ML043070443
| ML043070443 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 10/28/2004 |
| From: | Susquehanna |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| Download: ML043070443 (62) | |
Text
Oct. 28, 2004 Page 1 of 1 MANUAL HARD COPY DISTRIBUTION DOCUMENT TRANSMITTAL 2004-44057 USER INFORMATION 0 Na ERLACH*
SE M EMPL#:028401 CA#:0363 Address:
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TO:
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TRM2 -
TECHNICAL REQUIREMENTS MANUAL UNIT 2 REMOVE MANUAL TABLE OF CONTENTS DATE: 09/17/2004
)D MANUAL TABLE OF CONTENTS DATE: 10/27/2004
\\VATEGORY: DOCUMENTS TYPE: TRM2 ID:
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f SSES MANUAL Manual Name:
TRM2 manual
Title:
TECHNICAL REQUIREMENTS MANUAL UNIT 2 Table Of Contents Issue Date:
10/27/2004 Procedure Name Rev Issue Date Change ID change Number TRM2 N/A 08/01/2003
Title:
TECHNICAL REQUIREMENTS MANUAL UNIT 2 (07/28/2003)
TEXT LOES
Title:
TEXT TOC
Title:
TEXT 1.1
Title:
7 LIST OF EFFECTIVE SECTIONS 2
TABLE OF CONTENTS 10/27/2004 01/27/2004 0
11/19/2002 USE AND APPLICATION DEFINITIONS TEXT 2.1 0
11/19V2002
Title:
PLANT PROGRAMS AND SETPOINTS PLANT '`PROGRAMS TEXT 2.2 10/22/2003
Title:
PLANT PROGRAMS AND SETPOINTS INSTRUMENT TRIP SETPOINT TABLE TEXT 3.0 11/19/2002
Title:
APPLICABILITY/ ECHNICAL'\\REQUIREMENT FOR OPERATION (TRO) APPLICABILITY TEXT 3.1.1 67 t 0
11/19/2002
Title:
REACTIVITY CONTROL SYSTEMS ANTICIPATED TRANSIENT WITHOUT SCRAM ALTERNATE ROD INJECTION (ATWS-ARI) INSTRUMENTATION TEXT 4.3 0
09/27/2003
Title:
ADMINISTRATIVE CONTROLS SAFETY LIMIT VIOLATION TEXT 3.1.2 0
11/19/2002
Title:
REACTIVITY CONTROL SYSTEMS CONTROL ROD DRIVE (CRD) HOUSING SUPPORT TEXT 3.1.3 0
11/19/2002
Title:
REACTIVITY CONTROL SYSTEMS CONTROL -ROD BLOCK INSTRUMENTATION Page 1 of 14 Report Date: 10/28/04 Page 1
, of 14 Report Date: 10/28/04
SSES MANUAL Manual Name: TRM2 Manual
Title:
TECHNICAL REQUIREMENTS MANUAL UNIT 2
-I " '
TEXT 3.1.4 0
11/19/2002
Title:
REACTIVITY CONTROL SYSTEMS CONTROL ROD SCRAM ACCUMULATORS INSTRUMENTATION AND CHECK VALVE TEXT 3.2.1 2
10/27/2004
Title:
CORE OPERATING LIMITS CORE OPERATING LIMITS REPORT (COLR)
TEXT 3.3.1 0
11/19/2002
Title:
INSTRUMENTATION RADIATION MONITORING INSTRUMENTATION TEXT 3.3.2 0
11/19/2002
Title:
INSTRUMENTATION SEISMIC MONITORING INSTRUMENTATION TEXT 3.3.3
Title:
INSTRUMENTATION TEXT 3.3.4
Title:
INSTRUMENTATION TEXT 3.3.5
Title:
INSTRUMENTATION TEXT 3.3.6
Title:
INSTRUMENTATION TEXT 3.3.7
Title:
INSTRUMENTATION TEXT 3.3.8 0
11/19/2002 METEOROLOGICAL MONITORING INSTRUMENTATION 0.
11/19/2002 TRM POST-ACCIDENT MONITORING INSTRUMENTATION 0
11/19/2002 THIS PAGE INTENTIONALLY LEFT BLANK 1
10/22/2003 TRM ISOLATION ACTUATION INSTRUMENTATION 0
11/19/2002 MAIN TURBINE OVERSPEED PROTECTION SYSTEM 1
10/22/2003
Title:
INSTRUMENTATION TRM RPS INSTRUMENTATION TEXT 3.3.9 0
11/19/2002
Title:
INSTRUMENTATION LPRM UPSCALE ALARM INSTRUMENTATION TEXT 3.3.10 0
11/19/2002
Title:
INSTRUMENTATION REACTOR RECIRCULATION PUMP MG SET STOPS Report Date: 10/28/04 Page 2 of 14 Report Date: 10/28/04 Page 2 of 14
SSES MANUAL
, Manual Name:
TRM2 Manual
Title:
TECHNICAL REQUIREMENTS MANUAL UNIT 2 TEXT 3.3.11
Title:
INSTRUMENTATION 1
10/22/2003' MVP ISOLATION INSTRUMENTATION TEXT 3.4.1
Title:
REACTOR 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 REACTOR COOLANT SYSTEM CHEMISTRY 0
11/19/2002 COOLANT SYSTEM STRUCTURAL:INTEGRITY 0
11/19/2002 COOLANT SYSTEM REACTOR COOLANT SYSTEM (RCS) 0 11/19/2002 COOLANT SYSTEM REACTOR RECIRCULATION FLOW AND ROD LINE LIMIT 0
11/18/2002 COOLANT SYSTEM REACTOR VESSEL MATERIALS 0
11/19/2002
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 Page 3 of 14 Report Date: 10/28/04 Page 3 of 14 Report Date: 10/28/04
SSES MANUAL Manual Name:
TRM2 Manual
Title:
TECHNICAL REQUIREMENTS MANUAL UNIT 2 TEXT 3.6.4 0
11/19/2002
Title:
CONTAINMENT PRIMARY CONTAINMENT CLOSED SYSTEM BOUNDARIES TEXT 3.7.1
Title:
PLANT TEXT 3.7.2
Title:
PLANT TEXT 3.7.3.1
Title:
PLANT TEXT 3.7.3.2
Title:
PLANT 0
11/19/2002 SYSTEMS EMERGENCY SERVICE WATER SYSTEM (ESW)
SHUTDOWN 0
11/19/2002 SYSTEMS ULTIMATE HEAT SINK (UHS)
AND GROUND WATER LEVEL 0
11/19/2002 SYSTEMS FIRE SUPPRESSION WATER SUPPLY SYSTEM 0
11/19/2002 SYSTEMS SPRAY AND SPRINKLER SYSTEMS TEXT 3.7.3.3.
