ML071200043
| ML071200043 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 04/20/2007 |
| From: | Susquehanna |
| To: | Gerlach R Document Control Desk, NRC/NRR/ADRO |
| References | |
| 028401, 2007-16181 | |
| Download: ML071200043 (74) | |
Text
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Apr.
20, 2007 Page 1 of 1 MANUAL HARD COPY DISTRIBUTION DOCUMENT TRANSMITTAL 2007-16181 USER INFORMATION:
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TENTION:
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SSES MANUAL Manual Name:
TRM2 Manual
Title:
TECHNICAL REQUIREMENTS MANUAL UNIT 2 Table Of Contents Issue Date:
04/19 Procedure Name TEXT LOES
Title:
LIST OF EFFECT:
/2007 Rev Issue Date 36 04/19/2007 IVE SECTIONS 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
/
TEXT 2.1 1
02/04/20,05\\
Title:
PLANT PROGRAMS AND SETPOINTS PLANT-PROGRAMS TEXT 2. 2 6
- 04/0t9120.O,7
Title:
PLANT PROGRAMS AND SETPOINTS/INSTRUMENT-TRIP SETPOINT TABLE TEXT 3.0 2->
0.,-/29/2007
Title:
APPLICABILITY TECHNICAL REQUIREMENT FOR OPERATION (TRO)
APPLICABILITY TEXT 3.1.1 01" 11/19/2002
Title:
REACTIVITY CONTROL'SYSTEMS ANTICIPATED TRANSIENT WITHOUT SCRAM ALTERNATE ROD INJECTION (ATWS-ARI)
INSTRUMENTATION TEXT 3.1.2 0
11/19/2002
Title:
REACTIVITY CONTROL SYSTEMS CONTROL ROD DRIVE (CRD)
HOUSING SUPPORT TEXT 3.1.3 3
04/09/2007
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 7
04/19/2007
Title:
CORE OPERATING LIMITS CORE OPERATING LIMITS REPORT (COLR)
Page 1 of 15 Report Date: 04/19/07 Page 1 of 15 Report Date: 04/19/07
SSES MANUAL Manual Name:
TRM2 Manual
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 1
04/26/2006
Title:
INSTRUMENTATION 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 2
04/09/2007
Title:
INSTRUMENTATION LPRM UPSCALE ALARM INSTRUMENTATION TEXT 3.3.10 1
12/14/2004
Title:
INSTRUMENTATION REACTOR RECIRCULATION PUMP MG SET STOPS TEXT 3.3.11 1
10/22/2003
Title:
INSTRUMENTATION MVP ISOLATION INSTRUMENTATION TEXT 3.4.1 1
04/26/2006
Title:
REACTOR COOLANT SYSTEM REACTOR COOLANT SYSTEM CHEMISTRY Page 2 of 15 Report Date: 04/19/07 Page 2 of 15 Report Date: 04/19/07
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 T7 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 10
Title:
PLANT SYSTEMS EMERGENCY SERVICE WATER SYSTEM (ESW)
SHUTDOWN Page 3-of 15 Report Date: 04/19/07
SSES MANUAL Manual Name:
TRM2 Manual
Title:
TECHNICAL REQUIREMENTS MANUAL UNIT 2 TEXT 3.7.2
Title:
PLANT TEXT 3.7.3.1
Title:
PLANT TEXT 3.7.3.2
Title:
PLANT TEXT 3.7.3.3
Title:
PLANT TEXT 3.7.3.4
Title:
PLANT TEXT 3.7.3.5
Title:
PLANT TEXT 3.7.3.6
Title:
PLANT TEXT 3.7.3.7
Title:
PLANT TEXT 3.7.3.8
Title:
PLANT TEXT 3.7.4
Title:
PLANT TEXT 3.7.5.1
Title:
PLANT TEXT 3.7.5.2
Title:
PLANT 0
11/19/2002 SYSTEMS ULTIMATE HEAT SINK (UHS)
AND GROUND WATER LEVEL 1
04/26/2006 SYSTEMS FIRE SUPPRESSION WATER SUPPLY SYSTEM 2
04/26/2006 SYSTEMS SPRAY AND SPRINKLER SYSTEMS 2
08/18/2005 SYSTEMS C02 SYSTEMS 1
04/26/2006 SYSTEMS HALON SYSTEMS 1
04/26/2006 SYSTEMS FIRE HOSE STATIONS 1
04/26/2006 SYSTEMS YARD FIRE HYDRANTS AND HYDRANT HOSE HOUSES 1
04/26/2006 SYSTEMS FIRE RATED ASSEMBLIES 6
12/14/2006 SYSTEMS FIRE 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 0
Page 4 of 15 Report Date: 04/19/07 Page A of 15 Report Date: 04/19/07
SSES MANUJAL 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 1
02/04/2005
Title:
ELECTRICAL POWER 24 VDC ELECTRICAL SUBSYSTEM TEXT 3.8.5 0
11/19/2002
Title:
ELECTRICAL POWER DEGRADED VOLTAGE PROTECTION Page ~
of 15 Report Date: 04/19/07 Page 5 of 15 Report Date: 04/19/07
SSES MANUAL Manual Name:
TRM2 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 1
04/26/2006
Title:
MISCELLANEOUS SEALED-SOURCE CONTAMINATION TEXT 3.10.2 1
04/09/2007
Title:
MISCELLANEOUS SHUTDOWN MARGIN TEST RPS INSTRUMENTATION TEXT 3.10.3 1
"04/26/2006
Title:
MISCELLANEOUS INDEPENDENT SPENT FUEL STORAGE INSTALLATION (ISFSI)
TEXT 3.10.4 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 j.~
Report Date: 04/19/07 Page6 of 15 Report Date: 04/19/07
SSES MANUAL.
Manual Name:
TRM2 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 EFFLUENTS EFFLUENTS EFFLUENTS EFFLUENTS EFFLUENTS 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 3
11/14/2006 VENTILATION EXHAUST TREATMENT SYSTEM 2
12/14/2004 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION 1
04/26/2006 TOTAL DOSE 3
04/26/2006 MONITORING PROGRAM 2
04/26/2006 LAND USE CENSUS TEXT 3.11.4.3 1
04/26/2006
Title:
RADIOACTIVE EFFLUENTS INTERLABORATORY COMPARISON PROGRAM Page 7 of 15 Report Date: 04/19/07 Page 2 of 15 Report Date: 04/19/07
SSES MANUAL Manual Name:
TRM2 Manual
Title:
TECHNICAL REQUIREMENTS MANUAL UNIT 2 TEXT 3.12.1
Title:
LOADS CONTROL TEXT 3.12.2
Title:
LOADS CONTROL 0
11/19/2002 PROGRAM CRANE TRAVEL-SPENT FUEL STORAGE POOL 1
10/12/2006 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 ROD INJECTION (ATWS-ARI)
INSTRUMENTATION SCRAM ALTERNATE TEXT B3.1.2 0
11/19/2002 -
Title:
REACTIVITY CONTROL SYSTEM BASES CONTROL ROD DRIVE (CRD)
HOUSING SUPPORT TEXT B3.1.3 3
04/10/2007
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.
