ML071070403
| ML071070403 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 04/04/2007 |
| From: | Susquehanna |
| To: | Document Control Desk, NRC/NRR/ADRO |
| References | |
| 028401 | |
| Download: ML071070403 (72) | |
Text
Apr.
04, 2007 Page 1
of 2
MANUAL HARD COPY DISTRIBUTION DOCUMENT TRANSMITTAL 2007-13346 USER INFORMATIO AddrJCSA2 n~e#:2N194 EMPL#:028401 CA#:
0363 TRANSMITTAL INFORMATION:
TO:
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'iW 04/04/2007 LOCATION:
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ATTENTION:
"REPLACE" directions do not affect the Table of Contents, Therefore no TOC will be issued with the updated material.
TRM2 -
TECHNICAL REQUIREMENTS MANUAL UNIT 2 REMOVE MANUAL TABLE OF CONTENTS DATE: 03/28/2007 ADD MANUAL TABLE OF CONTENTS DATE: 04/03/2007 CATEGORY:
DOCUMENTS TYPE: TRM2 AoC~i
Apr.
04, 2007 Page 2
of 2
ID:
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6 CATEGORY:
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- USERS, ELECTRONICALLY REVIEW THE APPROPRIATE DOCUMENTS AND ACKNOWLEDGE COMPLETE IN YOUR NIMS INBOX.
I SSES MADUAL Manual Name:
TRM2 Manual
Title:
TECHNICAL REQUIREMENTS MANUAL UNIT 2 Table Of Contents Issue Date:
0 Procedure Name TEXT LOES
Title:
LIST OF EF
)4/03/2007 Rev 32 FECTIVE SECTIONS Issue Date 04/03/2007 Change ID Change Number TEXT TOC
Title:
9 12/14/2006 TABLE OF CONTENTS TEXT 1.1 0
11/19/2002
Title:
USE AND APPLICATION DEFINITIONS K'
/\\
/
TEXT 2.1 1
02/04/2005\\\\ \\
N',,
Title:
PLANT PROGRAMS AND SETPOINTS PLANT,-PROGRAMS' /
TEXT 2.2 5
1112212,005 /
Title:
PLANT PROGRAMS AND SETPOINTS//INSTRUMENT TRIP SETPOINT TABLE TEXT 3.0
Title:
'2 01/29/2007
- PCBI/ T N
F, APPLICABILITY TECHNICAL REQU~IREMENT FOR OPERATION (TRO)
APPLICABILITY TEXT 3.1.1 0-11/19/2002
Title:
REACTIVITYtONTRObL -SYSTEMS ANTICIPATED TRANSIENT WITHOUT SCRAM ALTERNATE ROD INJECTION,(ATWS"ARI)
INSTRUMENTATION TEXT 3.1.2 0/
/
0 11/19/2002
Title:
REACTIVITY CONTROL SYSTEMS* CONTROL ROD DRIVE (CRD)
HOUSING SUPPORT TEXT 3.1.3 2
11/22/2005
Title:
REACTIVITY CONTROL SYSTEMS CONTROL ROD BLOCK INSTRUMENTATION TEXT 3.1.4 0
11/19/2002
Title:
REACTIVITY CONTROL SYSTEMS CONTROL ROD SCRAM ACCUMULATORS INSTRUMENTATION AND CHECK VALVE TEXT 3.2.1 6
04/03/2007
Title:
CORE OPERATING LIMITS CORE OPERATING LIMITS REPORT (COLR)
Pae1 of1 eor ae 0/30 Page -1 of 15 Report Date: 04/03/07
SSES MANUJAL Manual Name:
TRM2 IManual
Title:
TECHNICAL REQUIREMENTS MANUAL UNIT 2 TEXT 3.3.1 0
11/19/2002
Title:
INSTRUMENTATION RADIATION MONITORING INSTRUMENTATION TEXT 3.3.2 1
04/26/2006
Title:
INSTRUMENTATION SEISMIC MONITORING INSTRUMENTATION TEXT 3.3.3
Title:
INSTRUMENTATION 1
04/26/2006 METEOROLOGICAL MONITORING INSTRUMENTATION TEXT 3.3.4 2
06/13/2006
Title:
INSTRUMENTATION TRM POST-ACCIDENT MONITORING INSTRUMENTATION TEXT 3.3.5 0
11/19/2002
Title:
INSTRUMENTATION THIS PAGE INTENTIONALLY LEFT BLANK TEXT 3.3.6 2
10/19/2005
Title:
INSTRUMENTATION TRM ISOLATION ACTUATION INSTRUMENTATION TEXT 3.3.7 0
11/19/2002
Title:
INSTRUMENTATION MAIN TURBINE OVERSPEED PROTECTION SYSTEM TEXT 3.3.8 1
10/22/2003
Title:
INSTRUMENTATION TRM RPS INSTRUMENTATION TEXT 3.3.9
Title:
INSTRUMENTATION TEXT 3.3.10
Title:
INSTRUMENTATION 1
11/22/2004 LPRM UPSCALE ALARM INSTRUMENTATION 1
12/14/2004 REACTOR RECIRCULATION PUMP MG SET STOPS TEXT 3.3.11 1
10/22/2003
Title:
INSTRUMENTATION MVP ISOLATION INSTRUMENTATION TEXT 3.4.1 1
04/26/2006
Title:
REACTOR COOLANT SYSTEM REACTOR COOLANT SYSTEM CHEMISTRY Page 2 of 15 Report Date: 04/03/07 Page 2 of
.15 Report Date: 04/03/07
SSES MANUAL Manual Name:
TRM2
'Manual
Title:
TECHNICAL REQUIREMENTS MANUAL UNIT 2 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
11/19/2002 COOLANT SYSTEM STRUCTURAL INTEGRITY 0
11/19/2002 COOLANT SYSTEM REACTOR COOLANT SYSTEM (RCS) 1 12/14/2004 COOLANT SYSTEM REACTOR RECIRCULATION FLOW AND ROD LINE LIMIT 1
04/26/2006 COOLANT SYSTEM REACTOR VESSEL MATERIALS 1
02/04/2005
Title:
ECCS AND RCIC ADS MANUAL INHIBIT TEXT 3.5.2 0
11/19/2002
Title:
ECCS AND RCIC ECCS AND RCIC SYSTEM MONITORING INSTRUMENTATION TEXT 3.5.3 0
11/19/2002
Title:
ECCS AND RCIC LONG TERM NITROGEN SUPPLY TO ADS TEXT'3.6.1 0
11/19/2002
Title:
CONTAINMENT VENTING OR PURGING TEXT 3.6.2 0
11/19/2002
Title:
CONTAINMENT SUPPRESSION CHAMBER-TO-DRYWELL VACUUM BREAKER POSITION INDICATION TEXT 3.6.3 0
11/19/2002
Title:
CONTAINMENT SUPPRESSION POOL ALARM INSTRUMENTATION TEXT 3.6.4 0
11/19/2002
Title:
CONTAINMENT PRIMARY CONTAINMENT CLOSED SYSTEM BOUNDARIES TEXT 3.7.1 0
11/19/2002
Title:
PLANT SYSTEMS EMERGENCY SERVICE WATER SYSTEM (ESW)
SHUTDOWN Page 3 of 15 Report Date: 04/03/07
SSES MANUAL Manual Name:
TRM2
'Manual
Title:
TECHNICAL REQUIREMENTS MANUAL UNIT 2 TEXT 3.7.2 0
11/19/2002
Title:
PLANT SYSTEMS ULTIMATE HEAT SINK (UHS)
AND GROUND WATER LEVEL TEXT 3.7.3.1
Title:
PLANT TEXT 3.7.3.2
Title:
PLANT TEXT 3.7.3.3
Title:
PLANT TEXT 3.7.3.4
Title:
PLANT TEXT 3.7.3.5
Title:
PLANT TEXT 3.7.3.6
Title:
PLANT TEXT 3.7.3.7
Title:
PLANT TEXT 3.7.3.8
Title:
PLANT TEXT 3.7.4
Title:
PLANT TEXT 3.7.5.1
Title:
PLANT TEXT 3.7.5.2
Title:
PLANT 1
04/26/2006 SYSTEMS FIRE SUPPRESSION WATER SUPPLY SYSTEM 2
04/26/2006 SYSTEMS SPRAY AND SPRINKLER SYSTEMS 2
SYSTEMS C02 SYSTEMS 1
SYSTEMS HALON SYSTEMS 08/18/2005 04/26/2006 SYSTEMS FIRE SYSTEMS YARD SYSTEMS FIRE SYSTEMS FIRE 1
04/26/2006 HOSE STATIONS 1
04/26/2006 FIRE HYDRANTS AND HYDRANT HOSE HOUSES 1
04/26/2006 RATED ASSEMBLIES 6
12/14/2006 DETECTION INSTRUMENTATION 1
04/26/2006 SYSTEMS SOLID RADWASTE SYSTEM 0
11/19/2002 SYSTEMS MAIN CONDENSER OFFGAS HYDROGEN MONITOR 0
11/19/2002 SYSTEMS MAIN CONDENSER OFFGAS EXPLOSIVE GAS MIXTURE Page 4 of 15 Report Date: 04/03/07 Page 4 of 15 Report Date: 04/03/07
SSES MANUAL Manual Name:
TRM2
'Manual
Title:
TECHNICAL REQUIREMENTS MANUAL UNIT 2 TEXT 3.7.5.3 1
04/26/2006
Title:
PLANT SYSTEMS LIQUID HOLDUP TANKS TEXT 3.7.6 1
03/01/2005
Title:
PLANT SYSTEMS ESSW PUMPHOUSE VENTILATION TEXT 3.7.7 0
11/19/2002
Title:
PLANT SYSTEMS MAIN CONDENSER OFFGAS PRETREATMENT LOGARITHMIC RADIATION MONITORING INSTRUMENTATION TEXT 3.7.8 5
10/12/2006
Title:
PLANT SYSTEMS SNUBBERS TEXT 3.7.9 1
08/28/2006
Title:
PLANT SYSTEMS CONTROL STRUCTURE HVAC TEXT 3.7.10 1
12/14/2004
Title:
PLANT SYSTEMS SPENT FUEL STORAGE POOLS (SFSPS)
TEXT 3.8.1
Title:
ELECTRICAL PROTECTIVE TEXT 3.8.2.1
Title:
ELECTRICAL CONTINUOUS TEXT 3.8.2.2
Title:
ELECTRICAL AUTOMATIC 2
02/04/2005 POWER PRIMARY CONTAINMENT PENETRATION CONDUCTOR OVERCURRENT DEVICES 1
12/14/2004 POWER MOTOR OPERATED VALVES (MOV)
THERMAL OVERLOAD 2
12/14/2004 POWER MOTOR OPERATED VALVES (MOV)
THERMAL OVERLOAD PROTECTION PROTECTION TEXT 3.8.3 0
11/19/2002
Title:
ELECTRICAL POWER DIESEL GENERATOR (DG)
MAINTENANCE ACTIVITIES TEXT 3.8.4
Title:
ELECTRICAL 1
02/04/2005 POWER 24 VDC ELECTRICAL SUBSYSTEM TEXT 3.8.5 0
11/19/2002
Title:
ELECTRICAL POWER DEGRADED VOLTAGE PROTECTION Page 5 of 15 Report Date: 04/03/07 Page 5 of
.15 Report Date: 04/03/07
SSES MANUAL Manual Name:
TRM2 S
Manual
Title:
TECHNICAL REQUIREMENTS MANUAL UNIT 2 TEXT 3.8.6 0
11/19/2002
Title:
ELECTRICAL POWER EMERGENCY SWITCHGEAR ROOM COOLING TEXT 3.8.7 0
12/14/2006
Title:
BATTERY MAINTENANCE AND MONITORING PROGRAM TEXT 3.9.1 0
11/19/2002
Title:
REFUELING OPERATIONS DECAY TIME TEXT 3.9.2 0
11/19/2002
Title:
REFUELING OPERATIONS COMMUNICATIONS TEXT 3.9.3 0
11/19/2002
Title:
REFUELING OPERATIONS REFUELING PLATFORM TEXT 3.10.1
Title:
MISCELLANEOUS TEXT 3.10.2
Title:
MISCELLANEOUS 1
04/26/2006 SEALED SOURCE CONTAMINATION 0
11/19/2002 SHUTDOWN MARGIN TEST RPS INSTRUMENTATION TEXT 3.10.3 1
04/26/2006
Title:
MISCELLANEOUS INDEPENDENT SPENT FUEL STORAGE INSTALLATION (ISFSI)
TEXT 3.10.4 1
08/28/2006
Title:
MISCELLANEOUS LEADING EDGE FLOW METER (LEFM)
TEXT 3.11.1.1 1
04/26/2006
Title:
RADIOACTIVE EFFLUENTS LIQUID EFFLUENTS CONCENTRATION TEXT 3.11.1.2 1
04/26/2006
Title:
RADIOACTIVE EFFLUENTS LIQUID EFFLUENTS DOSE TEXT 3.11.1.3 1
04/26/2006
Title:
RADIOACTIVE EFFLUENTS LIQUID WASTE TREATMENT SYSTEM Page 6 of 15 Report Date: 04/03/07 Pagek of 15 Report Date: 04/03/07
SSES MANU1TAL Manual Namee:
TRM2 b
Manual
Title:
TECHNICAL REQUIREMENTS MANUAL UNIT 2 TEXT 3.11.1.4
Title:
RADIOACTIVE TEXT 3.11.1.5
Title:
RADIOACTIVE TEXT 3.11.2.1
Title:
RADIOACTIVE TEXT 3.11.2.2
Title:
RADIOACTIVE TEXT 3.11.2.3
Title:
RADIOACTIVE FORM TEXT 3.11.2.4
Title:
RADIOACTIVE TEXT 3.11.2.5
Title:
RADIOACTIVE TEXT 3.11.2.6
Title:
RADIOACTIVE TEXT 3.11.3
Title:
RADIOACTIVE TEXT 3.11.4.1
Title:
RADIOACTIVE TEXT 3.11.4.2
Title:
RADIOACTIVE TEXT 3.11.4.3
Title:
RADIOACTIVE EFFLUENTS EFFLUENTS EFFLUENTS EFFLUENTS EFFLUENTS EFFLUENTS 1
12/14/2004 LIQUID RADWASTE EFFLUENT MONITORING INSTRUMENTATION 1
12/14/2004 RADIOACTIVE LIQUID PROCESS MONITORING INSTRUMENTATION 3
04/26/2006 DOSE RATE 1
04/26/2006 DOSE NOBLE GASES 1
04/26/2006 DOSE -
11/19/2002 GASEOUS RADWASTE TREATMENT SYSTEM EFFLUENTS EFFLUENTS 3
11/14/2006 VENTILATION EXHAUST
- 2.