Title:
PLANT 0
SYSTEMS C02 SYSTEMS 11/19/2002 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 0
11/19/2002 SYSTEMS HALON SYSTEMS 0
11/19/2002 SYSTEMS FIRE HOSE STATIONS 0
11/19/2002 SYSTEMS YARD FIRE HYDRANTS AND HYDRANT HOSE HOUSES 0
11/19/2002 SYSTEMS FIRE RATED ASSEMBLIES 1
01/12/2004 SYSTEMS FIRE DETECTION INSTRUMENTATION TEXT 3.7.4
Title:
PLANT SYSTEMS 0
11/19/2002 SOLID RADWASTE SYSTEM Page 4 of 14 Report Date: 10/28/04 Page 4 of 14 Report Date: 10/28/04
SSES MANUAL manual Name:
TRM2 Manual
Title:
TECHNICAL REQUIREMENTS MANUAL UNIT 2 TEXT 3.7.5.1
Title:
PLANT TEXT 3.7.5.2
Title:
PLANT TEXT 3.7.5.3
Title:
PLANT TEXT 3.7.6
Title:
PLANT TEXT 3.7.7 0
11/19/2002 SYSTEMS MAIN CONDENSER OFFGAS HYDROGEN MONITOR 0
11/19/2002 SYSTEMS MAIN CONDENSER OFFGAS EXPLOSIVE GAS MIXTURE 0
11/19/2002 SYSTEMS LIQUID HOLDUP TANKS 0
11/19/2002 SYSTEMS ESSW PUMPHOUSE VENTILATION 0
11/19/2002
Title:
PLANT SYSTEMS MAIN CONDENSER'OFFGAS PRETREATMENT LOGARITHMIC RADIATION MONITORING INSTRUMENTATION TEXT 3.7.8 0
11/19/2002
\\_>
Title:
PLANT SYSTEMS SNUBBERS TEXT 3.7.9 0
11/19/2002
Title:
PLANT SYSTEMS CONTROL STRUCTURE HVAC-TEXT 3.7.10 0
11/19/2002
Title:
PLANT SYSTEMS SPENT FUEL STORAGE POOLS (SFSPS)
TEXT 3.8.1 0
11/19/2002
Title:
ELECTRICAL POWER PRIMARY CONTAINMENT PENETRATION CONDUCTOR OVERCURRENT PROTECTIVE DEVICES TEXT 3.8.2.1
Title:
ELECTRICAL CONTINUOUS TEXT 3.8.2.2
Title:
ELECTRICAL AUTOMATIC 0
11/19/2002 POWER MOTOR OPERATED VALVES (MOV)
THERMAL OVERLOAD PROTECTION -
1 09/17/2004 POWER MOTOR OPERATED VALVES (MOV)
THERMAL OVERLOAD PROTECTION -
TEXT 3.8.3 0
11/19/2002
Title:
ELECTRICAL POWER DIESEL GENERATOR (DG) MAINTENANCE ACTIVITIES Page 5 of 14 Report Date: 10/28/04 Page 5 of 14 Report Date: 10/28/04
SSES MANUAL Manual Name:
TRM2 Manual
Title:
TECHNICAL REQUIREMENTS MANUAL UNIT 2 U-J TEXT 3.8.4 0
11/19/2002
Title:
ELECTRICAL POWER 24 VDC ELECTRICAL SUBSYSTEM TEXT 3.8.5 0
11/19/2002
Title:
ELECTRICAL POWER DEGRADED VOLTAGE PROTECTION TEXT 3.8.6 0
11/19/2002
Title:
ELECTRICAL POWER EMERGENCY SWITCHGEAR ROOM COOLING 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 0
11/19/2002
Title:
MISCELLANEOUS SEALED SOURCE CONTAMINATION TEXT 3.10.2 0
11/19/2002
Title:
MISCELLANEOUS SHUTDOWN MARGIN TEST RPS INSTRUMENTATION TEXT 3.10.3 0
11/19/2002
Title:
MISCELLANEOUS INDEPENDENT SPENT FUEL STORAGE INSTALLATION (ISFSI)
TEXT 3.10.4 0
11/19/2002
Title:
MISCELLANEOUS LEADING EDGE FLOW METER (LEFM)
TEXT 3.11.1.1 0
11/19/2002
Title:
RADIOACTIVE EFFLUENTS LIQUID EFFLUENTS CONCENTRATION TEXT 3.11.1.2 0
11/19/2002
Title:
RADIOACTIVE EFFLUENTS LIQUID EFFLUENTS DOSE Page 6 of 14 Report Date: 10/28/04 Page 6 of 14 Report Date: 10/28/04
SSES 'MANUAL Manual Name:
TRM2 Manual
Title:
TECHNICAL REQUIREMENTS MANUAL UNIT'2 TEXT 3.11.1.3
Title:
RADIOACTIVE TEXT 3.11.1.4
Title:
RADIOACTIVE TEXT 3.11.4.2
Title:
RADIOACTIVE TEXT 3.11.4.3
Title:
RADIOACTIVE EFFLUENTS EFFLUENTS EFFLUENTS EFFLUENTS 0
11/19/2002 LIQUID WASTE TREATMENT SYSTEM O
11/19/2002, LIQUID RADWASTE EFFLUENT MONITORING INSTRUMENTATION 0
11/19/2002 LAND USE CENSUS 0
11/19/2002 INTERLABORATORY COMPARISON PROGRAM TEXT 3.12.1
Title:
LOADS CONTROL PROGRAM TEXT 3.12.2
'_i
Title:
LOADS CONTROL PROGRAM
- 0.