Title:
.3 1
02/04/2005 INSTRUMENTATION BASES METEOROLOGICAL MONITORING INSTRUMENTATION Page8 of 2.~
Report Date: 04/19/07 Page 8 of 15 Report Date: 04/19/07
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:
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 2
04/10/2007 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 TEXT B3.4.2 0
11/19/2002
Title:
REACTOR COOLANT SYSTEM BASES STRUCTURAL INTEGRITY TEXT B3.4.3 0
11/19/2002
Title:
REACTOR COOLANT SYSTEM BASES HIGH/LOW PRESSURE INTERFACE LEAKAGE MONITOR TEXT B3.4.4 0
11/19/2002
Title:
REACTOR COOLANT SYSTEM BASES REACTOR RECIRCULATION FLOW AND ROD LINE LIMIT Page 9 of 15 Report Date: 04/19/07
SSES MANUTAL 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 1
04/19/2007
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 10 of 15 Report Date: 04/19/07
SSES MANTIAL 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 I
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 D
Title:
PLANT SYSTEMS BASES MAIN CONDENSER OFFGAS PRETREATMENT LOGARITHMIC RADIATION MONITORING INSTRUMENTATION Page 11 of 15 Report Date: 04/19/07
SSES MANUAL Manual Name:
TRM2 Manual
Title:
TECHNICAL REQUIREMENTS MANUAL UNIT 2 TEXT B3.7.8 2
Title:
PLANT SYSTEMS BASES SNUBBERS 10/12/2006 TEXT B3.7.9 1
12/14/2004
Title:
PLANT SYSTEMS BASES CONTROL STRUCTURE HVAC TEXT B3.7.10 1
12/14/2004
Title:
PLANT SYSTEMS BASES SPENT FUEL STORAGE POOLS TEXT B3.8.1 1
02/04/2005
Title:
ELECTRICAL POWER BASES PRIMARY CONTAINMENT PENETRATION CONDUCTOR OVERCURRENT PROTECTIVE DEVICES TEXT B3.8.2.1 0
11/19/2002
Title:
ELECTRICAL POWER BASES MOTOR OPERATED VALVES (MOV)
THERMAL OVERLOAD PROTECTION CONTINUOUS TEXT B3.8.2.2 1
09/17/2004
Title:
ELECTRICAL POWER BASES MOTOR OPERATED VALVES (MOV)
THERMAL OVERLOAD PROTECTION AUTOMATIC TEXT B3.8.3
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 DIESEL GENERATOR (DM)
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
Title:
.1 0
11/19/2002 REFUELING OPERATIONS BASES DECAY TIME Page 12 of 25.
Report Date: 04/19/07 Page 12 of 15 Report Date: 04/19/07
SSES MANUTAL~
Manual Name:
TRM2 Manual
Title:
TECHNICAL REQUIREMENTS MANUAL UNIT 2 TEXT B3.9.2 0
11/19/2002
Title:
REFUELING OPERATIONS BASES COMMUNICATIONS TEXT B3.9.3 0
11/19/2002
Title:
REFUELING OPERATIONS BASES REFUELING PLATFORM TEXT B3.10.1
Title:
MISCELLANEOUS TEXT B3.10.2
Title:
MISCELLANEOUS TEXT B3.10.3
Title:
MISCELLANEOUS 0
BASES SEALED 11/19/2002 SOURCE CONTAMINATION 1
04/10/2007 BASES SHUTDOWN MARGIN TEST RPS INSTRUMENTATION 0
11/19/2002 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 0
11/19/2002 EFFLUENTS BASES LIQUID EFFLUENTS CONCENTRATION TEXT B3.11.1.2 0
"11/19/2002
Title:
RADIOACTIVE EFFLUENTS BASES LIQUID EFFLUENTS DOSE TEXT B3.11.1.3
Title:
RADIOACTIVE TEXT B3.11.1.4
Title:
RADIOACTIVE 0
11/19/2002 EFFLUENTS BASES LIQUID WASTE TREATMENT SYSTEM EFFLUENTS 0
BASES 0
BASES 11/19/2002 LIQUID RADWASTE EFFLUENT MONITORING INSTRUMENTATION TEXT B3.11.1.5
Title:
RADIOACTIVE EFFLUENTS 11/19/2002 RADIOACTIVE LIQUID PROCESS MONITORING INSTRUMENTATION TEXT B3.11.2.1 1
12/14/2004
Title:
RADIOACTIVE EFFLUENTS BASES DOSE RATE Page 1~.
of 15 Report Date: 04/19/07 Page 13 of 15 Report Date: 04/19/07
SSES MANUJAL 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 1
01/27/2004 BASES RADIOACTIVE GASEOUS 0
11/19/2002 BASES TOTAL DOSE 2
01/06/2006 BASES MONITORING PROGRAM TREATMENT SYSTEM EFFLUENT MONITORING TEXT B3.11.4.2 1 0 11/19/2002
Title:
RADIOACTIVE EFFLUENTS BASES LAND USE CENSUS TEXT B3.11.4.3 0
11/19/2002
Title:
RADIOACTIVE EFFLUENTS BASES INTERLABORATORY COMPARISON PROGRAM TEXT B3.12.1
Title:
LOADS CONTROL PROGRAM 0
11/19/2002 BASES CRANE TRAVEL-SPENT FUEL STORAGE POOL TEXT B3.12.2 0
11/19/2002
Title:
LOADS CONTROL PROGRAM BASES HEAVY LOADS REQUIREMENTS TEXT B3.12.3 0
11/19/2002
Title:
LOADS CONTROL PROGRAM BASES LIGHT LOADS REQUIREMENTS Page 14 of 15 Report Date:
04/19/07 Page 14 of 15 Report Date: 04/19/07
SSES MANUAL Manual Name:
TRM2 O
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:
TEXT 4.7
Title:
ADMINISTRATIVE CONTROLS ADMINISTRATIVE ADMINISTRATIVE ADMINISTRATIVE ADMINISTRATIVE ADMINISTRATIVE ADMINISTRATIVE 0
CONTROLS 0
CONTROLS 0
CONTROLS 0
CONTROLS 0
CONTROLS 0
CONTROLS 09/27/2003 ORGANIZATION 09/27/2003 REPORTABLE EVENT ACTION 09/27/2003 SAFETY LIMIT VIOLATION 09/27/2003 PROCEDURES & PROGRAMS 09/27/2003 REPORTING REQUIREMENTS 09/27/2003 RADIATION PROTECTION PROGRAM 09/27/2003 TRAINING
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Page 25.
