMO-4lMicroburn-B2," Siemens Power Corporation, October 1999.
- 20. EMF-CC-074(P)(A), Volume 4, Revision 0, "BWR Stability Analysis:
Assessment of STAIF with Input from MICROBURN-B2," November.1 999.
- 21. NEDO-32465-A, "BWROG Reactor Core Stability Detect and Suppress Solutions Licensing Basis Methodology for Reload Applications," August 1996.
SUQUHNN NI.
TRI.23 EFETV DAE1/520
PPL Rev. 1 I
OPRM Instrumentation 3.3.9 3.3 Instrumentation 3.3.9 OPRM Instrumentation Configuration TRO 3.3.9 Oscillation Power Range Monitor (OPRM) supporting setpoints and settings shall be within the specified limits.
' APPLICABILITY:
ACTIONS Thermal POWER Ž25% RTP
-NNOTE-
- 1.
Separate Condition entry is allowed for each channel CONDITION-REQUIRED ACTION COMPLETION TIME A.
OPRM Setpoints and A.1' Enter the condition referenced in Immediately Settings not in accordance
'Table 3.3.9-1 for the parameter with Table 3.3.9-1 B. As required by Required B.1 Declare affected OPRM module
-Immediately Action A.1 and referenced inoperable.
in Table 3.3.9.1-C. As required by Required C.1 Restore the OPRM Setpoints and 120 days Action A.1 and referenced Settings to within the specified in Table 3.3.9-1 limits.
D. Alternate method to detect D.1 Initiate Action in accordance with Immediately and suppress thermal Conditions E, F, or G hydraulic instability oscillations required by LCO 3.3.1.3 Required Action A.3 or Required Action B.1 (continued)
SUSQUEHANNA - UNIT 1
.TRM / 3.3-22 EFFECTIVE DATE 11/15/2004
PPL Rev. I OPRM Instrumentation 3.3.9 ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIME E.
NOTE-Only applicable as required by Required Action D.1 E.f Place reactor mode switch in the Immediately Total core flow as a'sudwpoion function of THERMAL sudw oiin POWER within Region I of the Power Flow map as specified in the COLR.
OR Total core flow as a function of THERMAL POWER within Region II of the Power Flow map as specified in the COLR and less than 50% of required LPRM upscale alarms OPERABLE F. -NOTE Only applicable as required by Required Action D.1 and when in Region II of the Power Flow map as specified in the COLR.
Two or more APRM F.1 Place the reactor mode switch in Immediately readings oscillating with t
one or more oscillating
(continued)
SUSQUEHANNA - UNIT 1 -
7RM / 3.3-22a EFFECTIVE DATE 11/15/2004
OPRM Instrumental 3.3 tion
'.9 PPL Rev. 1.
CONDITION REQUIRED ACTION COMPLETION TIME F. (continued)
Two or more LPRM upscale alarms activating and deactivating with a period 21 second and <5 seconds.
OR Sustained LPRM oscillations >10 W/cm2 peak-to-peak with a period
Ž1 second and <5 seconds.
G. -NOTE Only applicable as required by Required Action D.1.
Total core flow as a G.1 Initiate action to restore total core Immediately function of THERMAL flow as a function of THERMAL POWER within Region II bf POWER outside of Region II.
the Power Flow map as specified in the COLR.
H.
Less than 50% of the H.1 Post sign on the reactor control 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> required LPRM Upscale panel that less than 50% of the Alarms are OPERABLE LPRM Upscale Alarms are OPERABLE.
SUSQUEHANNA - UNIT 1
.TRM / 3.3-22b UTEFFECTIVE DATE 11/15/2004
PPL Rev. 1 OPRM Instrumentation
- 3.3.9-TECHNICAL REQUIREMENT SURVEILLANCE SURVEILLANCE FREQUENCY 1-TRS 3.3.9.1I
.I. ^T#r "NUj 1 t Only required to be met when an alternate method to detect and suppress thermal hydraulic instability oscillations is required by LCO 3.3.1.3 Required Action A.3 or Required Action B.1.