12/14/2004 RADIOACTIVE GASEOUS TREATMENT SYSTEM EFFLUENT MONITORING INSTRUMENTATION EFFLUENTS EFFLUENTS EFFLUENTS EFFLUENTS 1
04/26/2006 TOTAL DOSE 3
04/26/2006 MONITORING PROGRAM 2
04/26/2006 LAND USE CENSUS 1
04/26/2006 INTERLABORATORY COMPARISON PROGRAM Pae7 o
5RprtDt:0/30 Page 7 of
.15 Report Date: 04/03/07
SSES MANUAL Manual Name:
TRM2 Manual
Title:
TECHNICAL REQUIREMENTS MANUAL UNIT 2 TEXT 3.12.1 0
11/19/2002
Title:
LOADS CONTROL PROGRAM CRANE TRAVEL-SPENT FUEL STORAGE POOL TEXT 3.12.2 1
10/12/2006
Title:
LOADS CONTROL PROGRAM HEAVY LOADS REQUIREMENTS TEXT 3.12.3 0
11/19/2002
Title:
LOADS CONTROL PROGRAM LIGHT LOADS REQUIREMENTS TEXT B3.0 2
01/29/2007
Title:
APPLICABILITY BASES TECHNICAL REQUIREMENT FOR OPERATION (TRO)
APPLICABILITY TEXT B3.1.1 0
11/19/2002
Title:
REACTIVITY CONTROL SYSTEM BASES ANTICIPATED TRANSIENT WITHOUT SCRAM ALTERNATE ROD INJECTION (ATWS-ARI)
INSTRUMENTATION TEXT B3.1.2 0
11/19/2002
Title:
REACTIVITY CONTROL SYSTEM BASES CONTROL ROD DRIVE (CRD)
HOUSING SUPPORT TEXT B3.1.3 2
11/22/2005
Title:
REACTIVITY CONTROL SYSTEM BASES CONTROL ROD BLOCK INSTRUMENTATION TEXT 'B3.1.4 0
11/19/2002
Title:
REACTIVITY CONTROL SYSTEM BASES CONTROL ROD SCRAM ACCUMULATORS INSTRUMENTATION AND CHECK VALVE TEXT B3.2.1 0
11/19/2002
Title:
CORE OPERATING LIMITS BASES CORE OPERATING LIMITS REPORT (COLR)
TEXT B3.3.1 0
11/19/2002
Title:
INSTRUMENTATION BASES RADIATION MONITORING INSTRUMENTATION TEXT B3.3.2 0
11/19/2002
Title:
INSTRUMENTATION BASES SEISMIC MONITORING INSTRUMENTATION TEXT B3.3.3 1
02/04/2005
Title:
INSTRUMENTATION BASES METEOROLOGICAL MONITORING INSTRUMENTATION Page 8 of 15 Report Date: 04/03/07
SSES MANUAL Manual Name:
TRM2 Manual
Title:
TECHNICAL REQUIREMENTS MANUAL UNIT 2 TEXT B3.3.4
Title:
INSTRUMENTATION TEXT B3.3.5
Title:
INSTRUMENTATION TEXT B3.3.6
Title:
INSTRUMENTATION TEXT B3.3.7
Title:
INSTRUMENTATION TEXT B3.3.8
Title:
INSTRUMENTATION TEXT B3.3.9
Title:
INSTRUMENTATION TEXT B3.3.10
Title:
INSTRUMENTATION TEXT B3.3.11
Title:
INSTRUMENTATION TEXT B3.4.1
Title:
REACTOR COOLANT TEXT B3.4.2
Title:
REACTOR COOLANT TEXT B3.4.3
Title:
REACTOR COOLANT TEXT B3.4.4
Title:
06/13/2006 BASES TRM POST ACCIDENT MONITORING (PAM)
INSTRUMENTATION 1
06/13/2006 BASES THIS PAGE INTENTIONALLY LEFT BLANK 3
10/19/2005 BASES TRM ISOLATION ACTUATION INSTRUMENTATION 0
11/19/2002 BASES MAIN TURBINE OVERSPEED PROTECTION SYSTEM 1
10/22/2003 BASES TRM RPS 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 0
11/19/2002 SYSTEM BASES REACTOR COOLANT SYSTEM CHEMISTRY 0
11/19/2002 SYSTEM BASES STRUCTURAL INTEGRITY 0
11/19/2002 SYSTEM BASES HIGH/LOW PRESSURE INTERFACE LEAKAGE MONITOR 0
11/19/2002 SYSTEM BASES REACTOR RECIRCULATION FLOW AND ROD LINE LIMIT Page 9 of 15 Report Date: 04/03/07 Page 9 of 15 Report Date: 04/03/07
SSES MANUAL Manual Name:
TRM2
'Manual
Title:
TECHNICAL REQUIREMENTS MANUAL UNIT 2 TEXT B3.4.5 0
11/19/2002
Title:
REACTOR COOLANT SYSTEM BASES REACTOR VESSEL MATERIALS TEXT B3.5.1 0
11/19/2002
Title:
ECCS AND RCIC BASES ADS MANUAL INHIBIT TEXT B3.5.2 0
11/19/2002
Title:
ECCS AND RCIC BASES ECCS AND RCIC SYSTEM MONITORING INSTRUMENTATION TEXT B3.5.3 0
11/19/2002
Title:
ECCS AND RCIC BASES LONG TERM NITROGEN SUPPLY TO ADS TEXT B3.6.1 0
11/19/2002
Title:
CONTAINMENT BASES VENTING OR PURGING TEXT B3.6.2 0
11/19/2002
Title:
CONTAINMENT BASES SUPPRESSION CHAMBER-TO-DRYWELL VACUUM BREAKER POSITION INDICATION TEXT B3.6.3 0
11/19/2002
Title:
CONTAINMENT BASES SUPPRESSION POOL ALARM INSTRUMENTATION TEXT 'B3.6.4 1
12/14/2004
Title:
CONTAINMENT BASES PRIMARY CONTAINMENT CLOSED SYSTEM BOUNDARIES TEXT B3.7.1 0
11/19/2002
Title:
PLANT SYSTEMS BASES EMERGENCY SERVICE WATER SYSTEM (SHUTDOWN)
TEXT B3.7.2 0
11/19/2002
Title:
PLANT SYSTEMS BASES ULTIMATE HEAT SINK (UHS)
GROUND WATER LEVEL TEXT B3.7.3.1 1
04/26/2006
Title:
PLANT SYSTEMS BASES FIRE SUPPRESSION WATER SUPPLY SYSTEM TEXT B3.7.3.2 2
04/26/2006
Title:
PLANT SYSTEMS BASES SPRAY AND SPRINKLER SYSTEMS Page i__0 of 15 Report Date: 04/03/07
SSES MANJAL Manual Name:
TRM2
'Manual
Title:
TECHNICAL REQUIREMENTS MANUAL UNIT 2 TEXT B3.7.3.3
Title:
PLANT TEXT B3.7.3.4
Title:
PLANT TEXT B3.7.3.5
Title:
PLANT TEXT B3.7.3.6
Title:
PLANT TEXT B3.7.3.7
Title:
PLANT TEXT B3.7.3.8
Title:
PLANT TEXT B3.7.4
Title:
PLANT TEXT B3.7.5.1
Title:
PLANT TEXT B3.7.5.2
Title:
PLANT TEXT B3.7.5.3
Title:
PLANT TEXT B3.7.6
Title:
PLANT SYSTEMS BASES SYSTEMS BASES SYSTEMS BASES 0
11/19/2002 C02 SYSTEMS 1
04/26/2006 HALON SYSTEMS 1
04/26/2006 FIRE HOSE STATIONS 1
04/26/2006 YARD FIRE HYDRANTS AND SYSTEMS BASES HYDRANT HOSE HOUSES SYSTEMS BASES SYSTEMS BASES SYSTEMS BASES SYSTEMS BASES SYSTEMS BASES SYSTEMS BASES SYSTEMS BASES 0
11/19/2002 FIRE RATED ASSEMBLIES 1
01/12/2004 FIRE DETECTION INSTRUMENTATION 0
11/19/2002 SOLID RADWASTE SYSTEM 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 1
03/01/2005 ESSW PUMPHOUSE VENTILATION TEXT B3.7.7 0
11/19/2002
Title:
PLANT SYSTEMS BASES MAIN CONDENSER OFFGAS PRETREATMENT LOGARITHMIC RADIATION MONITORING INSTRUMENTATION Page 11 of 15 Report Date: 04/03/07
SSES MANUAL Manual Name:
TRM2
'Manual
Title:
TECHNICAL REQUIREMENTS MANUAL UNIT 2 TEXT B3.7.8
Title:
PLANT TEXT B3.7.9
Title:
PLANT TEXT B3.7.10
Title:
PLANT 2
SNUBBERS 10/12/2006 SYSTEMS BASES SYSTEMS BASES SYSTEMS BASES 1
12/14/2004 CONTROL STRUCTURE HVAC.