of j~
Report Date: 04/19/07 Page 15 of 15 Report Date: 04/19/07
SUSQUEHANNA STEAM ELECTRIC STATION PPL Rev. 36 LIST OF EFFECTIVE SECTIONS (TECHNICAL REQUIREMENTS MANUAL)
Section Title TOC TABLE OF CONTENTS 1.0 2.0 3.0 3.1 3.2 3.3 USE AND APPLICATION Page TRM / 1.0-1 Page TRM / 1.0-2 Page TRM / 1.0-3 PLANT PROGRAMS Page 2.0-1 Pages TRM / 2.0-2 and TRM 2.0-3 Page TRM / 2.0-4 Page TRM / 2.0-5 Pages TRM / 2.0-6 and TRM / 2.0-7 Page TRM / 2.0-8 Pages TRM / 2.0-9 through TRM / 2.0-11 Page TRM / 2.0-12 Pages TRM / 2.0-13 and TRM / 2.0-14 Page TRM / 2.0-15 APPLICABILITY Pages TRM / 3.0-1 and TRM / 3.0-21 Page TRM / 3.0-3 Page TRM / 3.0-4 REACTIVITY CONTROL SYSTEMS Pages 3.1-1 through 3.,1-5, Pages TRM / 3.1-6,through TRM /3.1-8 Pages TRM / 3.1-9 and-TRM/ 3.1-9a Page TRM /3 1-1 CORE OPERATING LIMITS REPORT Page TRM. /3.2-*1 Pages TRM /i3.2"2 through TRM / 3.2-48 INSTRUMENTATION Pages TRM / 3.3-1 through TRM / 3.3-3 Page TRM / 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 / 3.3-9a Page TRM / 3.3-10 Page TRM / 3.3-11 Page TRM / 3.3-11a Page TRM / 3.3-12 Page TRM / 3.3-13 Page TRM / 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 03/27/2007 12/03/2004 11/15/2004 03/27/2007 11/15/2004 11/15/2005 01/10/2007 03/15/2002 11/30/2005 08/31/1998 03/27/2007-02/18/1999 02/18/1999 08/31/1998 03/30/2007 07/16/1999 03/31/2006 08/31/1998 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 SUSQUEHANNA - UNIT 2 TRM / LOES-1 EFFECTIVE DATE 04/04/2007
SUSQUEHANNA STEAM ELECTRIC STATION PPL Rev. 36 LIST OF EFFECTIVE SECTIONS (TECHNICAL REQUIREMENTS MANUAL)
Section Title Effective Date 3.4 3.5 3.6 Page TRM / 3.3-16 Pages TRM / 3.3-17 and TRM / 3.3-18 Pages TRM / 3.3-19 and TRM / 3.3-20 Page TRM / 3.3-21 Page TRM / 3.3-21a Pages TRM /3.3-21b 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 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 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 T-RM / 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 / 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 / 3.7-17 Page TRM / 3.7-18 Page TRM / 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 06/27/2001 06/14/2002 10/22/2003 03/27/2007 11/15/2004 03/27/2007 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 3.7 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
- UNIT 2 TRM I LOES-2 EFFECTIVE DATE 04/04/2007 SUSQUEHANNA - UNIT 2 TRM / LOES-2 EFFECTIVE DATE 04/04/2007
SUSQUEHANNA STEAM ELECTRIC STATION PPL Rev. 36 LIST OF EFFECTIVE SECTIONS (TECHNICAL REQUIREMENTS MANUAL)
Section Title Page TRM / 3.7-29 Page TRM / 3.7-30 Page TRM / 3.7-31 Page TRM / 3.7-32 Page TRM / 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 / 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 / 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 / 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 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 3.8 3.9 REFUELING OPERATIONS Pages 3.9-1 through 3.9-3 3.10 MISCELLANEOUS Page TRM / 3.10-1 Pages 3.10-2 through 3.10-4 Pages TRM / 3.10-5 and TRM / 3.10-6 Page TRM / 3.10-7 Page TRM / 3.10-8 08/31/1998 03/31/2006 08/30/1998 03/27/2007 03/31/2006 08/16/2006 SUSQUEHANNA - UNIT 2 TRM / LOES-3 EFFECTIVE DATE 04/04/2007
SUSQUEHANNA STEAM ELECTRIC STATION PPL Rev. 36 LIST OF EFFECTIVE SECTIONS (TECHNICAL REQUIREMENTS MANUAL)
Section Title Effective Date 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 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
- D3/31/2006 11/30/2005 08/31/1998 03/31/2006 08/31/1998 03/31/2006 02/05/1999 09/30/2006 02/05/1999 08/31/1998 3.12 4.0 SUSQUEHANNA - UNIT 2 TRM / LOES-4 EFFECTIVE DATE 04/04/2007
SUSQUEHANNA STEAM ELECTRIC STATION PPL Rev. 36 LIST OF EFFECTIVE SECTIONS (TECHNICAL REQUIREMENTS MANUAL)
Section Title Effective Date B 3.0 B 3.1 B 3.2 B 3.3 B 3.4 B 3.5 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 / 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 / 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 3.3-42 Page TRM / B 3-3-13 Page TRM / B 3.3 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 I 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 ECCS AND RCIC BASES Pages B 3.5-1 through B 3.5-5 08/31/1998 01/10/2007 08/31/1998 03/15/2002 11/30/2005 03/15/2002 07/13/1999 08/31/1998 03/27/2007 02/18/1999 08/31/1998 04/07/2000 08/31/1998 01/31/2005 05/30/2006 03/30/2001 08/31/1998 09/13/2005 12/03/2004.
06/25/2002
-06114/2002 06/14/2002 10/22/2003 10/22/2003 10/22/2003 03/27/2007 03/27/2007 05/16/2003 10/22/2003 05/16/2003 08/31/1998 10/15/1999 08/31/1998 08/31/1998 SUSQUEHANNA - UNIT 2 TRM / LOES-5 EFFECTIVE DATE 04/04/2007
SUSQUEHANNA STEAM ELECTRIC STATION PPL Rev. 36 LIST OF EFFECTIVE SECTIONS (TECHNICAL REQUIREMENTS MANUAL)
Section Title B 3.6 B 3.7 B 3.8 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 Page TRM / B 3.6-5 Page TRM / B 3.6-6 Pages TRM / B 3.6-7 through TRM / B 3.6-11 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 3.7-10a through TRM / B 3.7-11a 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 I 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 07/26/2001 02/01/1999 08/31/1998 03/29/2007 04/04/2007 12/03/2004 12/31/2002 08/31/1998 08/02/1999 03/31/2006 08/02/1999 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 04/04/2007
SUSQUEHANNA STEAM ELECTRIC STATION PPL Rev. 36 LIST OF EFFECTIVE SECTIONS (TECHNICAL REQUIREMENTS MANUAL)
Section Title Effective Date 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 08/31/1998 10/23/1998 B 3.10 MISCELLANEOUS BASES Page B 3.10-1 Pages TRM / B 3.10-2 and 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 3.11-11 a Pages TRM/B 3.11-12 and TRM/B 3.11-13 Page TRM / B 3.11-14 Page TRM / B 3.11-15 Pages B 3.11-16 through B 3.11-19 Page TRM / B 3.11-20 Page TRM / B 3.11-20a 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 13.11-24 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 B.3.12 LOADS CONTROL PROGRAM BASES Pages TRM / B 3.12-1 through TRM / B 3.12-3 08/31/1998 03/27/2007 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 02/05/1999 LDCN4461 TRM2 text LOES.doc 4/2/07 SUSQUEHANNA - UNIT 2 TRM / LOES-7 EFFECTIVE DATE 04/04/2007
Core Operating Limits Report (COLR)
PPL Rev. 7 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 1 3.2-1 EFFECTIVE DATE 08131/1998
PPL Rev-7 PL-NF-07-002 Rev. 1 Page 1 of 47 Susquehanna SES Unit 2 Cycle 14 CORE OPERATING LIMITS REPORT Nuclear Fuels Engineering March 2007 p
SUSQUEHANNA UNIT 2
'TRM/3.2-2 EFFECTIVE DATE 03/30/2007
PPL Rev. 7 PL-NF-07-002 Rev. 1 Page 2 of 47 CORE OPERATING LIMITS REPORT REVISION DESCRIPTION INDEX Rev.