Verify total core flow as a function of THERMAL POWER is outside of Region I and 11 of the Power Flow map as specified in the COLR.
24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> TRS 3.3.9.2 Perform CHANNEL CALIBRATION on each LPRM 24 months Upscale alarm 24 months TRS 3.3.9.3 Verify OPRM parameter setpoints and settings are.
within limits I
L' SUSQUEHANNA - UNIT 1
.TRM i 3.3-22c EFFECTIVE DATE 11/15/2004
OPRM Instrumentation
'3.3.9 PPL Rev. 1 Table 3.3.9-1 OPRM SETPOINTS AND SETTINGS.
CQNDITIONS REFERENCE D FROM OPRM REQUIRED PARAMETER DESCRIPTION' ACTION A.1 VALUE*'
- 1. TOL Period Confirmation Tolerance B.
0.10 and
- 0.30 sec 2., Ta Averaging Filter B
5sec
- 3. Fc Conditioning Filter Cutoff Frequency
' B 1.5 Hz
- 4. Tmin Minimum Oscillation Period B
'2 1.0 and
- 1.2 sec
- 5. Tmax Maximum Oscillation'Period B '
3.0 and
- 3.5 sec
- 6. Noise Floor Peak Discrimination Threshold B
- 7. Minimum Cell Operability, Requirement B
Ž2 LPRM/Cell
- 8. Si Peak Threshold Setpoint c(a) 2 1.10 and
- 1.20
- 9. S2 Valley Threshold Setpoint C '.
0.85 and
- 0.95
- 10. Smax Max. Amplitude Trip Setpoint
,c(a) 1.30 and
, 1.50.
- 11. DR3 Growth Rate Factor Setpoint Ca 2 1.30 and
" 1.60
- 12. T1 lo' S1 to S2 Timer Range '
c(a)
Ž0.3 sec
- 13. T1 hi SI to S2 Timer Range.
C(a) 2.5 sec
- 14. T2 lo S2 to(S3 or Smax) Timer Range C(a) 20.3 sec
- 15. T2 hi S2 to(S3 or Smax) Timer Range C-(a) 2.5 sec (a)
Applicable only when two channels'in the same trip system not in accordance with Table i
SUSQUEHANNA - UNIT 1
'. TRM / 3.3-22d EFFECTIVE DATE 11/15/2004
OPRM Instrumentation PPL Rev. 1 B 3.3.9 B 3.3.9 OPRM Instrumentation BASES TRO The OPRM system configuration governs its operation in accordance with the licensing analysis. 'Several configuration parameters are intrinsic to the trip function safety setpoint bases or provide settings for defense-in-depth algorithm features that are not assumed in the basis for the protection system safety analysis (Reference 2, Reference 3).
Each of the setting values may be used as the process setpoint or device setting without further adjustment for uncertainties.
Setpoints and Settings Bases TOL Period Confirmation Tolerance The specified range of values for the period tolerance has been demonstrated to provide continuous confirmations upon transition from stable reactor operation to a growing reactor instability.. A range of values is provided to allow system tuning to avoid spurious alarms on period confirmations. Limiting the setpoint adjustment range provides assurance that the Period Based Detection Algorithm will provide sufficient confirmations for a growing instability.
Ta Averaging Filter The averaging filter is used to provide a normalization of the input signal such that the average signal value is 1.0. The filter time constant is chosen to approximate the fuel thermal time constant. Setting optimizes system response during fast power transients.
Fc Conditioning Filter Cutoff Frequency The specified value'for the Conditioning Filter Cutoff Frequency has been demonstrated to provide continuous confirmations upon transition from stable reactor operation to a growing reactor instability. Setting minimizes impact on signal amplitude and provides assurance that the Period Based Detection Algorithm will provide sufficient confirmations for a growing instability..