1 12/14/2004 SPENT FUEL STORAGE POOLS TEXT B3.8.1 1
02/04/2005
Title:
ELECTRICAL POWER BASES PRIMARY CONTAINMENT PENETRATION CONDUCTOR OVERCURRENT PROTECTIVE DEVICES TEXT B3.8.2.1
Title:
ELECTRICAL CONTINUOUS TEXT B3.8.2.2
Title:
ELECTRICAL AUTOMATIC TEXT B3.8.3
Title:
ELECTRICAL TEXT'B3.8.4
Title:
ELECTRICAL TEXT B3.8.5
Title:
ELECTRICAL TEXT B3.8.6
Title:
ELECTRICAL TEXT B3.8.7 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 -
0 11/19/2002 POWER BASES DIESEL GENERATOR (DG)
MAINTENANCE 0
11/19/2002 POWER BASES 24 VDC ELECTRICAL POWER SUBSYSTEM 0
11/19/2002 POWER BASES DEGRADED VOLTAGE PROTECTION 1
02/04/2005 POWER BASES EMERGENCY SWITCHGEAR ROOM COOLING 0
12/14/2006 ACTIVITIES
Title:
BATTERY MAINTENANCE AND MONITORING PROGRAM TEXT B3.9.1 0
11/19/2002
Title:
REFUELING OPERATIONS BASES DECAY TIME Page 12 of 15 Report Date: 04/03/07 Page 12.
of
.15 Report Date: 04/03/07
SSES MANUAL Manual Name:
TRM2 Manual
Title:
TECHNICAL REQUIREMENTS MANUAL UNIT 2 TEXT B3.9.2 0
Title:
REFUELING OPERATIONS BASES 11/19/2002 COMMUNICATIONS TEXT B3.9.3 0
11/19/2002
Title:
REFUELING OPERATIONS BASES REFUELING PLATFORM TEXT B3.10.1
Title:
MISCELLANEOUS TEXT B3.10.2 0
11/19/2002 BASES SEALED SOURCE CONTAMINATION 0
11/19/2002
Title:
MISCELLANEOUS BASES SHUTDOWN MARGIN TEST RPS INSTRUMENTATION TEXT B3.10.3 0
11/19/2002
Title:
MISCELLANEOUS BASES INDEPENDENT SPENT FUEL STORAGE INSTALLATION (ISFSI)
TEXT B3.10.4 0
Title:
MISCELLANEOUS BASES LEADING 11/19/2002 EDGE FLOW METER (LEFM)
TEXT B3.11.1.1
Title:
RADIOACTIVE TEXT B3.11.1.2
Title:
RADIOACTIVE TEXT B3.11.1.3
Title:
RADIOACTIVE TEXT B3.11.1.4
Title:
RADIOACTIVE TEXT B311.1.5
Title:
RADIOACTIVE 0
11/19/2002 EFFLUENTS BASES LIQUID EFFLUENTS CONCENTRATION 0
11/19/2002 EFFLUENTS BASES LIQUID EFFLUENTS DOSE 0
11/19/2002 EFFLUENTS BASES LIQUID WASTE TREATMENT SYSTEM 0
11/19/2002 EFFLUENTS BASES LIQUID RADWASTE EFFLUENT MONITORING INSTRUMENTATION 0
11/19/2002 EFFLUENTS BASES RADIOACTIVE LIQUID PROCESS MONITORING INSTRUMENTATION TEXT B3.11.2.1 1
12/14/2004
Title:
RADIOACTIVE EFFLUENTS BASES DOSE RATE Page 13.
of 15 Report Date: 04/03/07 Page 13 of
.15 Report Date: 04/03/07
SSES MANUAL Manual Name:
TRM2
'Manual
Title:
TECHNICAL REQUIREMENTS MANUAL UNIT 2 TEXT B3.11.2.2
Title:
RADIOACTIVE EFFLUENTS TEXT B3.11.2.3
Title:
RADIOACTIVE EFFLUENTS PARTICULATES FORM TEXT B3.11.2.4
Title:
RADIOACTIVE EFFLUENTS TEXT B3.11.2.5
Title:
RADIOACTIVE EFFLUENTS TEXT B3.11.2.6
Title:
RADIOACTIVE EFFLUENTS INSTRUMENTATION TEXT B3.11.3
Title:
RADIOACTIVE EFFLUENTS TEXT B3.11.4.1
Title:
RADIOACTIVE EFFLUENTS 0
11/19/2002 BASES DOSE -
NOBLE GASES 0
11/19/2002 BASES DOSE -
11/19/2002 BASES GASEOUS RADWASTE TREATMENT SYSTEM 4
11/14/2006 BASES VENTILATION EXHAUST TREATMENT SYSTEM 1
01/27/2004 BASES RADIOACTIVE GASEOUS EFFLUENT MONITORING 0
11/19/2002 BASES TOTAL DOSE 2
01/06/2006 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 TEXT B3.11.4.2
Title:
RADIOACTIVE TEXT B3.11.4.3
Title:
RADIOACTIVE EFFLUENTS 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 Page 14 of 15 Report Date: 04/03/07 Page 14 of 15 Report Date: 04/03/07
SSES MANUAL Manual Name:
TRM2
'Manual
Title:
TECHNICAL REQUIREMENTS MANUAL UNIT 2 TEXT 4.1
Title:
TEXT 4.2
Title:
TEXT 4.3
Title:
TEXT 4.4
Title:
TEXT 4.5
Title:
TEXT 4.6
Title:
0 CONTROLS 09/27/2003 ORGANIZATION ADMINISTRATIVE ADMINISTRATIVE ADMINISTRATIVE ADMINISTRATIVE ADMINISTRATIVE 0
09/27/2003 CONTROLS REPORTABLE EVENT ACTION 0
09/27/2003 CONTROLS SAFETY LIMIT VIOLATION 0
09/27/2003 CONTROLS PROCEDURES & PROGRAMS 0
09/27/2003 CONTROLS REPORTING REQUIREMENTS 09/27/2003 RADIATION PROTECTION PROGRAM ADMINISTRATIVE CONTROLS TEXT 4.7 0
09/27/2003
Title:
ADMINISTRATIVE CONTROLS TRAINING Page 2~
of 15 Report Date: 04/03/07 Page 15 of 15 Report Date: 04/03/07
SUSQUEHANNA STEAM ELECTRIC STATION PPL Rev. 32 LIST OF EFFECTIVE SECTIONS (TECHNICAL REQUIREMENTS MANUAL)
Section Title TOC 1.0 TABLE OF CONTENTS USE AND APPLICATION Page TRM / 1.0-1 Page TRM / 1.0-2 Page TRM / 1.0-3 2.0 3.0 3.1 PLANT PROGRAMS Page 2.0-1 Pages TRM / 2.0-2 and TRM 2.0-3 Page TRM I 2.0-4 Page TRM / 2.0-5 Pages TRM / 2.0-6 and TRM / 2.0-7 Page TRM / 2.0-8 Pages TRM / 2.0-9 through TRM / 2.0-11 Pages TRM / 2.0-12 through TRM / 2.0-15 APPLICABILITY Pages TRM / 3.0-1 and TRM / 3.0-2 Page TRM / 3.0-3 Page TRM / 3.0-4 REACTIVITY CONTROL SYSTEMS Pages 3.1-1 through 3.1-6 Pages TRM / 3.1-7 and TRMI 3.'1-8 Pages TRM / 3.1-9 and TRM I 3.1-9 Page TRM / 3.1-10 CORE OPERATING LIMITS REPORT Page TRM /,3.2-1 Pages TRMI 3.2-22 through TRM / 3.2-48 INSTRUMENTATION PageslTRM I,3.3-1 through TRM / 3.3-3
{Page TRM I 3.3-4 Pages 3)3-5 and 3.3-6 Page TRM 3.3-7 Page 3.3-8 Pages TRM / 3.3-9 and TRM I 3.3-9a Page TRM / 3.3-10 Page TRM / 3.3-11 Page TRM / 3.3-1 la Page TRM / 3.3-12 Page TRM / 3.3-13 Page TRM 1 3.3-14 Page TRM / 3.3-15 Effective Date 11/29/2006 08/31/1998 10/04/2002 08/31/1998 08/31/1998 01/28/2005 06/25/2002 04/12/1999 11/15/2004 12/03/2004 11/15/2004 11/15/2005 01/10/2007 03/15/2002 11/30/2005 08/31/1998 11/15/2005 02/18/1999 02/18/1999 08/31/1998 03/08/2007 07/16/1999 03/31/2006 08/3111998 03/31/2006 08/31/1998 12/17/1998 05/30/2006 06/02/2005 05/30/2006 03/30/2001 09/13/2005 12/14/1998 10/22/2003, 3.2 I
3.3 SUSQUEHANNA
- UNIT 2 TRMILOES-1 EFFECTIVE DATE 03/08/2007 SUSQUEHANNA - UNIT 2 TRM / LOES-1 EFFECTIVE DATE 03/08/2007
SUSQUEHANNA STEAM ELECTRIC STATION PPL Rev. 32 LIST OF EFFECTIVE SECTIONS (TECHNICAL REQUIREMENTS MANUAL)
Section Title Page TRM / 3.3-16 Pages TRM I 3.3-17 and TRM / 3.3-18 Pages TRM I 3.3-19 and TRM / 3.3-20 Page TRM / 3.3-21 Pages TRM /3.3-21a through TRM / 3.3-21d Page TRM / 3.3-22 Pages TRM / 3.3-23 and TRM / 3.3-24 Page TRM / 3.3-25 3.4 REACTOR COOLANT SYSTEM Page TRM / 3.4-1 Pages 3.4-2 through 3.4-5 Pages 3.4-6 through 3.4-11 Page TRM / 3.4-12 Page TRM / 3.4-13 3.5 3.6 3.7 EMERGENCY CORE COOLING AND RCIC Page TRM / 3.5-1 Pages 3.5-2 and 3.5-3 Page TRM / 3.5-4 Pages 3.5-5 through 3.5-7 CONTAINMENT Pages 3.6-1 through 3.6-4 Page TRM / 3.6-5 Page 3.6-6 Pages TRM / 3.6-7 through TRM / 3.6-9 PLANT SYSTEMS Pages TRM / 3.7-1 and TRM / 3.7-2 Page 3.7-3 Pages TRM / 3.7-4 and TRM / 3.7-5 Pages TRM / 3.7-6 through TRM / 3.7-8 Page TRM I 3.7-9 Page TRM / 3.7-10 Page TRM /3.7-11 Pages TRM / 3.7-12 and TRM / 3.7-13 Page TRM / 3.7-14 Pages TRM / 3.7-15 and TRM / 3.7-16 Page TRM I 3.7-17 Page TRM / 3.7-18 Page TRM I 3.7-19 Pages TRM / 3.7-20 through TRM / 3.7-22 Pages TRM / 3.7-23 and TRM / 3.7-24 Pages TRM / 3.7-25 through TRM / 3.7-27 Page TRM / 3.7-28 Effective Date 06/27/2001 06/14/2002 10/22/2003 11/15/2004 11/15/2004 12/03/2004 05/16/2003 10/22/2003 03/31/2006 10/23/1998 08/31/1998 12/03/2004 03/31/2006 01/28/2005 08/31/1998 04/17/2000 08/31/1998 08/31/1998 01/07/2002 08/31/1998 12/31/2002 07/29/1999 08/31/1998 03/31/2006 08/02/1999 03/31/2006 08/16/2005 01/21/2000 08/02/1999 08/09/2005 08/02/1999 03/31/2006 08/02/1999 03/31/2006 08/02/1999 03/31/2006 08/02/1999 11/29/2006 SUSQUEHANNA-UNIT2 TRM I LOES-2 EFFECTIVE DATE 03/08/2007 SUSQUEHANNA - UNIT 2 TRM / LOES-2 EFFECTIVE DATE 03/08/2007
SUSQUEHANNA STEAM ELECTRIC STATION PPL Rev. 32 LIST OF EFFECTIVE SECTIONS (TECHNICAL REQUIREMENTS MANUAL)