11/19/2002' CRANE TRAVEL-SPENT FUEL STORAGE'POOL 0
11/19/2002 HEAVY LOADS REQUIREMENTS TEXT 3.12.3 0
11/19/2002
Title:
LOADS CONTROL PROGRAM LIGHT LOADS REQUIREMENTS TEXT B3.0 0
11/19/2002
Title:
APPLICABILITY BASES TECHNICAL REQUIREMENT FOR OPERATION (TRO)
APPLICABILITY -
TEXT B3.1.1 0
11/19/2002
Title:
REACTIVITY CONTROL SYSTEM BASES ANTICIPATED ROD INJECTION (ATWS-ARI) INSTRUMENTATION TEXT B3.1.2 0
11/19/2002-'
Title:
REACTIVITY CONTROL SYSTEM BASES CONTROL'ROD TEXT B3.1.3 0
11/19/2002
Title:
REACTIVITY CONTROL.SYSTEM BASES CONTROL'ROD TEXT B3.1.4 0
11/19/2002
Title:
REACTIVITY CONTROL SYSTEM BASES CONTROL ROD AND CHECK VALVE TRANSIENT WITHOUT SCRAM ALTERNATE DRIVE (CRD)
HOUSING SUPPORT BLOCK INSTRUMENTATION' SCRAM ACCUMULATORS INSTRUMENTATION Page 7 of 14 Report Date: 10/28/04 Page 7 of 14 Report Date: 10/28/04
rn SSES MANUAL Manual Name: TRM2 Manual
Title:
TECHNICAL REQUIREMENTS MANUAL UNIT 2
.i j
TEXT B3.2.1
Title:
CORE OPERATING L TEXT B3.3.1
Title:
INSTRUMENTATION TEXT B3.3.2
Title:
INSTRUMENTATION TEXT B3.3.3
Title:
INSTRUMENTATION 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 IMITS 0
11/19/2002 BASES CORE OPERATING LIMITS REPORT (COLR) 0 11/19/2002 BASES RADIATION MONITORING INSTRUMENTATION 0
11/19/2002 BASES SEISMIC MONITORING INSTRUMENTATION 0
11/19/2002 BASES METEOROLOGICAL MONITORING INSTRUMENTATION 0
11/19/2002 BASES TRM POST ACCIDENT MONITORING (PAM) INSTRUMENTATION 0
11/19/2002 BASES THIS PAGE INTENTIONALLY LEFT BLANK 1
10/22/2003 BASES TRM ISOLATION ACTUATION INSTRUMENTATION 0
11/19/2002 BASES MAIN TURBINE OVERSPEED PROTECTION SYSTEM 1
10/22/2003 BASES TRM RPS INSTRUMENTATION 0
11/19/2002 BASES LPRM UPSCALE ALARM INSTRUMENTATION 0
11/19/2002 BASES REACTOR RECIRCULATION PUMP MG SET STOPS 1
10/22/2003 BASES MVP ISOLATION INSTRUMENTATION PageB of 14 Report Date: 10/28/04 Page 8.of 14 Report Date: 10/28/04
SSES MANUAL Manual Name:
TRM2 Manual
Title:
TECHNICAL REQUIREMENTS MANUAL UNIT 2 TEXT B3.4.1
Title:
REACTOR TEXT B3.4.2
Title:
REACTOR TEXT B3.4.3
Title:
REACTOR TEXT B3.4.4
Title:
REACTOR TEXT B3.4.5
Title:
REACTOR 0
11/19/2002 COOLANT SYSTEM BASES REACTOR COOLANT SYSTEM CHEMISTRY 0
11/19/2002 COOLANT SYSTEM BASES STRUCTURAL INTEGRITY 0
11/19/2002 COOLANT SYSTEM BASES HIGH/LOW PRESSURE INTERFACE LEAKAGE MONITOR 0
11/19/2002 COOLANT SYSTEM BASES REACTOR RECIRCULATION FLOW AND ROD LINE LIMIT 0
11/19/2002 COOLANT SYSTEM BASES REACTOR VESSEL MATERIALS 0
11)19/2002 TEXT B3.5.1.
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 0
11/19/2002
Title:
CONTAINMENT BASES PRIMARY CONTAINMENT CLOSED SYSTEM BOUNDARIES Page 9 of 14 Report Date: 10/28/04 Page 9 of 14 Report Date: 10/28/04
SSES MANUAL Manual Name: TRM2 Manual
Title:
TECHNICAL REQUIREMENTS MANUAL UNIT 2 TEXT B3.7.1
Title:
PLANT 0
11/19/2002 EMERGENCY SERVICE WATER SYSTEM (SHUTDOWN)
SYSTEMS BASES TEXT B3.7.2
Title:
PLANT 0
11/19/2002 SYSTEMS BASES ULTIMATE HEAT SINK (UHS)
GROUND WATER LEVEL TEXT B3.7.3.1
Title:
PLANT TEXT B3.7.3.2
Title:
PLANT TEXT B3.7.3.3
Title:
PLANT TEXT B3.7.3.4
Title:
PLANT TEXT B3.7.3.5
Title:
PLANT SYSTEMS BASES SYSTEMS BASES SYSTEMS BASES SYSTEMS BASES SYSTEMS BASES 0
11/19/2002 FIRE SUPPRESSION WATER SUPPLY SYSTEM 0
11/19/2002 SPRAY AND SPRINKLER SYSTEMS
- 0.