Tmin Minimum Oscillation Period Tmax Maximum Oscillation Period The Minimum and Maximum Oscillation Period parameters establish the range of detectable oscillation periods of OPRM cell signals for signal oscillations associated with reactor core thermal-hydraulic instability.'
(continued),
SUSQUEHANNA-UNIT 1 TRM / B 3.3-17 EFFECTIVE DATE 11/15/2004
PPL Rev. 1 OPRM Instrumentation B 3.3.9 9
B 3.3.9 OPRM Instrumentation I BASES TRO (continued)
Noise Floor The period based algorithm uses a peak detection algorithm to determine the peaks and valleys of an OPRM cell signal. The Noise Floor setting assures that peaks and valleys are effectively detected for low amplitude cell signal resonances.
Minimum LPRM/Cell This value determines the availability and resulting sensitivity of cells in the reactor core in the event of LPRM channel failures. The minimum LPRM/cell is an assumption of the OPRM trip setpoint (Sp) basis calculation.
-Amplitude'and Growth Rate Algorithm Parameters Si S2 Smax DR3 TI lo T1 hi I Peak Threshold Setpoint Valley Threshold Setpoint Max. AmPlitude Trip Setpoint Growth Rate Factor Setpoint S1 to S2 Timer Range I S1 to S2 Timer Range T2 lo S2 to(S3 or Smax) Timer Range
'T2 hi S2 to(S3 or Smax) Timer Range These parameters calibrate the Amplitude and Growth Rate Algorithm, described in References 2 and 3, which provides an OPRM trip output to the Reactor Protection System. The OPRM design and licensing basis takes no credit for the Amplitude and Growth Rate Algorithm. The algorithm is provided as a defense-in-depth feature in the event of unanticipated power oscillations. These Amplitude and Growth Rate Algorithm Parameters are considered sufficient to. provide backup protection and to avoid spurious trips by maximizing margin to expected operating conditions and transients.
ACTIONS The required actions assure that the system settings that support the Period Based Algorithm setpoint analysis, and those parameters that define the Amplitude and Growth Rate Algorithm are returned in a timely manner to the values assumed in the analysis (Reference 2, Reference 3) or that the affected channel module is declared inoperable and the applicable Required Action of LCO 3.3.1.3 is then entered, or an alternate method to detect and suppress thermal hydraulic instability oscillations is employed.'
(continued)
SUSQUEHANNA -UNIT I
' TRM l B 3.3-17a EFFECTIVE DATE 11/15/2004 X..
I OPRM Instrumentation B 3.3.9 PPL Rev. 1 B 3.3.9 OPRM Instrumentation BASES ACTIONS Note 1 has been provided to modify the ACTIONS related to affected OPRM (continued) channels. Technical Specification Section 1.3, Completion Times, specifies that once a Condition has been entered, subsequent divisions, subsystems, components, or variables expressed in the Condition discovered to be inoperable or not within limits will not result in separate entry into the Condition. Technical Specification Section 1.3 also specifies that Required Actions of the Condition continue to apply for each additional failure, with Completion Times based on initial entry into the Condition. However, the Required Actions for affected OPRM modules and channels provide appropriate compensatory measures for separate modules and channels. As such, a Note has been provided that allows separate Condition entry for each affected OPRM channel.
B.1 Several parameter settings are essential for the proper operation of the OPRM period-based trip algorithm. The permissible values of Period Confirmation Tolerance, Averaging Filter time constant, Conditioning Filter Cutoff Frequency, and minimum operable LPRM per cell parameters are limited by the setpoint basis calculations and system transient response analysis. The Minimum and Maximum Oscillation Period settings limit the algorithm window to the cell signal resonances that can be associated with unstable thermal-hydraulic conditions. The Noise Floor setting assures that the cell signal peak detection algorithm is sufficiently responsive to low frequency and low amplitude cell signal resonances.
Because the ability of the OPRM module to perform its safety function is affected by these parameter settings, the affected module must be considered inoperable when these conditions are not met The cell signal processing parameters within each module affects the response and operability of only that module.