Section Title 3.8 Page TRM I 3.7-29 Page TRM / 3.7-30 Page TRM I 3.7-31 Page TRM / 3.7-32 Page TRM I 3.7-33 Page TRM / 3.7-34 Pages TRM / 3.7-35 and TRM / 3.7-36 Pages 3.7-37 through 3.7-38 Page TRM / 3.7-39 Pages TRM / 3.7-40 and TRM I 3.7-40a Pages 3.7-41 and 3.7-42 Pages TRM / 3.7-43 through TRM / 3.7-48 Pages TRM / 3.7-48a and TRM I 3.7-48b Page TRM / 3.7-49 Page TRM / 3.7-50 Page TRM / 3.7-51 Page TRM / 3.7-52 Page TRM / 3.7-53 ELECTRICAL POWER Page TRM / 3.8-1 Pages TRM / 3.8-2 and TRM / 3.8-3 Page TRM / 3.8-4 Pages TRM / 3.8-5 and TRM / 3.8-6 Pages TRM / 3.8-7 through TRM / 3.8-10 Page TRM / 3.8-11 Page TRM I 3.8-12 Pages 3.8-13 and 3.8-14 Page TRM / 3.8-15 Pages TRM / 3.8-16 and TRM / 3.8-17 Page 3.8-18 Page TRM / 3.8-19 Page TRM / 3.8-20 Pages TRM / 3.8-21 through TRM / 3.8-23 Pages 3.8-24 and 3.8-25 Pages TRM / 3.8-26 through TRM / 3.8-29 REFUELING OPERATIONS Pages 3.9-1 through 3.9-3 Effective Date 11/16/2001 11/30/2005 11/16/2001 01/09/2004 10/05/2002 03/31/2006 02/01/1999 08/31/1998 03/31/2006 02/14/2005 08/31/1998 10/05/2006 10/05/2006 03/09/2001 08/16/2006 12/03/2004 04/15/2003 07/29/1999 04/02/2002 01/28/2005 01/31/2005 04/02/2002 12/03/2004 08/10/2004 12/03/2004 08/31/1998 01/28/2005 04/02/2002 02/01/1999 04/02/2002 02/01/1999 06/06/1999 08/31/1998 11/29/2006 08131/1998 03/31/2006 08/30/1998 03/08/2003 06/05/2002 03/31/2006 08/16/2006 3.9 3.10 MISCELLANEOUS Page TRM / 3.10-1 Pages 3.10-2 through 3.10-4 Page TRM 3.10-5 Page TRM / 3.10-6 Page TRM / 3.10-7 Page TRM / 3.10-8 SUSQUEHANNA - UNIT 2 TRM / LOES-3 EFFECTIVE DATE 03/08/2007
SUSQUEHANNA STEAM ELECTRIC STATION PPL Rev. 32 LIST OF EFFECTIVE SECTIONS (TECHNICAL REQUIREMENTS MANUAL)
Section Title 3.11 RADIOACTIVE EFFLUENTS Page TRM / 3.11-1 Pages 3.11-2 through 3.11-3 Page TRM / 3.11-4 Page 3.11-5 Page TRM / 3.11-6 Pages 3.11-7 through 3.11-9 Page TRM / 3.11-10 Pages 3.11-11 and 3.11-12 Page 3.11-13 Page TRM / 3.11-14 Pages 3.11-15 and 3.11-16 Page TRM / 3.11-17 Page 3.11-18 Page TRM / 3.11-19 Pages TRM / 3.11-20 and TRM / 3.11-21 Page TRM / 3.11-22 Page TRM / 3.11-23 Page TRM / 3.11-24 Page 3.11-25 Pages TRM / 3.11-26 through TRM / 3.11-28 Page TRM / 3.11-29 Pages TRM 3.11-30 through TRM / 3.11-32 Page TRM / 3.11-33 Page 3.11-34 Page TRM / 3.11-35 Pages TRM / 3.11-36 through TRM / 3.11-39 Pages 3.11-40 through 3.11-44 Page TRM / 3.11-45 Page 3.11-46 Page TRM / 3.11-47 LOADS CONTROL PROGRAM Pages TRM / 3.12-1 through TRM / 3.12-3 Page TRM / 3.12-4 Page TRM / 3.12-5 ADMINISTRATIVE CONTROLS Pages 4.0-1 through 4.0-8 Effective Date 03/31/2006 08/31/1998 03/31/2006 08/31/1998 03/31/2006 08/31/1998 12/03/2004 08/31/1998 09/01/1998 12/03/1004 09/01/1998 03/31/2006 08/31/1998 08/15/2005 03/31/2006 04/02/2002 11/14/2006 05/13/2005 09/01/1998 01/21/2004 12/03/2004 01/21/2004 03/31/2006 08/31/1998 03/31/2006 11/30/2005 08/31/1998 03/31/2006 08/31/1998 03/31/2006 3.12 4.0 02/05/1999 09/30/2006 02/05/1999 08/31/1998 SUSQUEHANNA
- UNIT 2 TRM / LOES-4 EFFECTIVE DATE 03/08/2007 SUSQUEHANNA - UNIT 2 TRM / LOES-4 EFFECTIVE DATE 03/08/2007
SUSQUEHANNA STEAM ELECTRIC STATION PPL Rev. 32 LIST OF EFFECTIVE SECTIONS (TECHNICAL REQUIREMENTS MANUAL)
Section Title B 3.0 B 3.1 B 3.2 B 3.3 B 3.4 APPLICABILITY BASES Pages TRM / B 3.0-1 through TRM / B 3.0-3 Page TRM / B 3.0-4 Pages TRM / B 3.0-5 through TRM / B 3.0-10 Pages TRM I B 3.0-11 and TRM / B 3.0-12 Pages TRM / B 3.0-13 and TRM / B 3.0-14 Page TRM / B 3.0-15 REACTIVITY CONTROL SYSTEMS BASES Pages TRM / B 3.1-1 through TRM / B 3.1-3 Page B 3.1-4 Pages TRM / B 3.1-5 through TRM / B 3.1-7 Page TRM / B 3.1-8 CORE OPERATING LIMITS BASES Page B 3.2-1 INSTRUMENTATION BASES Page TRM / B 3.3-1 Page B 3.3-2 Pages TRM I B 3.3-3 and TRM / B 3.3-3A Pages TRM / B 3.3-4 through TRM / B 3.3-7 Pages TRM / B 3.3-8 and TRM / B 3.3-9 Page B 3.3-10 Pages TRM / B 3.3-11 and TRM / B 3.3-12 Page TRM / B 3.3-13 Page TRM / B 3.3-14 Page TRM / B 3.3-14a Page TRM / B 3.3.-14b Page TRM / B 3.3-15 Page TRM / B 3.3-16 Page TRM / B 3.3-17 Pages TRM / B 3.3-18 and TRM / B 3.3-19 Pages TRM / B 3.3-19a through TRM / B 3.3.19e Pages TRM / B 3.3-20 and TRM / B 3.3-21 Page TRM / B 3.3-22 Page TRM / B 3.3-23 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 08/31/1998 01/10/2007 08/31/1998 03/15/2002 11/30/2005 03/15/2002 07/13/1999 08/31/1998 11/15/2005 02/18/1999 08/31/1998 04/07/2000 08/31/1998 01/3112005 05/30/2006 03/30/2001 08/31/1998 09/13/2005 12/03/2004 06/25/2002 06/14/2002 06/14/2002 10/22/2003 10/22/2003 10/22/2003 11/115/2004 11/1512004 05/16/2003 10/22/2003 05/16/2003 08/31/1998 10/15/1999 08/31/1998 08/31/1998 07/26/2001 02/01/1999 08/31/1998 B 3.5 B 3.6 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 SUSQUEHANNA - UNIT 2 TRM / LOES-5 EFFECTIVE DATE 03/08/2007 SUSQUEHANNA - UNIT 2 TRM / LOES-5 EFFECTIVE DATE 03/08/2007
SUSQUEHANNA STEAM ELECTRIC STATION PPL Rev. 32 LIST OF EFFECTIVE SECTIONS (TECHNICAL REQUIREMENTS MANUAL)
Section Title Page TRM / B 3.6-4 Page TRM / B 3.6-5 Page TRM / B 3.6-6 Pages TRM / B 3.6-7 through TRM I B 3.6-11 B 3.7 B 3.8 PLANT SYSTEMS BASES Pages B 3.7-1 and B 3.7-2 Page TRM / B 3.7-3 Page TRM / B 3.7-4 Page TRM / B 3.7-5 Pages TRM / B 3.7-6 and TRM / B 3.7-6a Pages TRM / B 3.7-7 and TRM / B 3.7-7a Page TRM / B 3.7-8 Page TRM / B 3.7-9 Page TRM / B 3.7-10 Pages TRM / B 3.7-1Oa through TRM / B 3.7-1 Ia Pages TRM / B 3.7-12 through TRM / B 3.7-14 Pages TRM / B 3.7-14a and 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 Pages TRM / B 3.7-21 and TRM / B3.7-21a Pages TRM / B 3.7-22 and TRM / B 3.7-23 Pages TRM / B 3.7-24 through TRM / B 3.7-30 Pages TRM / B 3.7-30a and TRM / B 3.7-30b Page TRM / B 3.7-31 Page TRM / B 3.7-32 Page TRM / B 3.7-33 Page TRM / B 3.7-34 Page TRM / B 3.7-35 ELECTRICAL POWER BASES Page TRM / B 3.8-1 Pages TRM / B 3.8-2 and TRM / B 3.8-2a Page TRM / B 3.8-3 Page TRM / B 3.8-3a Page TRM / B 3.8-4 Page TRM / B 3.8-4a Page TRM / B 3.8-5 Pages TRM / B 3.8-6 through TRM / B 3.8-16 Page TRM / B 3.8-17 Pages TRM / B 3.8-18 through TRM / B 3.8-24 Effective Date 09/23/1999 01/07/2002 12/03/2004 12/31/2002 08/31/1998 08/02/1999 03/31/2006 0810211999 03/31/2006 08/02/1999 08/02/1999 03/31/2006 08/02/1999 03/31/2006 08/02/1999 01/09/2004 02/01/1999 08/31/1998 02/14/2005 04/07/2000 10/05/2006 10/05/2006 12/03/2004 03/09/2001 04/15/2003 12/03/2004 07/05/2000 04/02/2002 01/28/2005 04/02/2002 04/02/2002 04/02/2002 08/10/2004 08/31/1998 04/02/2002 01/28/2005 11/29/2006 SUSQUEHANNA - UNIT 2 TRM / LOES-6 EFFECTIVE DATE 03/08/2007
SUSQUEHANNA STEAM ELECTRIC STATION PPL Rev. 32 LIST OF EFFECTIVE SECTIONS (TECHNICAL REQUIREMENTS MANUAL)
Section Title B.3.9 REFUELING OPERATIONS BASES Pages B 3.9-1 and B 3.9-2 Pages B 3.9-3 through B 3.9-7 B 3.10 MISCELLANEOUS BASES Pages B 3.10-1 through B 3.10-2 Page TRM / B 3.10-3 Pages TRM / B 3.10-4 and TRM / B 3.10-5 Pages TRM / B 3.10-6 and TRM / 3.10-7 B 3.11 RADIOACTIVE EFFLUENTS BASES Pages B 3.11-1 through B 3.11-9 Page TRM / B 3.11-10 Pages TRM/B 3.11-11 and TRM/B 3.11-1 Ia Pages TRM/B 3.11-12 and TRM/B 3.11-13 Page TRM /B 3.11-14 Page TRM /B 3.11-15 Pages B 3.11-16 through B 3.11-19 Page TRM I B 3.11-20 Page TRM / B 3.11-20a Page TRM /B 3.11-21 Pages TRM / B 3.11-22 and TRM / B 3.11-23 Page TRM / B 3.11-23a Pages TRM / B 3.11-24 and TRM / B 3.11-25 Pages B 3.11-26 through B 3.11-27 Pages TRM / B 3.11-28 and TRM / B 3.11-29 Page TRM / B 3.11-30 Pages B 3.11-31 through B 3.11-35 Page TRM / B 3.11-36 Effective Date 08/31/1998 10/23/1998 08/31/1998 03/08/2003 08/23/1999 04/17/2002 08/31/1998 02/01/1999 04/07/2000 02/01/1999 12/03/2004 02/01/1999 08/31/1998 04/02/2002 04/02/2002 05/13/2005 11/14/2006 05/13/2005 01/21/2004 08/31/1998 11/30/2005 12/03/2004 08/31/1998 02/12/1999 B.3.12 LOADS CONTROL PROGRAM BASES Pages TRM / B 3.12-1 through TRM / B 3.12-3 02/05/1999 TRM2 text LOES.doc 3/612007 SUSQUEHANNA - UNIT 2 TRM / LOES-7 EFFECTIVE DATE 03/08/2007
Core Operating Limits Report (COLR)
PPL Rev. 6 3.2.1 3.2 Core Operating Limits Report (COLR) 3.2.1 Core Operating Limits Report (COLR)
TRO 3.2.1 The Core Operating Limits specified in the attached COLR shall be met.