11/19/2002 C02 SYSTEMS 0
11/19/2002 HALON SYSTEMS 0
11/19/2002 FIRE HOSE STATIONS TEXT B3.7.3.6
Title:
PLANT 11/19/2002 FIRE HYDRANTS AND SYSTEMS BASES YARD HYDRANT HOSE HOUSES TEXT B3.7.3.7
Title:
PLANT TEXT B3.7.3.8
Title:
PLANT 11/19/2002 RATED ASSEMBLIES SYSTEMS BASES FIRE 1
FIRE 01/12/2004 DETECTION INSTRUMENTATION SYSTEMS BASES TEXT B3.7.4
Title:
PLANT 0
11/19/2002 SYSTEMS BASES SOLID RADWASTE SYSTEM TEXT B3.7.5.1
Title:
PLANT SYSTEMS 0
11/19/2002 BASES MAIN CONDENSER OFFGAS HYDROGEN MONITOR Page 10 of 14 Report Date: 10/28/04 Page 10 of 14 Report Date: 10/28/04
SSES MANUAL Manual Name:
TRM2 Manual
Title:
TECHNICAL REQUIREMENTS MANUAL UNIT 2 TEXT B3.7.5.2
Title:
PLANT SYSTEMS TEXT B3.7.5.3
Title:
PLANT SYSTEMS TEXT B3.7.6
Title:
PLANT SYSTEMS 0
11/19/2002 BASES MAIN CONDENSER'OFFGAS EXPLOSIVE GAS MIXTURE 0
11/19/2002 BASES LIQUID HOLDUP TANKS '
0 11/19/2002 BASES ESSW PUMPHOUSE VENTILATION TEXT B3.7.7 0
11/19/2002
Title:
PLANT SYSTEMS BASES MAIN CONDENSER OFFGAS PRETREATMENT LOGARITHMIC RADIATION MONITORING INSTRUMENTATION TEXT B3.7.8 0
11/19/2002
Title:
PLANT SYSTEMS BASES SNUBBERS TEXT B3.7.9 0
11/19/2002 j
Title:
PLANT SYSTEMS BASES CONTROL STRUCTURE HVAC TEXT B3.7.10 0
11/19/2002,
Title:
PLANT SYSTEMS BASES SPENT FUEL STORAGE POOLS TEXT B3.8.1
Title:
ELECTRICAL PROTECTIVE 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 0
11/19/2002 POWER BASES PRIMARY CONTAINMENT PENETRATION CONDUCTOR OVERCURRENT DEVICES 0
11/19/2002, POWER BASES MOTOR OPERATED VALVES (MOV) THERMAL OVERLOAD PROTECTION -
1 09/17/2004 POWER BASES MOTOR OPERATED VALVES (MOV)YTHERMAL OVERLOAD PROTECTION -
0 11/19/2002 POWER BASES DIESEL GENERATOR'-(DG) -MAINTENANCE'ACTIVITIES 0
11/19/2002' POWER BASES 24 VDC ELECTRICAL POWER SUBSYSTEM Page 11 of 14 Report Date: 10/28/04 Page 11 of 14 Report Date: 10/28/04
- -U SSES MANUAL Manual Name:
TRM2 Manual
Title:
TECHNICAL REQUIREMENTS MANUAL UNIT 2 TEXT B3.8.5 0
11/19/2002
Title:
ELECTRICAL POWER BASES DEGRADED VOLTAGE PROTECTION TEXT B3.8.6 0
11/19/2002
Title:
ELECTRICAL POWER BASES EMERGENCY SWITCHGEAR ROOM COOLING TEXT B3.9.1 0
11/19/2002
Title:
REFUELING OPERATIONS BASES DECAY TIME TEXT B3.9.2 0
11/19/2002
Title:
REFUELING OPERATIONS BASES COMMUNICATIONS TEXT B3.9.3 0
11/19/2002
Title:
REFUELING OPERATIONS BASES REFUELING PLATFORM TEXT B3.10.1 0
11/19/2002
Title:
MISCELLANEOUS BASES SEALED SOURCE CONTAMINATION TEXT B3.10.2 0
11/19/2002
Title:
MISCELLANEOUS BASES SHUTDOWN MARGIN TEST RPS INSTRUMENTATION TEXT B3.10.3 0
11/19/2002
Title:
MISCELLANEOUS BASESINDEPENDENT SPENT FUEL STORAGE INSTALLATION (ISFSI)
TEXT B3.10.4 0
11/19/2002
Title:
MISCELLANEOUS BASES LEADING EDGE FLOW METER (LEFM)
TEXT B3.11.1.1 0
11/19/2002
Title:
RADIOACTIVE EFFLUENTS BASES LIQUID EFFLUENTS CONCENTRATION TEXT B3.11.1.2 0
11/19/2002
Title:
RADIOACTIVE EFFLUENTS BASES LIQUID EFFLUENTS DOSE TEXT B3.11.1.3 0
11/19/2002
Title:
RADIOACTIVE EFFLUENTS BASES LIQUID WASTE TREATMENT SYSTEM Page 12 of 14 Report Date: 10/28/04
SSES, MANUAL I Manual Name:
TRM2 Manual
Title:
TECHNICAL REQUIREMENTS MANUAL UNIT 2 TEXT B3.11.1.4
Title:
RADIOACTIVE EFFLUENTS TEXT B3.11.1.5
Title:
RADIOACTIVE EFFLUENTS INSTRUMENTATION TEXT B3.11.2.1
Title:
RADIOACTIVE EFFLUENTS TEXT B3.11.2.2
Title:
RADIOACTIVE EFFLUENTS TEXT B3.11.2.3
Title:
RADIOACTIVE EFFLUENTS PARTICULATES FORM TEXT B3.11.2.4
<j
Title:
RADIOACTIVE EFFLUENTS TEXT B3.11.2.5
Title:
RADIOACTIVE EFFLUENTS TEXT B3.11.2.6
Title:
RADIOACTIVE EFFLUENTS INSTRUMENTATION TEXT B3.11.3