Affected No.
Sections Description/Purpose of Revision 0
1 ALL 6.0 Issuance of this COLR is in support of Unit 2 Cycle 14 operation.
Figure 6.2-2 changed per AR 855311855311to improve operating margin.
FORM NFP-QA-008-2, Rev. 1 SUSQUEHANNA UNIT 2 TRM/3.2-,3 EFFECTIVE DATE 03/30/2007
PPL Rev. 7 PL-NF-07-002 Rev. 1 Page 3 of 47 SUSQUEHANNA STEAM ELECTRIC STATION Unit 2 Cycle 14 CORE OPERATING LIMITS REPORT Table of Contents 1.0 INTR O DUCTIO N....................................................................................................
4 2.0 DEFINITIO NS......................................................................................................
5 3.0 SHUTDOWN MARGIN................................................
6 4.0 AVERAGE PLANAR LINEAR HEAT GENERATION RATE (APLHGR).................
7 5.0 MINIMUM CRITICAL POWER RATIO (MCPR)...............................
9 6.0 LINEAR HEAT GENERATION RATE-(LHGR)............................
21 7.0 ROD-BLOCK MONITOR (RBMI)
SETPOINTS AND OPERABILITY REQUIREMENTS...............................................
29 8.0 RECIRCULATION LOOPS - SINGLE LOOP OPERATION.......................
31 9.0 POW ER / FLOW MAP............................................................................................
43 10.0 OPRM SETPO INTS................................................................................................
45 11.0 R E FE R E N C ES...........................................................................................
.............. 46 SUSQUEHANNA UNIT 2 rRM/3,2-4 EFFECTIVE DATE 03/30/2007
PPL Rev. 7 PL-NF-07-002 Rev. 1 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 03/30/2007
PPL Rev. 7 PL-NF-07-002 Rev. 1 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 LHGRFACr is a multiplier applied to the LHGR limit when operating at less than 108 Mlbmlhr core flow. The LHGRFACf multiplier protects against both fuel centedine melting and cladding strain during anticipated system transients initiated from core flows less than 108 Mlbmlhr, 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 Moniter-(OPRM) will reliably detect and suppress anticipated stability related power oscillations while providing a high degree of confidence thatthe 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. be4ow which the OPRM RPS trip is activated.
SUSQUEHANNA UNJT 2 TRM/3.2-6 EFFECTIVE DATE 03/30/2007
PPL Rev. 7 PL-NF-07-002 Rev. 1 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 (BOO) SHUTDOWN MARGIN (SDM) tests must also account for changes in core reactivity during the cycle. Therefore, the SDM measured at BOC must be equal to or greater than the applicable requirement from either 3.2.a or 3.2.b plus an adder, "R". The adder, "R", is the difference between the calculated value of maximum core reactivity (that is, minimum SDM) during the operating cycle and the calculated BOO core reactivity. If the value of 4RR is zero (that is, BOC is the most reactive point in the cycle) no correction to the BOO 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 TRMI3,2_-7 EFFECTIVE DATE 03/30/2007
PPL Rev. 7 PL-NF-07-002 Rev. 1 Page 7 of 47 4.0 AVERAGE PLANAR LINEAR HEAT GENERATION RATE (APLHGR) 4.1 Technical Soecification Reference Technical Specification 3.2.1 42 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 OATE 03/30/2007
SSES UNIT 2 CYCLE 14 (16 44 124 44.44 INDETERMINING MAPRAT 0.0,12.5" ",""
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I FIGUR 4.2-1l I
I
PPL Rev. 7 PL-NF-07-002 Rev. 1 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-1O) 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 EOG 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 TRMI3.2-10 EFFECTIVE DATE 03/30/2007
PPL Rev. 7 PL-NF-07-002 Rev. 1 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 IRM/3.2-11 EFFECTIVE DATE 03/30/2007
PPL Rev. 7 PL-NF-07-002 Rev. 1 Page 11 of 47 EOC-RPT and Main Turbine Bypass Operable SUSQUEHANNA UNIT 2 TRM/3.2-12 EFFECTIVE DATE 03/3012007
(A (A
--.4 2.2 2.1 2.0 1.9 (A
(A 4V1.7 CL.1 1,.6 4
SSES UNIT 2 CYCLE 14 LEGEND CURVE A-MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME 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 (50,1.62)
J
REFERENCE:
T.S. 3.2.2 (86.3,1.37)
(108,1.37)1 F'1
~~11
~11ni
~~~1
-.4
-1Ev~
(A (A
N) 1.5 1.4 1.3 1.2 30 40 50 60 70 80 90 100 110 Total Core Flow (MLB/HR)
MCPR OPEFATING LIMIT VERSUS TOTAL CORE FLOW EOC-RPT AND, MAIN TURBINE BYPASS OPERABLE TWO LOOP OPERATION (BOC TO EOC)
FIGURE 5.2-1
-u XT z
I
-n<
6D 6
,CD Nz rn m
C>
C0 NJ SSES UNIT 2 CYCLE 14 3.5 3.4 3.3 3.2 3.1 3.0 2.9 2.8 t
2.7 E.j 2.6 2.5 2.4 CL 0 2.3 a:
C. 2.2
=E2.1 2.0 1.9 1.8 1.7 1.6 1.5 1.4 1.3 LEGEND CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM (25,3.15)
INSERTION TIME
-CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME (302.4)..
I....
1 77-SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 USED IN DETERMINING MFLCPR MFCP I- -____________
... i.
r-"
I-D v
(40,1.76) 1
-V A--
I I
I 4
4 (40,1.68) l!
II
-I w1 -
4I a
I
REFERENCE:
T.S. 3.2.21 I
1 1 (65~1.58)7 (80,1.47)
(85.1-.44)-
(100,1.41) 4 I
1 M(100,1.37)
II ___________
I~
I.