Channel operability is evaluated for each inoperable module and Required Actions taken in accordance with LCO 3.3.1.3.
C.1 The design objective for the growth rate and amplitude algorithms is to provide automatic action to limit the size of these unanticipated oscillations, thereby preventing fuel cladding damage. Several parameter settings define the function of the Amplitude and Growth Rate Algorithm. The OPRM design and licensing basis takes no credit for the Amplitude and Growth Rate Algorithm, which is provided as a defense-in-depth feature in the event of unanticipated oscillations.
(continued)
.1 I SUSQUEHANNA - UNIT 1 I. TRM / B 3.3-17b EFFECTIVE DATE 11/15/2004 I
OPRM Instrumentation PPL Rev. 1 B 3.3.9 B 3.3.9 OPRM Instrumentation BASES ACTIONS C.1 (continued)
Because the ability of the OPRM module to perform its safety function is not affected by these parameter settings, the affected module need not be immediately considered inoperable when these conditions are not met.
These parameters are to be maintained for conformance with the licensing requirement of a defense-in-depth feature in addition to the licensed OPRM trip function. This is corrected by returning the parameters to conformance within 120 days of identification.
Since the Amplitude and Growth Rate parameters within each module affect only the defense-in-depth response within each channel module, failure to maintain the proper parameters in either module in the channel affects only the operability of that module. The trip channel requires only one operable module function, and the trip system requires only one channel for this backup function to be operable.
D.1 This Action is to be taken if the Period Based Detection Algorithm trip function is not available in accordance with LCO 3.3.1.3, and initiation of an alternate method to Detect and Suppress thermal hydraulic instability oscillations is required by the referenced LCO Required Actions. The applicable Conditions are entered as required.
E.1 As directed from Required Action D.1, this Action provides preemptive protection through Power/Flow Map operating restrictions When operating in Region I of the Power. Flow map specified in the COLR, orwhen operating in Region I of the Power / Flow map specified in the COLR with less than 50% of the required LPRM upscale alarms are OPERABLE, the potential for thermal-hydraulic oscillations is greatly increased and sufficient margin may not be available for operator response to suppress potential thermal-hydraulic oscillations. Therefore, the reactor mode switch must be immediately placed in the shutdown position. Action is taken immediately to place the plant in a condition where any potential for thermal-hydraulic instabilities will be terminated.
- (continued)
'SUSQUEHANNA - UNIT I TRM IB 3.3-17c EFFECTIVE DATE 11/151204
OPRM Instrumentation PPL Rev. 1 B 3.3.9
- B 3.3.9 OPRM Instrumentation BASES ACTIONS F.1 (continued)
As directed from Required Action D.1, this Action provides guidance for Operator action in response to thermal-hydraulic instability oscillations.
When operating in Region 11 of the Power/Flow map specified in the COLR immediate response is necessary when there are indications that thermal hydraulic oscillations are occurring as defined in the CONDITION.
LPRM upscale alarms are required to detect reactor core thermal-hydraulic instability events. The criteria for determining which LPRM upscale alarms are required is based on assignment of these alarms to designated core zones. These 'core zones consist of the level A, B, and C alarms in 4 or 5 adjacent LPRM strings. The number and location of LPRM strings in each zone assure that with 50% or more of the associated LPRM upscale alarms OPERABLE sufficient monitoring capability is available to detect core wide and regional oscillations. Operating plant instability data is used to determine the specific LPRM strings assigned to each zone.
G.1 As directed from Required Action D.1, this Action provides guidance for
-Operator action in response to operation in conditions that may lead to thermal-hydraulic instability oscillations.
When operating in Region II of the Power/Flow map specified in the COLR, the potential for thermal-hydraulic oscillations is increased and sufficient margin may not be available for operator response to suppress potential thermal-hydraulic oscillations. Therefore, action must be initiated immediately to restore operation outside of Regions II of the Power/Flow map specified in the COLR. This can be accomplished by either decreasing THERMAL POWER with control rod insertion or increasing core flow by increasing recirculation pump speed. The starting of a recirculation pump will not be used as a means to exit the excluded Regions because the starting of a recirculation pump with the plant operating above the 80% rod line is prohibited due to potential instability problems.