Title:
RADIOACTIVE EFFLUENTS TEXT B3.11.4.1
Title:
RADIOACTIVE EFFLUENTS TEXT B3.11.4.2
Title:
RADIOACTIVE EFFLUENTS TEXT B3.11.4.3
Title:
RADIOACTIVE EFFLUENTS 0
11/19/2002 BASES LIQUID RADWASTE EFFLUENT MONITORING INSTRUMENTATION 0
11/19/2002 BASES RADIOACTIVE LIQUID PROCESS MONITORING 0
11/19/2002 BASES DOSE RATE 0
11/19/2002 BASES DOSE -
NOBLE GASES 0
11/19/2002 BASES DOSE - IODINE, TRITIUM, AND RADIONUCLIDES IN 0
BASES 11/19/2002 GASEOUS RADWASTE TREATMENT SYSTEM :
2 10/27/2004 BASES VENTILATION EXHAUST TREATMENT SYSTEM 1
01/27/2004 BASES RADIOACTIVE GASEOUS EFFLUENT MONITORING LDCN 3614 0
11/19/2002 BASES TOTAL DOSE 0
11/19/2002 BASES MONITORING PROGRAM 0
11/19/2002 BASES LAND USE CENSUS 0
11/19/2002 BASES INTERLABORATORY COMPARISON PROGRAM Page 13.
of 14 Report Date: 10/28/04 Page 13.
of 14 Report Date: 10128/04
SSES MANUAL Manual Name:
TRM2 Manual
Title:
TECHNICAL REQUIREMENTS MANUAL UNIT 2 TEXT B3.12.1 0
11/19/2002
Title:
LOADS CONTROL PROGRAM 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 TEXT 3.11.2.1 1
01/27/2004
Title:
RADIOACTIVE EFFLUENTS DOSE RATE TEXT 3.11.2.6 1
01/27/2004
Title:
RADIOACTIVE EFFLUENTS RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION LDCN 3614 TEXT 4.1
Title:
0 09/27/2003 ADMINISTRATIVE CONTROLS ORGANIZATION TEXT 4.2
Title:
TEXT 4.4
Title:
TEXT 4.5
Title:
TEXT 4.6
Title:
TEXT 4.7
Title:
ADMINISTRATIVE ADMINISTRATIVE ADMINISTRATIVE ADMINISTRATIVE ADMINISTRATIVE 0
09/27/2003 CONTROLS REPORTABLE EVENT ACTION 0
09/27/2003 CONTROLS PROCEDURES & PROGRAMS 0
09/27/2003 CONTROLS REPORTING REQUIREMENTS 0
09/27/2003 CONTROLS RADIATION PROTECTION PROGRAM 0
09/27/2003 CONTROLS TRAINING Page 14 of 14 Report Date: 10/28/04 Page 14 of 14 Report Date: 10/28/04
SUSQUEHANNA STEAM ELECTRIC STATION PPL Rev. 7 LIST OF EFFECTIVE SECTIONS (TECHNICAL REQUIREMENTS MANUAL)
Section Title Effective Date TOC TABLE OF CONTENTS 01/21/04 1.0 USE AND APPLICATION Page TRM 1 1.0-1 Page TRM / 1.0-2 Page TRM /1.0-3 2.0 3.0 3.1 3.2 PLANT PROGRAMS Page 2.0-1 Pages TRM / 2.0-2 through TRM /2.0-4 Page TRM / 2.0-5 Page TRM /2.0-6 Page TRM /2.0-7 Page TRM I 2.0-8 Page TRM /2.0-9 Pages TRM /2.0-10 and TRM /2.0-11 Page TRM /2.0-12 Page TRM /2.0-13 APPLICABILITY Pages TRM /3.0-1 and TRM 1 i.0-2)
Page TRM /3.0-3 l
Page TRM /3.0-4 N,,
REACTIVITY CONTROL SYSTEMS Pages 3.1-1 ttnough 3.1-6 Pages TRM13.1-7 and rRM / 3.1-8 Pages TRM / 3.1-9 and TRM / 3.1-9a Page(RM 13 10 CORE9PERATING LIMITS REPORT VPagv21A Q
gTRM /13.2-2 through TRM / 3.2-37 INSTRUMENTATION Pages TRM 1 3.3-1 through TRM / 3.3-3 Page TRM / 3.3-4 Pages 3.3-5 through 3.3-8 Pages TRM / 3.3-9 and TRM / 3.3-9a Pages TRM / 3.3-10 and TRM / 3.3-11 Page TRM /3.3-12 Pages TRM / 3.3-13 and TRM /3.3-14 Page TRM /3.3-15 Page TRM 13.3-16 08/31/1998 10/04/2002 08/31/1998 08/31/1998 06/25/2002 04/12/1999 10/22/2003 10/22/2003 08/30/2001 09/06/2002 04/12/1999 10/22/2003 06/1612000 04/08/1999 03/15/2002 04/08/1999 08/31/1998 06/05/2002 02/18/1999 02/18/1999 68/31/1998 10/15/2004
.1 3.3 07/16/1999 11/28/2000
...08/31/1998 12/17/1998 12/17/1998 03/30/2001 12/14/1998 10/22/2003 06/27/2001 SUSQUEHANNA -UNIT 2 TRM I LOES-1 EFFECTIVE DATE 10/15/2004
SUSQUEHANNA STEAM ELECTRIC STATION PPL Rev. 7 UST OF EFFECTIVE SEC77ONS (TECHNICAL REQUIREMENTS MANUAL)