20 30 40 50 60 70 80 90 100
. Core Power (% RATED)
MCPR OqERATING LIMIT VERSUS CORE POWER EOC-RPT AND MAIN TURBINE BYPASS OPERABLE TWO LOOP OPERATION (BOC TO EOC)
FIGURE 5.2-2 (b Z
-n 6~.
N
PPL Rev. 7 PL-NF-07-002 Rev. 1 Page 14 of 47 Main Turbine Bypass Inoperable / EOC-RPT Operable SUSQUEHANNA UNIT 2 TRM/3.2-15 EFFECTIVE DATE 03/30/2007
VI) c:
V),
SSES UNIT 2 CYCLE 14 2.3 2.2 I
I I
LEGEND CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME K
2.1 2.0 (30,1.98) 4
- 4.
4-I SAFETY ANALYSES ASSUME THAT TWO OR MORE BYPASS VALVES ARE INOPERABLE PER SR 3.7.6.1 OR 3.7.6.2 r
(,~1 N,
E1.9 1.8 0.
(.1.7 f!1 "1 R71
- 4.
1-~
3 U
1 -~~ I F
I USED IN DETERMINING MFLCPR F
V C-,
N-)
1.6 1.5 A
(81.8,1.58)
(108,1.58)
RE FERNCE: T.S. 3.7.6a.d322' 1.4-1.3 30 40 50 60 70 80 90 100 110 Total Core Flow (MLBIHR)
MCPR OPEFRATING LIMIT VERSUS TOTAL CORE FLOW MAIN TURBINE BYPASS INOPERABLE I EOC.RPT OPERABLE TWO LOOP OPERATION (BOC TO EOC)
FIGURE 5.2-3
-u (D
0
- 0 x
0
<I
. z
-71
0, m
SSES UNIT 2 CYCLE 14 E
C, 0
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 m
m rn m
-1m c~)
C)
C)
C)
(100,1.58) 20 30 40 50 60 70 80 90 Core Power (% RATED)
MCPR OIqERATING LIMIT VERSUS CORE POWER MAIN TURBINE BYPASS INOPERABLE I EOC-RPT OPERABLE TWO LOOP OPERATION (BOC to EOC)
FIGURE 5.2-4 100 03 xD v
co <
(D~
0)
PPL Rev. 7 PL-NF-07-002 Rev. I Page 17 of 47 EOC-RPT Inoperable /
Main Turbine Bypass Operable SUSQUEHANNA 'UNIT 2 TRM / 3. 2 -18 EFFECTIVE DATE 03/30/2007
V)
N)
SSES UNIT 2 CYCLE 14 2.2 2.1 2.0 1.9 20
~1.8 CL 0
Ix 0- 1.6 m
m 1.5 1.4 1.3 1.2 30 60 40 50 70 80 90 100 110 Total Core Flow (MLB/HR)
MCPR OPEF*ATING LIMIT VERSUS TOTAL CORE FLOW EOC-RPT INOPERABLE / MAIN TURBINE BYPASS OPERABLE TWO LOOP OPERATION (BOC TO EOC)
FIGURE 5.2-5 Co
-A.co z-n 6
-4
rnl
--4 CA)
N) cND CL 0.m 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 SSES UNIT 2 CYCLE 14 LEGEND 5,3.15)
CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM (25,3.15)...
INSERTION TIME S(30,2.94)
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 (40,1166)
- A IRE=ERENCE: T.S. 3.3.4.1 and 3.2.2"l
_... B (8 0,1.4 7 )
-U CD
-4 C-)
CID (100,1.41) 20 30 40 5o 60 70 80 90 100 Core Power (% RATED)
MCPR OPERATING LIMIT VERSUS CORE POWER EOC-RPT INOP'ERABLE / MAIN TURBINE BYPASS OPERABLE TWO LOOP OPERATION (BOC to EOC)
FIGURE 5.2-6
-n 6O
PPL Rev. 7 PL-NF-07-002 Rev, 1 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 0630 0.860 25 1.500 1.910 5
2.700 3.440 Average Scram Realistic Maximum Insertion Time Allowable SUSOUEHANNA UNTT 2 T'RM!3.2-21 EFFECTIVE DATE 03/30/2007
PPL Rev. 7 PL-NF-07-002 Rev. 1 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 ATRIUMT1-10 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 / 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 likit 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,..2-2 EFFECTIVE DATE 03/30/2007
0 o
16 14 Nr SSES UNIT 2 CYCLE 14 m
-J N)
CD) m rn rn 0
C)
_12 2
6.
0)
I-1 X 8
.3 6
I 4
I i
I I
4 4
i 4
g 4
4 4
4 1
4 4
1 4
.i.
0.0,13.4
- 18900,13.4
- 3
REFERENCE:
TS. 3.2.3 USED IN DETERMININGFDLRXJ"
.¶..
4 p
p t
I 4
4 I
4I i i r
I I*
l I
4 i4
)
4i I i
i4 4
4 4
4 4I 4
4
¶ 4
I 4I I
4 4I 4*
I 1
1 4
4 l
I I
I I
I 4
4 4
4 4
4 4
I p
I I
4 4
4 4
4 4i i
Il l
l II iI I
I I
j I
I i i }
4 P
4 I
4
]
I 4
,l4 4
r 4
4 4
4i 1
4 i 4
4 i 1
I.11 i*
e*
~
~
~
~
.1.
I i
I.
I@
- .**w.
l
- I@
v J-I.i..**
.74400,7.10 I
4 4
I tI 4
4
~4I I
1 44I I
S I
Ir I
I p
4 4
44 I
I 4
4 4
4 4
4 4
I a
G,
ýc <
D C
0
-4 4
0 10000 20000 30000 40000 50000 60000 70000 80000 Pellet Exposure (MWD/MTU)
LINEAR HEAT GENERATION RATE LIMIT VERSUS PELLET EXPOSURE ATRIUMT-10 FUEL FIGURE 6.2-1
PPL Rev. 7 PL-NF-07-002 Rev. 1 Page 23 of 47 Main Turbine Bypass Operable I EOC-RPT Operable and Inoperable SUSQUEHANNA UNIT 2 TRM/3. 2 -24 EFFECTIVE DATE 03/30/2007
U0 a
SSES UNIT 2 CYCLE 14 O
1.10
. 1...
1...
1 1
"1.....
I a
a A
I I
~~7
,1.001 00 0
o0...
a
]
i
.oJ
.*..=o*...*................
- ° I.......
A A
A A
a I
A A
1 A
A o ~~.
0
.8 qj L9
- c O* 0,.....
0.70 CL Z
J........
RD................................................................-
C-)
0.50
--H rn*
C) 0.40 30 C)
"4 a
a A
l AA
REFERENCE:
TA$. 3.2.3and3..
A A
A a
a SEDNDEERMINING FDLRX 40 50
,60 70 80 90 100 110 A Total Core Flow (MLB/hr)
CD Z
FLOWpEPENDENT LHGR LIMIT MULTIPLIER t
MAIN TURBINE BYPASS OPERABLE ATRIUMTM-i0 FUEL C)
FIGURE 6.2-2
9*
<SSES UNIT 2 CYCLE 14 1
10 i*~aa a
i o
a a
I
- Iti I
a a
a a
I aa Ii a
a a
a a
a a
a a
r a
- o.