(continued)
SUSQUEHANNA - UNIT I TRM B 3.3-17d EFFECTIVE DATE 11-15/2004
OPRM Instrumentation B 3.3.9 PPL Rev. I B 3.3.9 OPRM Instrumentation BASES ACTIONS (continued)
H.1 The LPRMs provide a capability to monitor power in selected locations of the reactor core. The LPRM Upscale Alarm Instrumentation provides information concerning local power oscillations. Condition G requires a reactor scram when operating in Region II of the PowerlFlow map specified in the COLR-with indications that thermal hydraulic oscillations are occurring. The number and location of LPRM strings in each zone assures'that with 50% or more of the associated LPRM upscale alarms OPERABLE any power oscillations which could occur would be detected and proper actions can be taken.
A sign is posted in the Control Room to ensure that plant operators are
-aware of the system condition if a plant transient results in the plant entering into the instability region.
X TRS TRS 3.3.9.1 Required only when the OPRM trip function is not available, this TRS ensures the combination of core flow and THERMAL POWER'are within required limits to prevent uncontrolled thermal hydraulic oscillations by ensuring the recirculation loops are within the limits established by the Power
/ Flow map'specified-in the COLR. At low recirculation flows and high reactor power, the reactor exhibits increased susceptibility to thermal-hydraulic
'instability. The Power / Flow map specified in the COLR is based on guidance provided in References 7, 8, and 9 which' also provided the guidance'on how to respond to operation in these conditions. The 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> Frequency is based on operating experience and the operators inherent knowledge of the current reactor status, including significant changes in THERMAL POWER and core flow to ensure the requirements are constantly met.
TRS 3.3.9.2 This TRS is to be performed at the specified Frequency to ensure that the LPRM Upscale Alarm Instrumentation are maintained OPERABLE.
-N (continued)
SUSQUEHANNA -UNIT I
- TRM / B3.3-17e EFFECTIVE DATE 11/15/2004
PPL Rev. 1 OPRM Instrumentation B 3.3.9 B 3.3.9 OPRM Instrumentation BASES TRS TRS 3.3.9.3 (continued)
( u The parameter setpoint verification surveillance compares the desired settings and setpoints'to the' values contained in the processor memory.
This surveillance is required to assure that the settings are maintained in accordance with the setpoint analysis. The frequency is based on the OPRM CALIBRATION frequency per SR 3.3.1.3.3.
REFEREN CES
- 1. NEDO-31960-A, BWROG Long Term Solution Licensing Methodology
- 2. NEDO-31960-A, Supp. 1, BWROG Long Term Solution Licensing Methodology
- 3. NEDO-32465-A, BWROG Reactor Stability Detect and Suppress Solutions Licensing Basis Methodology and Reload Applications
-4. ' ENPD-400-P-A, 'Generie Topical Report for the ABB Option Ill OPRM
- 5. Generic Letter 94-02, Long-Term Solutions and Upgrade Of Interim Operating Recommendations for Thermal-Hydraulic Instabilities in Boiling Water Reactors
- 6. LCO 3.3.1.3, OPRM Instrumentation
- 7. GE Service Information Letter No. 380, "BWR Core Thermal Hydraulic Stability," Revision 1,' February 10, 1984.
8.' Letter, L. A. England to M. J. Virgilio, OBWR Owner's Group Guidelines for Stability Interim Corrective Action," June 6,1994.
- 9. EMF-CC-074(P)(A), Volume 4, Revision 0, "BWR Stability Analysis:
Assessment of STAIF with Input from MICROBURN-B2,M November 1999.
SUSQUEHANNA - UINIT 1 TRM / B 3.3-17f EFFECTIVE DATE 11/15/2004