Section Title Effective Date Pages TRM / 3.3-17 and TRM / 3.3-18 Pages TRM /3.3-19 and TRM / 3.3-20 Page 3.3-21 Pages TRM / 3.3-22 through TRM / 3.3-24 Page TRM /3.3-25 06/14/2002 10/22/2003 08/3111998 05/16/2003 10/22/2003 10/23/1998 08/31/1998 3.4 REACTOR COOLANT SYSTEM Pages 3.4-1 through 3.4-5 Pages 3.4-6 through 3.4-13 3.5 EMERGENCY CORE COOLING AND RCIC Pages 3.5-1 through 3.5-3 Page TRM / 3.5-4 Pages 3.5-5 through 3.5-7 08/3111998 04/1712000 08/31/1998 3.6 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 08/31/1998 01/07/2002 08/31/1998 12131/2002 3.7 PLANT SYSTEMS Pages TRM / 3.7-1 and TRM / 3.7-2 Page 3.7-3 Pages TRM / 3.7-4 through TRM / 3.7-10 Page TRM / 3.7-11 Pages TRM / 3.7-12 through TRM / 3.7-27 Pages TRM 1 3.7-28 through TRM / 3.7-31 Page TRM / 3.7-32 Page TRM / 3.7-33 Pages TRM / 3.7-34 through TRM / 3.7-36 Pages 3.7-37 through 3.7-39 Pages TRM / 3.7-40 and TRM / 3.7-40a Pages 3.7-41 and 3.7-42 Pages 3.7-43 through 3.7-47 Page TRM / 3.7-48 Pages TRM / 3.7-49 and TRM / 3.7-50 Pages TRM / 3.7-51 and TRM / 3.7-52 Page TRM / 3.7-53 ELECTRICAL POWER Pages TRM / 3.8-1 and TRM /3.8-2 Page 3.8-3 Page TRM /3.8-4
- Pages TRM / 3.8-5 and TRM /3.8-6 07/29/1999 08/31/1998 08/02/1999 01/21/2000 08/0211999 11/16/2001 01/09/2004 10/05/2002 02/01/1999 08/31/1998 08/11/2000 08/31/1998 10/13/1998 03/08/2003 03/09/2001 04/15/2003
...07129/1999 04102/2002 08/31/1998 12131/2002 04/0212002 3.8 SUSQUEHANNA -UNIT 2 TRM I LOES-2 EFFECTIVE DATE 10/15/2004
SUSQUEHANNA STEAM ELECTRIC STATION PPL Rev. 7 LIST OF EFFECTIVE SECTIONS (TECHNICAL REQUIREMENTS MANUAL)
Section Title Effective Date Pages TRM / 3.8-7 through TRM / 3.8-8 Page TRM / 3.8-9 Page 3.8-10 Page TRM / 3.8-11 Pages 3.8-12 through 3.8-14 Pages TRM / 3.8-15 through TRM /3.8-17 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.
08/31/1998 08/2412001 08/31/1998 08/1012004 08/31/1998 04/0212002
- 02/01/1999
- 04/02/2002 02/01/1999 06/06/1999 08/31/1998 3.9 3.10 REFUELING OPERATIONS Pages 3.9-1 through 3.9-3 MISCELLANEOUS Pages 3.10-1 through 3.10-4 Page TRM / 3.10-5
- Page TRM /3.10-6 Page TRM / 3.10-7 Page TRM / 3.10-8 08/31/1998 08/30/1998 03/08/2003 06/05/2002 04107/2000 Corrected 04/17/2002 3.11 3.12 4.0 RADIOACTIVE EFFLUENTS Pages 3.11-1 through 3.11-12 Pages 3.11-13 through 3.11-16 Pages 3.11-17 and 3.11-18 Page TRM / 3.11-19 Pages 3.11-20 and 3.11-21 Pages TRM / 3.11-22 through TRM / 3.11-24 Page 3.11-25 Pages TRM / 3.11-26 through TRM / 3.11-32 Pages 3.11-33 through 3.11-47 LOADS CONTROL PROGRAM Pages TRM / 3.12-1 through TRM / 3.12-5 ADMINISTRATIVE CONTROLS Pages 4.0-1 through 4.0-8 08/31/1998 09/01/1998 08/31/1998
- 01/2112004 08/31/1998 04/02/2002 09/01/1998 01/21/2004 08/31/1998 02/05/1999
, 08/31/1998 SUSQUEHANNA - UNIT 2 TRM / LOES-3 EFFECTIVE DATE 10/15/2004
SUSQUEHANNA STEAM ELECTRIC STATION PPL Rev. 7 UST OF EFFECTIVE SECTIONS (TECHNICAL REQUIREMENTS MANUAL)
Section Title Effective Date B 3.0 B3.1 APPLICABILITY BASES Pages B 3.0-1 through B 3.0-10 Pages TRM / B 3.0-11 through 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 08/31/1998 03/15/2002 07/13/1999 08/31/1998 07/13/1999 02/18/1999 B 3.2 CORE OPERATING LIMITS BASES Page B 3.2-1 08/31/1998 B3.3 B3.4 B3.5 INSTRUMENTATION BASES Page TRM/B 3.3-1 Page B 3.3-2 Pages TRM / B 3.3-3 and TRM l B 3.3-3A Pages TRM / B 3.3-4 through TRM / B 3.3-6 Pages TRM / B 3.3-7 through TRM / B 3.3-9 Pages B 3.3-10 through B 3.3-12 Page TRM / B3.3-13 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 3.3-20 and TRM / B 3.3-21 Page TRM / B3.3-22 Page TRM / B3.3-23 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 04/07/2000 08/31/1998 12/29/2000 03/21/2003 03/30/2001 08/31/1998 10/22/2003 06/25/2002 06/14/2002 06/14/2002 10/22/2003 10/22/2003 10/22/2003 05/16/2003 10/22/2003 05/16/2003 08/31/1998 10/15/1999 08/31/1998 ECCS AND RCIC BASES Pages B 3.5-1 through B 3.5-5 08/31/1998 B 3.6 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 07/26/2001 02/01/1999 08/31/1998 09/23/1999 01/07/2002 SUSQUEHANNA - UNIT 2 TRM / LOES-4 EFFECTIVE DATE 10/15/2004