0
"'÷..........
I....
1..........
=.....
.+.....
0.8:
.....I o.
r1o a
a a
a (10,1.00 R
a a
3a2
.3 a
n a
.. I..
- a.
a a
I.......
0.50 0
.70..
0........*...
A P
LS......A 0.4 20 30 40 50 so 70 80 90 100 a
Cor Poe
(%
USDATEETRINNGD)R rr a
a a
a a
a
(:
r
-,,0u.....
~
- a.
a...
a0
.40 I*I
~
.i p
liI*.*
!i i
m aing a..
J I
1l 1
l 20
=30 4+0,50,7 0
0 0
POWER DEPENDENT LHGR LIMIT MULTPLIER MAIN TURBINE BYPASS OPERABLE R
o..
U M M~
0, 0.
ATRIUMT 01 FUEL 4
FIGURE 6.2-3
PPL Rev. 7 PL-NF-07-002 Rev. 1 Page 26 of 47 Main Turbine Bypass Inoperable I EOC-RPT Operable and Inoperable SUSQUEHANNA UNIT 2
'TRM/3-2-27 EFFECTIVE DATE 03/30/2007
CSSES UNIT 2 CYCLE 14 1j.1u
-r-
=1.00 0.90 t y 0.80 u
4"1 0= 0.70 Q.
0.
0.60 0.50 C=?
CW 0.40 3
N) 4 4
4 4
a S
i a
a 1
4 4
4
,i ii I
a a
1 a
a a
a I
1 I
4 P
I 4
I I
4 4
4 I
4 4
t I
1 6
a a
I 4
4 i
4 3
I 4
1 4
4 ~
1' a
(9....
)
.(.. 8...
.)
SAFETY ANALYSES ASSUME THAT TWO OR MORE BYPASS SVALVES ARE INOPERABLE PER SR 3.7..1 OR 3.7.62 3
4 I
i I
4 4
l 5
4 4
4 I
S i
4 I
I S
i S
i i.i
~USED IN DETERMINING FDLRX
~.............E.YPA...
.A.
I N O.
P 3
44I44I S
I i
3 u-(D
-4 O
40 50 60 70 80 90 100 110
,Total Core Flow (MLB!HR)
(D (0<
FLOW PEPENDENT LHGR LIMIT MULTIPLIER MAIN TURBINE BYPASS INOPERABLE 0
4~o ATRIUMTM-10 FUEL FIGURE 6.2-4
t4 SSES UNIT 2 CYCLE 14 c1.00 0.90 ce 0.80 a.
L 0.70 0l.60
-T-m 0.50 c) 0.40 CC 0.6
-n,.
I a
a a
a b
a I
a a
I a
ap1 a
a a
- a.
a 1
a,0 a
(100,0.90)
..... I I...
I..
.SAFETY ANALYSES ASSUME THAT TWO OR MORE BYPASS
- VALVES ARE INOPERABLE PER SR 3.7.6.1 OR 3.7.6.2 N
D R
REFERENCE:
T.Sa 3.2.3 and 3.7.6 S
a USEDINDETERMININGFDLRX
.. acaaaAia i
a I
a a
a ia a*
a a
i (25,0.42) - -
a30,0.4a a...
r-T(D 20 30 40 i
,0 60 70 8o 90 100 Core Power (% RATED)
-0 C-mD Z
POWqR DEPENDENT L-GR LfMIT MULTIPLIER 1
1o 00 0
MAIN TURBINE BYPASS INOPERABLE 0
ATRIUM M-10 FUEL 0
FIGURE 6.2.5
PPL Rev. 7 PL-NF-07-002 Rev. 1 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 03/30/2007
PPL Rev. 7 PL-NF-07-002 Rev. 1 Page 30 of 47 Table 7-2-1 RBM Setpoints Allowable Nominal Trip Function Value(1' Setpoint Low Power Range Setpoint 28.0 24.9 Intermediate Power Range Setpoint 63.0 61.0 High Power Range Setpoint 83.0 81.0 Low Power Range - Upscale 123.4 123.0 Intermediate Power Range - Upscale 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
(% of Rated) "
MCPR (z,3)
_>28 and < 90
< 1-78
>90
< 1.71 (2)
Applicable to Main Turbine Bypass Operable and Inoperable and EOC-RPT Operable and Inoperable.
(3)
Applicable to both Two Loop and Single Loop Operation.
SUSQUEHANNA UNIT 2 TRMI3.2,-3].
EFFECTIVE DA!E 03/30/2007
PPL Rev. 7 PL-NF-07-002 Rev. 1 Page 31 of 47 8.0 RECIRCULATION LOOPS - SINGLE LOOP OPERATION 8.1 Technical Specification Reference Technical Specification 3.2.1, 3.2.2, 3.2.3, 3.3.4.1, 3.4-1, and 3.7.6 8.2 Description APLHGR The APLHGR limit for ATRIUM'rM-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 Limit The MCPR limit is specified as a function of core power, core flow, and plant equipment operability status. The MCPR limits for all fuel types (ATRIUM TM-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 BOGC to EOC Figure 8.2-3: Power-Dependent MCPR value determined from BOC to EOC b)
Main Turbine Bypass Inoperable / EOC-RPT Operable Figure 8.2-4: Flow-Dependent MCPR value determined from BOC to 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 SUMIJEHANNA UNIT 2 T-RM/3.2-32 EFFECTIVE DATE 03/30/2007
PPL Rev. 7 PL-NF-07-002 Rev. 1 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 TRMi3.2-.33 EFFECTIVE DATE 03/30/2007
o
-T" M
t-4
-\\)
16 14 12
.E N~ o210
.tz Cu ca<8 I..
(-U.
SSES UNIT 2 CYCLE 14
- a.
REEEC T.S.3.4 11 an3.1 a~
~ ~~~
a s
as a
s
~
a I IN DETERMINING a
aRA 0.,00a 5
a,1 a.0:
1 a
REFERENCE T.S. 3.41.and 3.2.
I' i,
~USE:D IN DETERMINING MAPRAT t
a a
a a1a a
r a
l u
I dl a
araa a
,a.,
a a
a a
a aa
,.a a
a a
a-!
i a a*
a, a
a a
a 1
a Jia a
a a
a a
a r
a~
a
~
a a
~
ah h
S a
i 67000,5.6 aa.
a a
a
.1 6005
-,ri
-H-m
ýi LI)
-:4 6
-U
-U3 I--
(D z T
0 a*
.I)
C:
'--4 I'O)
I I
10000 20000 30000 40000 50000 60000 70000 Average Planar Exposure (MWDIMTU)
AVERAGE PLANAR LINEAR HEAT GINERATION RATE LIMIT VERSUS AVERAGE PLANAR EXPOSURE SINGLE LOOP OPERATION ATRIUMT"-10 FUEL FIGURE 8.2-1
PPL Rev. 7 PL-NF-07-002 Rev. I Page 34 of 47 EOC-RPT and Main Turbine Bypass Operable SUSQUEHANNA UNIT 2 TRM/3.2-35 EFFECTIVE. DATE 03/30/2007
0 (f~
(~l m
-4 SSES UNIT 2 CYCLE 14 2.3 I
I I
I I
tLEGEND CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME 2.2
-(30,2.18)
I IN) 2.1 E
2.0 0
ot, a.