APPLICABILITY:
Specified in the referenced Technical Specifications.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.
Core Operating Limits not A.1 Perform action(s)
Specified in referenced met.
described in referenced Technical Technical Specification.
Specifications.
TECHNICAL REQUIREMENT SURVEILLANCE SURVEILLANCE FREQUENCY NOTE N/A No associated Surveillances. Surveillances are implemented in the applicable Technical Specifications.
SUSQUEHANNA - UNIT 2 TRM / 3.2-1 EFFECTIVE DATE 8/31/1998
PPL Rev. 6 PL-NF-07-002 Rev. 0 Page 1 of 47 Susquehanna SES Unit 2 Cycle 14 CORE OPERATING LIMITS REPORT Nuclear Fuels Engineering March 2007 Ij ill
/
S I
ppI ~
4 SUSQUEHANNA UNIT 2 TRM/3.2-2 EFFECTIVE DATE 03/08/2007
PPL Rev. 6 PL-NF-07-002 Rev. 0 Page 2 of 47 CORE OPERATING LIMITS REPORT REVISION DESCRIPTION INDEX Rev.
Affected No.
Sections Description/Purpose of Revision 0
ALL Issuance of this COLR is in support of Unit 2 Cycle 14 operation.
FORM NFP-QA-008-2, Rev. 1 SUSQUEHANNA UNIT 2 TRM/3.2-3 EFFECTIVE DATE 03/08/2007
PPL Rev. 6 PL-NF-07-002 Rev. 0 Page 3 of 47 SUSQUEHANNA STEAM ELECTRIC STATION Unit 2 Cycle 14 CORE OPERATING LIMITS REPORT Table of Contents 1.0 INTR O D U CT IO N.....................................................................................................
4 2.0 DEFINITIO N S.....................................................................................................
5 3.0 SHUTDOW N M ARG IN............................................................................................
6 4.0 AVERAGE PLANAR LINEAR HEAT GENERATION RATE (APLHGR)................... 7 5.0 MINIMUM CRITICAL POWER RATIO (MCPR)......................................................
9 6.0 LINEAR HEAT GENERATION RATE (LHGR).........................................................
21 7.0 ROD BLOCK MONITOR (RBM) SETPOINTS AND OPERABILITY REQ U IR EM ENTS..................................................................................................
29 8.0 RECIRCULATION LOOPS - SINGLE LOOP OPERATION.....................................
31 9.0 POW ER / FLO W M AP............................................................................................
43 10.0 O PRM SETPO INTS................................................................................................
45 11.0 R E FE R E N C E S............................................................................................................
46 SUSQUEHANNA UNIT 2 TRM/3.2-4 EFFECTIVE DATE 03/08/2007
PPL Rev. 6 PL-NF-07-002 Rev. 0 Page 4 of 47
1.0 INTRODUCTION
This CORE OPERATING LIMITS REPORT for Susquehanna Unit 2 Cycle 14 is prepared in accordance with the requirements of Susquehanna Unit 2, Technical Specification 5.6.5. As required by Technical Specifications 5.6.5, core shutdown margin, the core operating limits, RBM setpoints, and OPRM setpoints presented herein were developed using NRC-approved methods and are established such that all applicable limits of the plant safety analysis are met.
SUSQUEHANNA UNIT 2 TRM/3.2-5 EFFECTIVE DATE 03/08/2007
PPL Rev. 6 PL-NF-07-002 Rev. 0 Page 5 of 47 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 PLANAR EXPOSURE at a specified height shall be equal to the total energy produced per unit length at the specified height divided by the total initial weight of uranium per unit length at that height.
2.2 The PELLET EXPOSURE shall be equal to the total energy produced per unit length of fuel rod at the specified height divided by the total initial weight of uranium per unit length of that rod at that height.
2.3 FDLRX is the ratio of the maximum LHGR calculated by the core monitoring system for each fuel bundle divided by the LHGR limit for the applicable fuel bundle type.
2.4 LHGRFACf is a multiplier applied to the LHGR limit when operating at less than 108 Mlbm/hr core flow. The LHGRFACf multiplier protects against both fuel centerline melting and cladding strain during anticipated system transients initiated from core flows less than 108 Mlbm/hr.
2.5 LHGRFACP is a multiplier applied to the LHGR limit when operating at less than 100%
rated power. The LHGRFACp multiplier protects against both fuel centerline melting and cladding strain during anticipated system transients initiated from partial power conditions.
2.6 MFLCPR is the ratio of the applicable MCPR operating limit for the applicable fuel bundle type divided by the MCPR calculated by the core monitoring system for each fuel bundle.
2.7 MAPRAT is the ratio of the maximum APLHGR calculated by the core monitoring system for each fuel bundle divided by the APLGHR limit for the applicable fuel bundle type.
2.8 OPRM is the Oscillation Power Range Monitor. The Oscillation Power Range Monitor (OPRM) will reliably detect and suppress anticipated stability related power oscillations while providing a high degree of confidence that the MCPR safety limit is not violated.
2.9 Np is the OPRM setpoint for the number of consecutive confirmations of oscillation half-cycles that will be considered evidence of a stability related power oscillation.
2.10 Sp is the OPRM trip setpoint for the peak to average OPRM signal.
2.11 Fp is the core flow, in Mlbm / hr, below which the OPRM RPS trip is activated.
SUSQUEHANNA UNIT 2 TRM/3.2-6 EFFECTIVE DATE 03/08/2007
PPL Rev. 6 PL-NF-07-002 Rev. 0 Page 6 of 47 3.0 SHUTDOWN MARGIN 3.1 Technical Specification Reference Technical Specification 3.1.1 3.2 Description The SHUTDOWN MARGIN shall be equal to or greater than:
a) 0.38% Ak/k with the highest worth rod analytically determined OR b) 0.28% Ak/k with the highest worth rod determined by test Since core reactivity will vary during the cycle as a function of fuel depletion and poison burnup, Beginning of Cycle (BOC) SHUTDOWN MARGIN (SDM) tests must also account for changes in core reactivity during the cycle. Therefore, the SDM measured at BOC must be equal to or greater than the applicable requirrement fror either 3.2.a or 3.2.b plus an adder, "R". The adder, "R", is the difference: between the calculated value of maximum core reactivity (that is, minimum SDM) during the operating cycle and the calculated BOC core reactivity. If the value of "R" is zero (that is, BOC is the most reactive point in the cycle) no correction to the BOC measured value is required.
The SHUTDOWN MARGIN limits provided in 3.2a and 3.2b are applicable in MODES 1, 2, 3, 4, and 5. This includes core shuffling.
SUSQUEHANNA UNIT 2 TRM/3.2-7 EFFECTIVE DATE 03/08/2007
PPL Rev. 6 PL-NF-07-002 Rev. 0 Page 7 of 47 4.0 AVERAGE PLANAR LINEAR HEAT GENERATION RATE (APLHGR) 4.1 Technical Specification Reference Technical Specification 3.2.1 4.2 Description The APLHGRs for ATRIUMTM-10 fuel shall not exceed the limit shown in Figure 4.2-1.
The APLHGR limits in Figure 4.2-1 are valid for Main Turbine Bypass Operable and Inoperable and EOC-RPT Operable and Inoperable in Two Loop operation.
The APLHGR limits for Single Loop operation are provided in Section 8.0.
SUSQUEHANNA UNIT 2 TRM/3.2-8 EFFECTIVE DATE 03/08/2007
.c/)
r-H eP SSES UNIT 2 CYCLE 14 16 14
~12 E-
[REFERENCE T.S. 3.2.1 0......
USED IN DETERMINING MAPRAT 0.0,12 1
0 2
J....
I.-
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i i
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i i
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l i67000,6.9l mT m
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mý 00 m1 6-4.
0 10000 20000 30000 40000 50000 60000 70000 Average Planar Exposure (MWDIMTU)
AVERAGE PLANAR LINEAR HEAT GENERATION RATE LIMIT VERSUS AVERAGE PLANAR EXPOSURE TWO LOOP OPERATION ATRIUMTM-10 FUEL FIGURE 4.2-1
PPL Rev. 6 PL-NF-07-002 Rev. 0 Page 9 of 47 5.0 MINIMUM CRITICAL POWER RATIO (MCPR) 5.1 Technical Specification Reference Technical Specification 3.2.2, 3.7.6, and 3.3.4.1 5.2 Description The MCPR limit is specified as a function of core power, core flow, average scram insertion time per Section 5.3 and plant equipment operability status. The MCPR limits for all fuel types (ATRIUMTM-10) shall be the greater of the Flow-Dependent or the Power-Dependent MCPR, depending on the applicable equipment operability status.
a)
EOC-RPT and Main Turbine Bypass Operable Figure 5.2-1: Flow-Dependent MCPR value determined from BOC to EOC Figure 5.2-2: Power-Dependent MCPR value determined from BOC to EOC b)
Main Turbine Bypass Inoperable / EOC-RPT Operable Figure 5.2-3: Flow-Dependent MCPR value determined from BOC to EOC Figure 5.2-4: Power-Dependent MCPR value determined from BOC to EOC c)
EOC-RPT Inoperable / Main Turbine Bypass Operable Figure 5.2-5: Flow-Dependent MCPR value determined from BOC to EOC Figure 5.2-6: Power-Dependent MCPR value determined from BOC to EOC The MCPR limits in Figures 5.2-1 through 5.2-6 are valid for Two Loop operation.
The MCPR limits for Single Loop operation are provided in Section 8.0.