SUSQUEHANNA STEAM ELECTRIC STATION PPL Rev. 7 IJST OF EFFECTIVE SECTIONS (TECHNICAL REQUIREMENTS MANUAL)
Section Title Effective Date Pages TRM I B 3.6-6 through TRM / B 3.6-11 12/31/2002 B 3.7 PLANT SYSTEMS BASES Pages B 3.7-1 and B 3.7-2 Pages TRM I B 3.7-3 through TRM I B 3.7-7 Page TRM I B 3.7-7a Pages TRM I B 3.7-8 through TRM I B 3.7-10 Page TRM I B 3.7-1 Oa Pages TRM I B 3.7-11 through TRM / B 3.7-14 Page TRM / B 3.7-14a and TRM / B 3.7-14b Pages TRM /,B 3.7-15 and TRM I B 3.7-16 Pages B 3.7-17 through B 3.7-20 Pages TRM I B 3.7-21 through TRM/B 3.7-21a Pages TRM/B 3.7-22 and TRM/B 3.7-23 Pages B 3.7-24 through B 3.7-30 Pages TRM I B 3.7-31 and TRM I B 3.7-32 Page TRM I B 3.7-33 Pages TRM I B 3.7-34 and TRM l B 3.7-35 08/31/1998 08/02/1999 08/02/1999 08/02/1999 08/02/1999 08/02/1999 01/09/2004
. 02/01/1999 08/31/1998 05/11/2001 04/07/2000 I08/31/1998 03/09/2001 04/15/2003 07/05/2000 B 3.8 B.3.9 ELECTRICAL POWER BASES Pages TRM / B 3.8-1 and TRM / B 3.8-2 Page TRM / B 3.8-2a Page TRM 1 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 3.8-17 REFUELING OPERATIONS BASES Pages B 3.9-1 and B 3.9-2 '-
Pages B 3.9-3 through B 3.9-7 04/02/2002 04/02/2002 04/02/2002 04/02/2002 04/02/2002 08/10/2004 08/31/1998 04/02/2002 08/31/1998 10/23/1998 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 i B 3.10-5 Pages TRM / B 3.10-6 and TRM / 3.10-7 08/31/1998 03/08/2003 08/23/1999
-04/17/2002 B 3.11 RADIOACTIVE EFFLUENTS BASES Pages B 3.11-1 through B 3.11-9 Pages TRM / B 3.11-10 Pages TRM/B 3.11-11 and TRM/B 3.11-1Ia Pages TRM/B 3.11-12 and TRM/B 3.11-13 08/31/1998
'02/01/1999 04/07/2000 02/01/1999 SUSQUEHANNA - UNIT 2 TRM / LOES-5 EFFECTIVE DATE 10/15/2004
SUSQUEHANNA STEAM ELECTRIC STATION PPL Rev. 7 LIST OF EFFECTIVE SECT1ONS (TECHNICAL REQUIREMENTS MANUAL)
Section Title Effective Date 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 Page TRM / B 3.11-22 Page TRM / B 3.11.23 PageTRM/B3.11-23a PagesTRM/B3.11-24andTRM/B3.11-25 Pages B 3.11-26 through B 3.11-35 Page TRM / B 3.11-36 11/01/1999 02/01/1999 08/31/1998 04/02/2002 04/02/2002
'10/15/2004 10/15/2004 04/02/2002 04/02/2002 01/21/2004 08/31/1998 02/12/1999 02/05/1999 B.3.12 LOADS CONTROL PROGRAM BASES Pages TRM / B 3.12-1 through TRM / B 3.12-3 TRWY ted LOES.doc 10114104 SUSQUEH.ANNA - UNIT 2 TRM / LOES-6 EFFECTIVE DATE 10/15/2004
Core Operating Umits Report (COLR) 3.2.1 PPL Rev. 2 3.2 Core Operating Limits Report (COLR) 3.2.1 Core Operating Umits Report (COLR)
TRO 3.2.1 APPLICABILITY:
The Core Operating Umits specified in the attached COLR shall be met.
Specified in the referenced Technical Specifications.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.
Core Operating Umits 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 3.2-1 EFFECTIVE DATE 8/31/1998
PPL Rev. 2 PL-NF-03-001 Rev. 3 Page1 of 36 Susquehanna SES Unit 2 Cycle 12 CORE OPERATING LIMITS REPORT Nuclear Fuels Engineering October 2004
- s.,
pp1 I SUSQUEHANNA UNIT 2 TRM/3.2-2 EFFECTIVE DATE 10/15/2004
PPL Rev. 2 PL-NF-03-001 Rev.3 Page 2 of 36 CORE OPERATING LIMITS REPORT REVISION DESCRIPTION INDEX Rev.