(50,2.08) 4
+ -.---------.-
'Y ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 USED IN DETERMINING MFLCPR
.i I....
I* "
I I
]
I
'-.,T 1.9 m
--4 1.8 1.7
REFERENCE:
___" 3.4.1 and S
REFERENCE:
T S 3.4.1 and 3.2.2I L
30 40 50 60 70 Total Core Flow (MLB/HR) so 90 100 110 MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW EOC-RPT AND MAIN TURBINE BYPASS OPERABLE SINGLE LOOP OPERATION (BOC to EOC)
FIGURE 8.2-2
~0 4-I~
4
- TJ "U
-T 6
0 0
(A rn
-1 SSES UNIT 2 CYCLE 14 4.1 3.9 3.7 3.5
-H 3.3 Em
-J 3.1
' 2,9 0
2.7 2.5 rn rn
~11 m
C-,
nfl
-H m
~-1 2.3 2.1 1.9 1.7 -L-20 50 30 40 60 70 80 90 100 Core Power (% RATED)
MCPR OPERATING LIMIT VERSUS CORE POWER EOC.RPTJAND MAIN TURBINE BYPASS OPERABLE SINGLE LOOP OPERATION (BOC to EOC)
FIGURE 8.2-3
-4 I-i--
C-4 C
0N,
PPL Rev. 7 PL-NF-07-002 Rev. 1 Page 37 of 47 Main Turbine Bypass Inoperable I EOC-RPT
-Operable SUSQUEHANNA UNIT 2 TRM/3.2--38 EFFECTIVE DATE 03/30/2007
(A rrl N)
-1 N)
SSES UNIT 2 CYCLE 14 2.6 2.5 2,4 2.3
_E 2 2.2 0
C.
~2.1
-U
-4 rn
-fl ni C-)
-H
-H m
(A (A
N) 2.0 1.9 30 40 50 60 70 80 90 100 Total Core Flow (MLBIHR)
MCPR OPEFATING LIMIT VERSUS TOTAL CORE FLOW MAIN TURBINE BYPASS INOPERABLE ! EOC-RPT OPERABLE SINGLE LOOP OPERATION (BOC to EOC)
FIGURE 8.2-4 110 (0 x~
0~
0
-4x zTn CD
W~
I ELI t~
~
I~E
~
I
- bb-..5 UINI I Z L;YJLI
- : 14 4.3 (25,4.25)
M LEGEND 41~
CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM 3INSERTION TIME 3.9 (30,3.74)
ICURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME 3,7 E 3.5 SAFETY ANALYSES ASSUME THAT TWO OR MORE BYPASS I VALVES ARE INOPERABLE PER SR 3.7.6.1 OR 3.7.6.2 E 3.3
-73 USED IN DETERMINING MFLCPR
.- 3.1 0X C3 02.9 02.7 2.5 n\\
2.3
-(40,2.32)
--IA
_(100,2 2.1
_.4,D,
("
]
72.9,2.03) 1.9
REFERENCE:
T.S. 3.4.1 3.7.6, and 3.2.2 1.7 20 30 40 50 60 70 80 90 100 Core Power (% RATED)
MCPR OFERATING LIMIT VERSUS CORE POWER MAIN TURBINE BYPASS INOPERABLE I EOC-RPT OPERABLE o
SINGLE LOOP OPERATION (BOC to EOC)
C0 FIGURE 8.2-5
)
PPL Rev. 7 PL-NF-07-002 Rev-1 Page 40 of 47 EOC-RPT Inoperable I Main Turbine Bypass Operable SUSQUEHANNA UNIT 2 TRM/3.2-41 EFFECTIVE DATE 03/30/2007
4Dr SSES UNIT 2 CYCLE 14 2.3 i
I I
LEGEND CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME 2.2 I
I
--4 2.1 2,0 E 2.0 0.
0:
IL0 1.9 (50,2.08)
SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES;
-i ARE OPERABLE PER SR 3,7.6.1 AND 3.7.6.2 USED IN DETERMINING MFLCPR L..
"V F-'
m
-ii
-T-m CD, C) 1.8
=*
(108,1.81)
-- --.B --
-A
REFERENCE:
T.S. 3.4.1, 3.3.4.1, and 3.2.22
!d, 3 2I 1.7 3(
40 5o I
70 80
.Total Core Flow (MLBIHR) 90 100 110
- u MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW EOC-RPT INOPERABLE / MAIN TURBINE BYPASS OPERABLE SINGLE LOOP OPERATION (BOC to EOC)
FIGURE 8.2-6
-.,4 z
-4 0to3
m SSES UNIT 2 CYCLE 14 4.1 3.9 3.7 3.5 3.3 Co
(~0 3.1 0
~2.7
'D r-m rn m
C-)
-9 m
rn C)
Co Co C)
N)
C) 2,5 2.3 2.1 1.9 1.7 20 30 40 s0 60 70 80 90 Core Power (% RATED)
MCPR OPERATING LIMIT VERSUS CORE POWER EOC-RPT INOERABLE / MAIN TURBINE BYPASS OPERABLE SINGLE LOOP OPERATION (BOC to EOC)
FIGURE 8.2-7 100 Co<
0
-4 NJ
PPL Rev-7 PL-NF-07-002 Rev. 1 Page 43 of 47 9.0 POWER / FLOW MAP 9.1 Technical Specification Reference Technical Specification 3.3.1.1 9.2 Description Monitor reactor conditions to maintain THERMAL POWER / core flow outside of Stability Regions I and II of the Power/ Flow map, Figure 9.1.
If the OPRM Instrumentation is OPERABLE per TS 3.3.1.1, Region I of the Power / Flow map is considered an immediate exit region.
If the OPRM Instrumentation is inooerable 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 I"RM/3.2-44 EFFECTIVE DATE 03/30/2007
PPL Rev. 7 PL-NF-07-002 Rev. 1 Page 44 of 47 120:
UNIT 2120 AP MId S.t.Mn POWVER I FLOW MAP T*
Purpose 110 initial I Date:
Trip SIoint IFORM PeOFIERABE 00MEDIATE ar/z",,*("7,
- IF OPR 2a~AE~MDM I1OSRMLA00200 Budr 0
EXIT lAW ON.2M04O2 L
A IjwoIeATELY F)T IAW Ol.-7O0j_2 90 r
I J, t I 1 90
-As,*hlrd In Ar1*Jmnl G toI IF ABOVE MLJ.LA BMNIDAR.T.