SUSQUEHANNA UNIT 2 TRM/3.2-10 EFFECTIVE DATE 03/08/2007
PPL Rev. 6 PL-NF-07-002 Rev. 0 Page 10 of 47 5.3 Average Scram Time Fraction If the average measured scram times are greater than the Realistic Scram times listed in Table 5.3-1 then the MCPR operating limits corresponding to the Maximum Allowable Average Scram Insertion Time must be implemented.
Determining MCPR operating limits based on interpolation between scram insertion times is not permitted. The evaluation of scram insertion time data, as it relates to the attached table should be performed per Reactor Engineering procedures.
SUSQUEHANNA UNIT 2 TRM/3.2-11 EFFECTIVE DATE 03/08/2007
PPL Rev. 6 PL-NF-07-002 Rev. 0 Page 11 of 47 EOC-RPT and Main Turbine Bypass Operable SUSQUEHANNA UNIT 2 TRM/3.2-12 EFFECTIVE DATE 03/08/2007
e e
Q~
2.2 2.1 2.0 1.9
.03 N3 "E 1.8 S1.7 0.
Q 1.6 SSES UNIT 2 CYCLE 14 LEGEND CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES AREOPERABLE PER SR 3.7.6.1 AND 3.7.6.2 USED IN DETERMINING MFLCPR (50,1.62)
(80.5,1.41)
(0
,.1 (108,1.41 B
REFERENCE:
T.S. 3.2.21 (86.3,1.37)
(108,1.37)
-n m
CD) m' mo N) 1.5 1.4 1.3 1.2 30 40 50 60 70 80 90 100 110 Total Core Flow (MLB/HR)
MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW EOC-RPT AND MAIN TURBINE BYPASS OPERABLE TWO LOOP OPERATION (BOC TO EOC)
FIGURE 5.2-1 CD I (0 <
(D Z
0 C4 )
e C/'
N) e e
SSES UNIT 2 CYCLE 14 N)
E
.- J I-0.
0 0.W 3.5 3.4 3.3 3.2 3.1 3.0 2.9 2.8 2.7 2.6 2.5 2.4 2.3 2.2 2.1 2.0 1.9 1.8 1.7 1.6 1.5 1.4 1.3 I
I I
LEGEND (25,3.15)
CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM (INSERTION TIME (30,2.94)
CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME L
- I I
I I
SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 USED IN DETERMINING MFLCPR/
-n CD) co)
NJ CD V
+
(40,1.76)
" A -..
t 1~
¶ I
T T
(40,1.68)
B I
REFERENCE:
T.S. 3.2.21 (65,1.56)-
I.
I I
(80,1.47)
(85,1.44)
(100,1.41)
(100,1.37)
I I
II 6 ___________
n 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 (0<
CD '
CA) 0
-4
PPL Rev. 6 PL-NF-07-002 Rev. 0 Page 14 of 47 Main Turbine Bypass Inoperable I EOC-RPT Operable SUSQUEHANNA UNIT 2 TRM/3.2-15 EFFECTIVE DATE 03/08/2,007
0 c/)
V)
SSES UNIT 2 CYCLE 14 2.3 2.2 D
A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME B: REALISTIC AVERAGE SCRAM INSERTION TIME 2.1 1
4-I[:
111-'
2.0
-(30,1.98) __
SAFETY ANALYSES ASSUME THAT TWO OR MORE BYPASS VALVES ARE INOPERABLE PER SR 3.7.6.1 OR 3.7.6.2 K
---q CY) 1.9
,-J 0)
C S1.8 0.
. 1.7 (50,1.87)
USED IN DETERMINING MFLCPR m
m C:)
0H Nm 1.6 1.5 1.4 1.3 A
B (81.8,1.58)
(108,1.58)
REFERENCE:
T.S. 3.7.6 and 3.2.21___________
30 40 50 60 70 80 90 100 110 Total Core Flow (MLBIHR)
MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW MAIN TURBINE BYPASS INOPERABLE I EOC-RPT OPERABLE TWO LOOP OPERATION (BOC TO EOC)
FIGURE 5.2-3 (D
(0 (D
0
NJ~
3.5 3.4 3.3 3.2 3.1 3.0 2.9 2.8 2.7 ED2.6 2.5 2.4 0.
0 2.3
.2.2 2.1 2.0 1.9 1.8 1.7 1.6 1.5 1.4 1.3 e
e SSES UNIT 2 CYCLE 14 LEGEND:
(25,3.34)
CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME (30,2.94)
CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME SAFETY ANALYSES ASSUME THAT TWO OR MORE BYPASS VALVES ARE INOPERABLE PER SR 3.7.6.1 OR 3.7.6.2
_USED IN DETERMINING MFLCPR (40,1.8 1)
A B_
_(100,1.58)
]
REFERENCE:
T.S. 3.7.6 and 3.2.2 (72.9,1.58)
S(72.9,1.58) m-n
_n m
m CD CD N) 20 30 40 50 60 70 80 90 100 Core Power (% RATED)
MCPR OPERATING LIMIT VERSUS CORE POWER MAIN TURBINE BYPASS INOPERABLE I EOC-RPT OPERABLE TWO LOOP OPERATION (BOC to EOC)
FIGURE 5.2-4
~1CD Co<
CD '
0
PPL Rev. 6 PL-NF-07-002 Rev. 0 Page 17 of 47 EOC-RPT Inoperable /
Main Turbine Bypass Operable SUSQUEHANNA UNIT 2 TRM/3.2-18 EFFECTIVE DATE 03/08/2007
U
_-H Fn SSES UNIT 2 CYCLE 14 2.2 2.1 2.0 1.9 T
I 4
4 D
A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME B: REALISTIC AVERAGE SCRAM INSERTION TIME
¶ q
4 J.
SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 c~)
N)
I.
"*1.8 4
1.7 0
1l.6 4
-~
1.
USED IN DETERMINING MFLCPR I
(30,1.7) m N~)
C=)
1.5 1.4 1.3 1.2 (50,1.62) 180.5,1.41)
(108,1.41)
REFERENCE:
T.S. 3.3.4.1 and 3.2.2 30 40 50 60 70 80 90 100 110 Total Core Flow (MLBIHR)
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 ca I-T)
(D Z
0
-4 rQ
U V) cU) mT~
D>
CA)
N.)
CD
.4t E
Z)
CL 0
W.
0L 3.5 3.4 3.3 3.2 3.1 3.0 2.9 2.8 2.7 2.6 2.5 2.4 2.3 2.2 2.1 2.0 1.9 1.8 1.7 1.6 1.5 1.4 1.3 U
6 SSES UNIT 2 CYCLE 14 I
I I
LEGEND (25,3.15)_
CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME (09 CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME
-(30,2.94)--
SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 USED IN DETERMINING MFLCPR (40,1.76)
A B
F
REFERENCE:
T.S. 3.3.4.1 and 3.2.21 7(80,1.47) mm
-T m
-H m
co N)
(100,1.41) 20 30 40 50 60 70 80 90 100 Core Power (% RATED)
MCPR OPERATING LIMIT VERSUS CORE POWER EOC-RPT INOPERABLE / MAIN TURBINE BYPASS OPERABLE TWO LOOP OPERATION (BOC to EOC)
FIGURE 5.2-6
(~<
(1-Z (0
0 4-1 4~
PPL Rev. 6 PL-NF-07-002 Rev. 0 Page 20 of 47 Table 5.3-1 Average Scram Time Fraction Table For Use With Scram Time Dependent MCPR Operating Limits Control Rod Average Scram Time to Position (seconds)
Position 45 0.470 0.520 39 0.630 0.860 25 1.500 1.910 5
2.700 3.440 Average Scram Realistic Maximum Insertion Time Allowable SUSQUEHANNA UNIT 2 TRM/3.2-21 EFFECTIVE DATE 03/08/2007
PPL Rev. 6 PL-NF-07-002 Rev. 0 Page 21 of 47 6.0 LINEAR HEAT GENERATION RATE (LHGR) 6.1 Technical Specification Reference Technical Specification 3.2.3 and 3.7.6 6.2 Description The maximum LHGR for ATRIUM TM-10 fuel shall not exceed the LHGR limit determined from Figure 6.2-1. The LHGR limit in Figure 6.2-1 is valid for Main Turbine Bypass Operable and Inoperable and EOC-RPT Operable and Inoperable.
In order to protect against both fuel centerline melting and cladding strain during anticipated system transients initiated from reduced power and flow conditions, power and flow dependent LHGR limit multipliers are provided:
a)
Main Turbine Bypass Operable / EOC-RPT Operable and Inoperable Figure 6.2-2: Flow-Dependent LHGR Limit Multiplier Figure 6.2-3: Power-Dependent LHGR Limit Multiplier b)
Main Turbine Bypass Inoperable I EOC-RPT Operable and Inoperable Figure 6.2-4: Flow-Dependent LHGR Limit Multiplier Figure 6.2-5: Power-Dependent LHGR Limit Multiplier The LGHR limit and LHGR limit multipliers in Figures 6.2-1 through 6.2-5 are valid for both Two Loop and Single Loop operation.
SUSQUEHANNA UNIT 2 TRM/3.2-22 EFFECTIVE DATE 03/08/2007
1SSES UNIT 2 CYCLE 14 V)16 m
I I
I I
o
.o e
- O*
h e
14.0,130.4.4-
REFERENCE:
T.S. 3.2.3--
.).
USED IN DETERMINING FDLRX[
N)
.2 10 W
CD Z
°','...
2" ---
CF")""
1, ~
4..0.-
CD':
-º '
r * -.
U.E
.N D.E M N G
D R C.4 CD
.9 0
10000 20000 30000 40000 50000 60000 70000 80000 N)Pellet Exposure (MWDIMTU)
W C r
LINEAR HEAT GENERATION RATE LIMIT VERSUS PELLET EXPOSURE m
6 TM 0
ATRIU
-0 FUEL 0.
FIGURE 6.2-1
PPL Rev. 6 PL-NF-07-002 Rev. 0 Page 23 of 47 Main Turbine Bypass Operable /
EOC-RPT Operable and Inoperable SUSQUEHANNA UNIT 2 TRM/3.2-24 EFFECTIVE DATE 03/08/2007
U V)
(V)
.1.10 1.00 0.90 75 W 0.80 5- 0.70 Ca 00 0.60 4
SSES UNIT 2 CYCLE 14 (90,1.00)
(10.8,1.00) a..............
- a..
(3,.0 (6,080 IIII
.SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES a
aARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2
REFERENCE:
T.S.
3.2.3 and 3.7.6 a
a..
a......a.....
j.............
a a
a a
a a
a UED IN~ DETERMINING FDLRX a
a a
a a
a a
a a
a a
a a
a a
a a
a a
a a
a a
a a
a*
a a
a a
a a
a a
a a
a a
a a
a a
a a
a a
a a
a a
a a
a a
a a
a a
a CD)
-4
~0.40-0 40 50 I
I I
I I
I
,,i 60 70 80 90 100 110 Total Core Flow (MLB/hr)
CD (0<
CD "
Z FLOW DEPENDENT LHGR LIMIT MULTIPLIER C)
C MAIN TURBINE BYPASS OPERABLE 0
ATRIUM
-10 FUEL 4
o FIGURE 6.2-2
C/)
1SSES UNIT 2 CYCLE 14 1.00 -
L CL 0.8 I
a M
4,07)
SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES C
C0 IR....
FERENCE: T.S. 3.2.3 and 3.7.6 0
USE IN ETEMINNGoDLR ih
.0.60 L
I I.
A..
o J --
J.....
DETER ININ 0.5 -
... r --
y ----
1
.1"l 1
1 11....
I.
I.
° a
a.....
a a
a a
a a
a a
0
.9 (25,0.42)..
(30,0.46)...............
. i
. I
. 3.
0.40 co 20 30 40 50 60 70 80 9.0 100 r9
~~Core Power (% RATED)WCDr CDCD Z
POWER DEPENDENT LHGR LIMIT MULTIPLIER 6.1 MAIN TURBINE BYPASS OPERABLE0 ATRI-U"Mi0 FUEL C
FIGURE 6.2-3
PPL Rev. 6 PL-NF-07-002 Rev. 0 Page 26 of 47 Main Turbine Bypass Inoperable I EOC-RPT Operable and Inoperable SUSQUEHANNA UNIT 2 TRM/3.2-27 EFFECTIVE DATE 03/08/2007
SSES UNIT 2 CYCLE 14
~I.Iu m
1.00 0.90 L.
0.
4.,
3:
n,0.80 2))
0.70 co 0.7 0
0.60 m-n
-'r m
0.50 m
c0.40 co CD I
Si S
i I
i S
i SIi I
i i
I I
S I
i I
i.
i S
i i
I I
i S
i S
I S
S i
S S
I S
i I
I S
I S
I S
(9 0,1.0 0 )
(1 0 8,1.0 0 )
... SAFETY ANALYSES ASSUME THAT TWO OR MORE BYPASS I
VALVES ARE INOPERABLE PER SR 3.7.6.1 OR 3.7.6.2
.(007)
.. (5,.0
REFERENCE:
T.S. 3.2.3 and 3.7.6 I-A S-I J..8
.8.
USED IN DETERMINING FDLRX
~ ~ -
- A 1
- - - - - - -I - -
i S
I i
i i
S S
i I
I S
I I
S I
I i
S i
I S
S S
i I
S i
I i
I i
i S
i S
i
.. ~~~~~~
~~~
i I
I i
I S
I I
I I
I I
I S
S S
S S
S S
I "
I I
I S
s I
I S
i ISI I
S 30 40 50 60 70 80 90 100 110 Total Core Flow (MLB/HR)
E (o <
CD~ '
FLOW DEPENDENT LHGR LIMIT MULTIPLIER N) C 0
MAIN TURBINE BYPASS INOPERABLE 0
ATRIUMTM-10 FUEL 4
N)
FIGURE 6.2-4
(_
SSES UNIT 2 CYCLE 14 I.IU 1.00 9
0.90-S 0.80 G) 0.70 0
0.60 "r-i
-nI
-n 0.50 r--
m 0.40 021 N)
CD (i
l i.9 I.....
1.....
OR 3.7.6.2 a.
(250 2
)
I I......
SAEYAAYE ASSUME THAT-TWOi OR MOR BYAS (25,0.2).
0,0(100-------
0 30 40 50 60 70 80 90 100 Core Power (% RATED)
W C r-(0 CD
- POWER DEPENDENT LHGR LIMIT MULTIPLIER N c) -n MAIN TURBINE BYPASS INOPERABLE 0
ATRIUMTM-10 FUEL C
FIGURE 6.2-5
-4
PPL Rev. 6 PL-NF-07-002 Rev. 0 Page 29 of 47 7.0 ROD BLOCK MONITOR (RBM) SETPOINTS AND OPERABILITY REQUIREMENTS 7.1 Technical Specification Reference Technical Specification 3.3.2.1 7.2 Description The RBM Allowable Value and Trip Setpoints for; a)
Low Power Range Setpoint, b)
Intermediate Power Range Setpoint, c)
High Power Range Setpoint, e)
Low Power Range - Upscale, f)
Intermediate Power Range - Upscale, and g)
High Power Range - Upscale shall be established as specified in Table 7.2-1. The RBM setpoints are valid for Two Loop and Single Loop Operation, Main Turbine Bypass Operable and Inoperable, and EOC-RPT Operable and Inoperable.
The RBM system design objective is to block erroneous control rod withdrawal initiated by the operator before fuel design limits are violated. If the full withdrawal of any control rod would not violate a fuel design limit, then the RBM system is not required to be operable. Table 7.2-2 provides RBM system operability requirements to ensure that fuel design limits are not violated.
SUSQUEHANNA UNIT 2 TRM/3.2-30 EFFECTIVE DATE 03/08/2007
PPL Rev. 6 PL-NF-07-002 Rev. 0 Page 30 of 47 Table 7.2-1 RBM Setpoints Allowable Nominal Trip Function Value(')
Setpoint Low Power Range Setpoint 28.0 24.9 Intermediate Power Range Setpoint 63.0 61.0 High Power Range Setpoint 83.0 81.0 Low Power Range - Upscale 123.4 123.0 Intermediate Power Range - Upscale 113.6 113.2 High Power Range - Upscale 110.6 110.2 (1)
Power setpoint function (Low, Intermediate, and High Power Range Setpoints) determined in percent of rated thermal power. Upscale trip setpoint function (Low, Intermediate, and High Power Range - Upscale) determined in percent of reference level.
Table 7.2-2 RBM System Operability Requirements Thermal Power MCPR (2.3)
(% of Rated)
>28 and < 90
< 1.78
>90
< 1.71 (2)
Applicable to Main Turbine Bypass Operable and Inoperable Operable and Inoperable.
(3)
Applicable to both Two Loop and Single Loop Operation.
and EOC-RPT SUSQUEHANNA UNIT 2 TRM/3.2-31 EFFECTIVE DATE 03/08/2007
PPL Rev. 6 PL-NF-07-002 Rev. 0 Page 31 of 47 8.0 RECIRCULATJON LOOPS - SINGLE LOOP OPERATION 8.1 Technical Specification Reference Technical Specification 3.2.1, 3.2.2, 3.2.3, 3.3.4.1, 3.4.1, and 3.7.6 8.2 Description APLHGR The APLHGR limit for ATRIUMTM-10 fuel shall be equal to the APLHGR Limit from Figure 8.2-1.
The APLHGR limits in Figure 8.2-1 are valid for Main Turbine Bypass Operable and Inoperable and EOC-RPT Operable and Inoperable in Single Loop operation.
Minimum Critical Power Ratio Limit The MCPR limit is specified as a function of core power, core flow, and plant equipment operability status. The MCPR limits for all fuel types (ATRIUMTM-10) shall be the greater of the Flow-Dependent or the Power-Dependent MCPR, depending on the applicable equipment operability status.
a)
EOC-RPT and Main Turbine Bypass Operable Figure 8.2-2: Flow-Dependent MCPR value determined from BOC to EOC Figure 8.2-3: Power-Dependent MCPR value determined from BOC to EOC b)
Main Turbine Bypass Inoperable I EOC-RPT Operable Figure 8.2-4: Flow-Dependent MCPR value determined from BOC to EOC Figure 8.2-5: Power-Dependent MCPR value determined from BOC to EOC c)
EOC-RPT Inoperable / Main Turbine Bypass Operable Figure 8.2-6: Flow-Dependent MCPR value determined from BOC to EOC Figure 8.2-7: Power-Dependent MCPR value determined from BOC to EOC SUSQUEHANNA UNIT 2 TRM/3.2-32 EFFECTIVE DATE 03/08/2007
PPL Rev. 6 PL-NF-07-002 Rev. 0 Page 32 of 47 The MCPR limits in Figures 8.2-2 through 8.2-7 are valid only for Single Loop operation.
Linear Heat Generation Rate Limit The LHGR limits for Single Loop Operation are defined in Section 6.0.
RBM Setpoints and Operability Requirements The RBM setpoints and operability requirements for Single Loop Operation are defined in Section 7.0.
SUSQUEHANNA UNIT 2 TRM/3.2-33 EFFECTIVE DATE 03/08/2007
m M-1 N) e SSES UNIT 2 CYCLE 14 16 14
~12 E
0.4 w"
w.2i0o cc 8.
REFERENCE T.S. 3.4.1 and Il2'.
-~~~~~~~~
.i
.=
.p
.==
.n
- o.
.. ]
I, USED IN DETERMINING MAPRAT V
l i
=
t
=
=
i
- 67000,5.6l m
C=)
NJ 6
4 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 ATRIUMTM-10 FUEL FIGURE 8.2-1 70000 W~ CD~
(0 CD '
wc)
-n
-~0 14 N
PPL Rev. 6 PL-NF-07-002 Rev. 0 Page 34 of 47 EOC-RPT and Main Turbine Bypass Operable SUSQUEHANNA UNIT 2 TRM/3.2-35 EFFECTIVE DATE 03/08/2007
U cri SSES UNIT 2 CYCLE 14 2.3 I
LEGEND CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME 2.2
-(30,2.18) 4 4
4-N.)
2.1 E
'4-2 2.0 0.
a-(3.
1.9 1.8 (50,2.08) t L
I
_/_
SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2
- 1II
~
1.
4 USED IN DETERMINING MFLCPR P1 m
71 C-D cz) co c--i (108,1.81)
B A-FRE: T
- 34. an-(80.5,1.81)-
IREFERENCE:
T.S. 3.4.1 and 3.2.2 1.7 30 40 50 60 70 80 90 100 110 Total Core Flow (MLBIHR)
MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW EOC-RPT AND MAIN TURBINE BYPASS OPERABLE SINGLE LOOP OPERATION (BOC to EOC)
FIGURE 8.2-2 (D
0
-4 CDI c) _
00 N)
U U-)
m MH N)
SSES UNIT 2 CYCLE 14 4.1 3.9 3.7 3.5
-(25,4.01)
(30,3.74)
I.
LEGEND CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME CURVE B: REALISTIC AVERAGE SCRAM TIME N)
U) 3.3 E
-J 3.1 2.9 0.
0
.2.7 2.
2.5 I
SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 I
I
+
4 -.------
I USED IN DETERMINING MFLCPR P
1 1
-n m
CA-)
N)
Nz) 2.3 2.1 4
(40,2.26) 9 I~
.r I
.4
.4 9
L (76,1.93)
(100,1.93) 1.9 1.7
REFERENCE:
T.S. 3.4.1 and 3.2.2 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 SINGLE LOOP OPERATION (BOC to EOC)
FIGURE 8.2-3 a)
(0hD CD C)n 6O
PPL Rev. 6 PL-NF-07-002 Rev. 0 Page 37 of 47 Main Turbine Bypass Inoperable / EOC-RPT Operable SUSQUEHANNA UNIT 2 TRM/3.2-38 EFFECTIVE DATE 03/08/2007
N.)
m
-71 c:)
co)
N.)
CD 9
SSES UNIT 2 CYCLE 14 V
2.6 2.5 2.4 E 2.3 Jm 2.2 L
2.1 2.0 1.9 1.8 I
-I I
(30,2.53)
Ii LEGEND CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME (50,2.39)
SAFETY ANALYSES ASSUME THAT TWO OR MORE BYPASS VALVES ARE INOPERABLE PER SR 3.7.6.1 OR 3.7.6.2 INN Kr USED IN DETERMINING MFLCPR
- 1.
- 4.
1 N%N B 4
4-
-4.
_____________ +
(108,2.03)
(120 A
(81.8,2.03)-
L-I 4
4.
-4
REFERENCE:
T.S. 3.4.1, 3.7.6, and 3.2.2 I
I I-30 40 50 60 70 80 90 100 110 Total Core Flow (MLBIHR)
MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW MAIN TURBINE BYPASS INOPERABLE / EOC-RPT OPERABLE SINGLE LOOP OPERATION (BOC to EOC)
FIGURE 8.2-4
-u CD o
0--
CD r-6 0N N.
li I Im A
A* I A m m C
SSES UNIT 2 CYCLE 14 4.3 (25,4.25 LEGEND 4.1 CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM 3.9 INSERTION TIME
-H (30,3.74)
CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME 3.7 3.5 SAFETY ANALYSES ASSUME THAT TWO OR MORE BYPASS VALVES ARE INOPERABLE PER SR 3.7.6.1 OR 3.7.6.2 3.3
-J I
USED IN DETERMINING MFLCPR (D
0 g2.9 C
.- 3.0-O-279 2.5 2.3 (40,2.'32)-,m'Q" B '
mB 2.1 kA __(100,2.03) 1 (72.9,2.03)
_*> ~
1.9--
m.