-1 J RodLine L IMMMDIAT'L'Y FXIT LAW ON-22AI,002 I
ii
-70 7a 7
i 7 r I"'
Si"t i" "
i""
11.C
-, 1 Tr -,
=
L -g u
9.1 k---
A J
1.L7 0-L 0
t I i
I I
t 44
-- (
SfUit 2 C ycl
-14 r
Fo U-I-N 2
1-1 E
C D-R33
/2 0,-
r
'1 '-t-1
'1 z'
.. t-I._
,L Jt
,l....
1,.
E1
-r.I r
n i
i 1 '-
50 J--*-*,**
J *-
Approx
,5 J'" "
% r 7 "" '
i
'-*""d 1"' "
1 60 1 -70 1,_80
,9D
,I 0,
Line 4
30 j_ AptWr*
Cmu;*io 30 30 P,
J-.:
-1, J-1-If
>2.25% and <40%
30%S
-i hermnal power, comply with LCO 1.2.2 MCPR 20 20
- i'3
'3N I "t "I" 0
10 20 30 40 so 60 70 so so 100 Ila Total Core Flow (Mlbm/hr)
(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 03/30/2007
PPL Rev. 7 PL-NF-07-002 Rev, 1 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 Np
=
16 F
=
60 Mlbm / hr SUSQUEHANNA UNIT 2 TRM/3. 2.- 4 6 EFFECTIVE DATE 03/30/2007
PPL Rev. 7 PL-NF-07-002 Rev. 1 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 I and 2, "RODEX2 Fuel Rod Thermal-Mechanical Response Evaluation Model." Exxon Nuclear Company, March 1984.
- 2. EMF-2361(P)(A), Revision 0, "EXEM BWR-2000 ECCS Evaluation Model,"
Framatome ANP, May 2001.
- 3. EMF-2292(PXA), Revision 0, "ATRIUM'M.-10: Appendix K Spray Heat Transfer Coefficients," Siemens Power Corporation, September 2000.
- 4. XN-NF-84-105(P)(A), Volume 1 and Volume I Supplements 1 and 2, "XCOBRA-T: A Computer Code for BWR Transient Thermal-Hydraulic Core Analysis," Exxon Nuclear Company, February 1987.
- 5.
XN-NF-80-19(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(PXA), Volumes 2, 2A. 2B, and 2C "Exxon Nuclear Methodology for Boiling Water Reactors: EXEM BWR ECGS Evaluation Model," Exxon Nuclear Compsany, September 1982.
-7. XN-NF-80-19(PXA), 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-80-1 9(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 03/30/2007
PPL Rev. 7 PL-NF-07-002 Rev. 1 Page 47 of 47
- 12. ANF-89-98(P)(A) Revision I and Supplement 1, "Generic Mechanical Design Criteria for BWR Fuel Designs," Advanced Nuclear Fuels Corporation, May 1995.
- 13. EMF-2209(P)(A), Revision 2, "SPCB Critical Power Correlation," Framatome ANP, September 2003.
- 14. Caldon, Inc., "TOPICAL REPORT: Improving Thermal Power Accuracy and Plant Safety While Increasing Operating Power Level Using the LEFM"T' System," Engineering Report - 80P, March 1997.
- 15. Caldon, Inc., "Supplement to Topical Report ER-80P: Basis for a Power Uprate with the LEFM' or LEFM CheckPlusTM System," Revision 0, Engineering Report ER-160P, 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 Ap~plications," 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 03/30/2007
Suppression Pool Alarm Instrumentation PPL Rev. 1 B 3.6.3 B 3.6.3 Suppression Pool Alarm Instrumentation BASES TRO The function of the Suppression Pool Instrumentation is to provide continuous monitoring of the suppression pool temperature and level. This monitoring function supplements the Operator observations and periodic Technical Specification Surveillance Requirements which require observation of the monitored parameters.
The suppression pool alarm instrumentation is designed to warn the control room operator that a limit has been reached and some compensatory action may be required. The setpoints are chosen to be consistent with the limits defined in the Technical Specifications.
Each channel of suppression pool narrow range level instrumentation consists of a transmitter, indicator and alarm circuit. This TRO only requires the alarm function to be maintained. The indicator is not required to support this function but can be used to support the performance of TRS 3.6.3.1, "Channel Check," and can be used to perform Surveillance Requirement (SR) 3.6.2.2.1.
Each channel of suppression pool temperature consists of 8 temperature detectors, as described in the Basis for SR 3.6.2.1.1, associated indicators and alarm circuits.
The four alarm functions, as specified in Table 3.6.3-1, are displayed by monitors located both on the-electronic unit (TX-25751 for Div. I, TX-25752 for Div 11) and on the main control board (TIAH-25751 for Div. I, TIAH-25752 for Div. II). The alarm displays on both the electronic unit and main control board must be surveilled.
Annunciators, tripped by the-plant computer at a calculated.bulk pool temprature of 880F and by the electronic unit at or below the 1050F, I 10°F and 120°F limits, enhance the operator's monitoring capability but are not required to be surveilled.
This TRO only requires the alarm function to be maintained. The indicators are not required to support this function but can be used to support the performance of TRS 3.6.3.1, "Channel Check" and can be used to perform SR 3.6.2.1.1.
ACTIONS The Actions are defined to ensure proper corrective measures are taken in response to the inoperable components.
(continued)
SUSQUEHANNA - UNIT 2 TRM / B 3.6-4 EFFECTIVE DATE 03/27/2007
Suppression Pool Alarm Instrumentation PPL Rev. 1 B 3.6.3 B 3.6.3 Suppression Pool Alarm Instrumentation BASES (continued)
TRS The TRSs are defined to be performed at the specified Frequency to ensure that the Suppression Pool Alarm Instrumentation Function is maintained OPERABLE.
TRS 3.6.3.1 Performance of the CHANNEL CHECK ensures that a gross failure of instrumentation has not occurred. A CHANNEL CHECK is normally a comparison of the parameter indicated on one channel against a similar parameter on other channels. It is based on the assumption that instrument channels monitoring the same parameter should read approximately the same value. Significant deviations between instrument channels could be an indication of excessive instrument drift in one of the channels or something even more serious. A CHANNEL CHECK will detect gross channel failure; thus, it is key to verifying the instrumentation continues to operate properly between each CHANNEL CALIBRATION.
Agreement criteria which are determined by the plant staff based on an investigation of a combination of the channel instrument uncertainties, may be used to support this parameter-comparison and include indication and readability. If a channel is outside the criteria, it may be an indication that the instrument has drifted outside its limit and does not necessarily, indicate the.
channel is Inoperable.-.
TRS 3.6.3.2 A CHANNEL FUNCTIONAL TEST is performed on each required channel to ensure that the entire channel will perform the intended function.
The Frequency of 92 days is based on the reliability analysis of Reference 1.
REFERENCES (1)
EWR 365129, Evaluation of extending SPOTMOS alarm functional test from 31 days to 92 days.
SUSQUEHANNA - UNIT 2 TRM / B 3.6-5 EFFECTIVE DATE 04/04/2007