REFERENCE:
T.S. 3.4.1, 3.7.6, and 3.2.2 1.7 20 30 40 50 60 70 80 90 100 rQ Core Power (% RATED) 0 "D
(<Z MCPR OPERATING LIMIT VERSUS CORE POWER
-n MAIN TURBINE BYPASS INOPERABLE /IEOC-RPT OPERABLE 6
SINGLE LOOP OPERATION (BOC to EOC) 0 FIGURE 8.2-5 4
)
PPL Rev. 6 PL-NF-07-002 Rev. 0 Page 40 of 47 EOC-RPT Inoperable I Main Turbine Bypass Operable SUSQUEHANNA UNIT 2 TRM/3.2-41 EFFECTIVE DATE 03/08/2007
e CZ) 2.3 M
2.2 2.1 2.0 0) 1.9 0
.2 1.9 e
e SSES UNIT 2 CYCLE 14 I
VI I 12 LEGEND CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME (50,2.08)
SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 I
i I
USED IN DETERMINING MFLCPR L.
.1~-
m m
CD) 00 1.8 (108,1.81)
B A
REFERENCE:
3.41,3.3.41,and3(80.5,1.21).2
REFERENCE:
T.S. 3.4.1, 3.3.4.1, and 3.2.2 1.7 30 40 50 60 70 80 90 100 110 Total Core Flow (MLBIHR)
MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW EOC-RPT INOPERABLE I MAIN TURBINE BYPASS OPERABLE SINGLE LOOP OPERATION (BOC to EOC)
FIGURE 8.2-6 (0<
(D -
Z 0
-n
-6
-h
- l CD 4
CK
1 U
V,)
Nm SSES UNIT 2 CYCLE 14 4.1 3.9 3.7 3.5
-(25,4.01)
I I
I I
(30,3.74)
LEGEND CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME I
cl) 3.3 E
-- 3.1 2.9 0.
(L 2.7 L) 2.5 SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 F.
USED IN DETERMINING MFLCPR m
m Cm m
m
-1 co
--j 2.3 2.1 1.9 1.7 4-,(40,2.26) 1
- 4.
4.
I J.
4 1
(100, I
I I
IREFERENCE:
T.S. 3.4.1, 3.3.4.1, and 3.2.2 (76,1.93) 1.93) 10 7
- 7.
4 20 30 40 50 60 Core Power (% RATED) 70 80 90 10 MCPR OPERATING LIMIT VERSUS CORE POWER EOC-RPT INOPERABLE I MAIN TURBINE BYPASS OPERABLE SINGLE LOOP OPERATION (BOC to EOC)
FIGURE 8.2-7
PPL Rev. 6 PL-NF-07-002 Rev. 0 Page 43 of 47 9.0 POWER I FLOW MAP 9.1 Technical Specification Reference Technical Specification 3.3.1.1 9.2 Description Monitor reactor conditions to maintain THERMAL POWER / core flow outside of Stability Regions I and II of the Power / Flow map, Figure 9.1.
If the OPRM Instrumentation is OPERABLE per TS 3.3.1.1, Region I of the Power / Flow map is considered an immediate exit region.
If the OPRM Instrumentation is inoperable per TS 3.3.1.1, Region I of the Power I Flow map is considered an immediate scram region.
Region II of the Power / Flow map is considered an immediate exit region regardless of the operability of the OPRM Instrumentation.
SUSQUEHANNA UNIT 2 TRM/3.2-44 EFFECTIVE DATE 03/08/2007
PPL Rev. 6 PL-NF-07-002 Rev. 0 Page 44 of 47 120 110-100.
90
Purpose:
]Initial
/ Date:
I STABILITY REGION I IF OPRM INOPERABLE IMMEDIATE SCRAM lAW ON-278-002 IF OPRM OPERABLE IMMEDIATE EXIT lAW ON-27-.002
- ======
- --.,.*UNIT 2
Tri Stpont POWER I FLOW MAP ARM Rod Block Trip Setpoint RESTRICTED REGION
+ I -- - - t
ý.
I MELILL Boundar 120 110 100 90 80
'U BMTAILITY REGION 11 MMFDIATELY EXIT lAW ON-278-002 I *,
ll RESTRICTED REGION
[As defined In Attachment G to NDAP-*A0338) 4_L M
a' LU A
I-80 70-60 50 40 30 20 10 0
.i:F A80VE MELLLA BOUNDARY, MMEDIATELY EXIT LAW ON-27"02 j
L j T -T 1-T I -I -I-T I -I -I-L
-t -j i ý-t-r 1 1-J-j j I 1 1-1 I - I i J -I-
-7 11 41 11 1 Natural Circulation Line Ell Approx J
One Pump I I 1 30% Speed.
T, r i
-j-r I
I L
J, I
Approx Two Pump 4 1-30% Speed.
j
+
I L I j J T
L I J _I-j L
+
T F -
I I
I I
I I.
IT-I I
1 1 I
I I
I F T
-I I
j j I ji II
~I. -WI-
-~
~j7 IL L I lU 60 50 K 2.,
,-ti
,~ ~
One mp r,,
L I
_JL
-I
-L L
L I
I I I I II L
I I
III 11z i
'1 "1- 0140,10-A-pr-I I
I One Pum
, :80-
-Spe
.,60 ij_70 ij_80_-ii_90 Li.IO0 i-i L I j I I II I
L 1 4 1 -
III'
- r 7 1 fl -
- I I
I I
40 30 20 10
_L. 3Jl I
I I
I T
T4- -1-I I T I
L 1.
- I I
I I
I. I I, ;.
6"4144*44419*4W1ý1i'*. I I i I I i I 1 0
0 10 20 30 40 50 60 70 80 90 100 110 Total Core Flow (Mlbmlhr)
(for SLO <75% Pump Speed Use Form GO-200-009-2)
Figure 9.1 SSES Unit 2 Cycle 14 Power / Flow Map SUSQUEHANNA UNIT 2 TRM/3.2-45 EFFECTIVE DATE 03/08/2007
PPL Rev. 6 PL-NF-07-002 Rev. 0 Page 45 of 47 10.0 OPRM SETPOINTS 10.1 Technical Specification Reference Technical Specification 3.3.1.1 10.2 Description Setpoints for the OPRM Instrumentation are established that will reliably detect and suppress anticipated stability related power oscillations while providing a high degree of confidence that the MCPR Safety limit is not violated. The setpoints are described in Section 2.0 and are listed below:
Sp 1.12
=
16 S
60 Mlbm / hr SUSQUEHANNA UNIT 2 TRM/3.2-46 EFFECTIVE DATE 03/08/2007
PPL Rev. 6 PL-NF-07-002 Rev. 0 Page 46 of 47
11.0 REFERENCES
11.1 The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC, specifically those described in the following documents:
- 1. XN-NF-81-58(P)(A), Revision 2 and Supplements 1 and 2, "RODEX2 Fuel Rod Thermal-Mechanical Response Evaluation Model," Exxon Nuclear Company, March 1984.
- 2. EMF-2361 (P)(A), Revision 0, "EXEM BWR-2000 ECCS Evaluation Model,"
Framatome ANP, May 2001.
- 3. EMF-2292(P)(A), Revision 0, "ATRIUMTM-10: Appendix K Spray Heat Transfer Coefficients," Siemens Power Corporation, September 2000.
- 4. XN-NF-84-105(P)(A), Volume 1 and Volume 1 Supplements 1 and 2, "XCOBRA-T: A Computer Code for BWR Transient Thermal-Hydraulic Core Analysis," Exxon Nuclear Company, February 1987.
- 5. XN-NF-80-19(P)(A), Volume I and Supplements 1 and 2, "Exxon Nuclear Methodology for Boiling Water Reactors: Neutronic Methods for Design and Analysis," Exxon Nuclear Company, March 1983.
- 6. XN-NF-80-19(P)(A), Volumes 2, 2A, 2B, and 2C "Exxon Nuclear Methodology for Boiling Water Reactors: EXEM BWR ECCS Evaluation Model," Exxon Nuclear Company, September 1982.
- 7. XN-NF-80-19(P)(A), Volume 3 Revision 2 "Exxon Nuclear Methodology for Boiling Water Reactors Thermex: Thermal Limits Methodology Summary Description," Exxon Nuclear Company, January 1987.
- 8. XN-NF-80-19(P)(A), Volume 4, Revision 1, "Exxon Nuclear Methodology for Boiling Water Reactors: Application of the ENC Methodology to BWR Reloads," Exxon Nuclear Company, June 1986.
- 9. XN-NF-85-67(P)(A), Revision 1, "Generic Mechanical Design for Exxon Nuclear Jet Pump BWR Reload Fuel," Exxon Nuclear Company, Inc.,
September 1986.
- 10. ANF-524(P)(A), Revision 2 and Supplements 1 and 2, "Advanced Nuclear Fuels Corporation Critical Power Methodology for Boiling Water Reactors,"
November 1990.
- 11. NE-092-001A, Revision 1, "Licensing Topical Report for Power Uprate With Increased Core Flow," Pennsylvania Power & Light Company, December 1992 and NRC SER (November 30, 1993).
SUSQUEHANNA UNIT 2 TRM/3.2-47 EFFECTIVE DATE 03/08/2007
PPL Rev. 6 PL-NF-07-002 Rev. 0 Page 47 of 47
- 12. ANF-89-98(P)(A) Revision 1 and Supplement 1,."Generic Mechanical Design Criteria for BWR Fuel Designs," Advanced Nuclear Fuels Corporation, May 1995'
- 13. EMF-2209(P)(A), Revision 2, "SPCB Critical Power Correlation," Framatome ANP, September 2003.
- 14. Caldon, Inc., "TOPICAL REPORT: Improving Thermal Power Accuracy and Plant Safety While Increasing Operating Power Level Using the LEFMITM System," Engineering Report - 80P, March 1997.
- 15. Caldon, Inc., "Supplement to Topical Report ER-80P: Basis for a Power Uprate with the LEFMITM or LEFM CheckPlusTM System," Revision 0, Engineering Report ER-1 60P, May 2000.
- 16. EMF-85-74(P)(A), Revision 0, Supplement 1(P)(A) and Supplement 2(P)(A),
"RODEX2A (BWR) Fuel Rod Thermal-Mechanical Evaluation Model,"
Siemens Power Corporation, February 1998.
- 17. EMF-2158(P)(A), Revision 0, "Siemens Power Corporation Methodology for Boiling Water Reactors: Evaluation and Validation of CASMO-4/Microburn-B2," Siemens Power Corporation, October 1999.
- 18. EMF-CC-074(P)(A), Volume 4, Revision 0, "BWR Stability Analysis -
Assessment of STAIF with Input from MICROBURN-B2," Siemens Power Corporation, August 2000.
- 19. NEDO-32465-A, "BWROG Reactor Core Stability Detect and Suppress Solutions Licensing Basis Methodology for Reload Applications," August 1996.
- 20. ANF-913(P)(A), Volume 1 Revisioni and Volume 1 Supplements 2, 3, and 4, "COTRANSA2: A Computer Program for Boiling Water Reactor Transient Analyses," Advanced Nuclear Fuels Corporation, August 1990.
- 21. ANF-1358(P)(A), Revision 3, "The Loss of Feedwater Heating Transient in Boiling Water Reactors," Framatome ANP, September 2005.
SUSQUEHANNA UNIT 2 TRM/3.2-48 EFFECTIVE DATE 03/08/2007