Affected
-No.
Sections DescriptionlPurpose of Revision ALL 5.0 6.0 8.0 TOC 1.0 9.0 10.0 5.0 8.0 10.0 Issuance of this COLR is in support of Unit 2 Cycle 12 operation.
This revision adds a text box to all appropriate plots. This text box indicates that for all bypass operable cases, four bypass valves are assumed operable. For the bypass inoperable cases, the text box indicates that two or more bypass valves are assumed inoperable.
This revision was generated in response to Facility Operating License Amendment 185 which altered SR 3.7.6.1.
This revision is administative in nature and no underlying calculations or plotted data were altered.
This revision adds the Power / Flow map to the COLR. Section 1.0 was revised to include the stability regions as part of the COLR. The Power/
Flow map was added as Section 9.0. The Reference section was renumbered as Section 10.0 and a stability reference added.
This revision is administrative in nature since the Power I Flow map is already included in NDAP-QA-0338.
The figures within Section 5.0 and Section 8.0 are revised to incorporate the 0.02 MCPR Safety Limit reduction approved by Amendment No. 191.
Figure 52-2 is revised to correct the Operating Limit error documented by CR 606127.
FORM NFP-QA-008-2, Rev. 1 SUSQUEHANNA UNIT 2 TRM/3.2-3 EFFECTIVE DATE 10/15/2004
PPL Rev. 2 PL-NF-03-001 Rev. 3 Page 3 of 36 SUSQUEHANNA STEAM ELECTRIC STATION Unit 2 Cycle 12 CORE OPERATING LIMITS REPORT Table of Contents 1.0 2.0 3.0 4.0 5.0 6.0 7.0 8.0 9.0
10.0 INTRODUCTION
4........................
DEFINITIONS
.5 SHUTDOWN MARGIN.6 AVERAGE PLANAR LINEAR HEAT GENERATION RATE (APLHGR)....................... 7 MINIMUM CRITICAL POWER RATIO (MCPR).9.
LINEAR HEAT GENERATION RATE (LHGR).
20 AVERAGE POWER RANGE MONITOR (APRM) GAIN AND SETPOINTS.23 RECIRCULATION LOOPS - SINGLE LOOP OPERATION.26 POWER I FLOW MAP........................................................................ 33 REFERENCES........................................................................................................... 35 SUSQUEHANNA UNIT 2 TRM/3.2-4 EFFECTIVE DATE 10/15/2004
PPL Rev. 2 PL-NF-03-001 Rev. 3 Page 4 of 36
1.0 INTRODUCTION
This CORE OPERATING LIMITS REPORT for Susquehanna Unit 2 Cycle 12 is prepared in accordance with the requirements of Susquehanna Unit 2, Technical Specification 5.6.5. As required by Technical Specifications 5. O, core shutdown margin, the core operating limits, APRM setpoints, and stability regions 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 10/15/2004
PPL Rev. 2 PL-NF-03-001 Rev.3 Page 5 of 36 2.0 DEFINITIONS Terms used in this COLR but not defined in Section 1.0 of the Technical Specifications or Section 1.1 of the Technical Requirements Manual are provided below.
2.1 The AVERAGE BUNDLE EXPOSURE shall be equal to the total energy produced by the bundle divided by the total initial weight of uranium in the fuel bundle.
2.2 The AVERAGE PLANAR EXPOSURE at a specified height shall be equal to the total energy produced per unit length at the specified height divided by the total initial weight of uranium per unit length at that height.
2.3 The FRACTION OF LIMITING POWER DENSITY (FLPD) shall be the LHGR existing at a given height divided by the applicable LHGR for APRM Setpoint Limit for that bundle type.
2.4 The FRACTION OF RATED THERMAL POWER (FRTP) shall be the measured THERMAL POWER divided by the RATED THERMAL POWER.
2.5 FDLRX is the ratio of the maximum LHGR calculated by the core monitoring system for each fuel bundle divided by the LHGR limit for the applicable fuel bundle type.
2.6 MFLCPR is the ratio of the applicable MCPR operating limit for the applicable fuel bundle type divided by the MCPR calculated by the core monitoring system for each fuel bundle.
2.7 MAPRAT is the ratio of the maximum APLHGR calculated by the core monitoring system for each fuel bundle divided by the APLGHR limit for the applicable fuel bundle type.
2.8 FDLRC is the ratio of the maximum LHGR calculated by the core monitoring system for each fuel bundle divided by the LHGR for APRM Setpoint Limit for the applicable fuel bundle type.
SUSQUEHANNA UNIT 2 TRM/3.2-6 EFFECTIVE DATE 10/15/2004
PPL Rev. 2 PL-NF-03-001 Rev. 3 Page 6 of 36 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%
k/k with the highest worth rod analytically determined OR b) 028% AkIk with the highest worth rod determined by test Since core reactivity will vary during the cycle as a function of fuel depletion and poison bumup, Beginning of Cycle (BOC) SHUTDOWN MARGIN (SDM) tests must also account for changes in core reactivity during the cycle. Therefore, the SDM measured at BOC must be equal to or greater than the applicable requirement from either 32.a or 3.2.b plus an adder, FR". 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 "RW 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 10/15/2004
PPL Rev. 2.
PL-NF-03-001 Rev. 3 Page 7 of 36 4.0 AVERAGE PLANAR UNEAR HEAT GENERATION RATE (APLHGR) 4.1 Technical Specification Reference Technical Specification 3.2.1 4.2 Descrihtion 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 10/15/2004
K
(-.
U1 Jo~
m a
-t N3a SSES UNIT 2 CYCLE 12 16-14 -
r-
-.a,12 -
M r\\ ccin 0
Z 8
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- a.
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1.0000 20000 30000 40000 50000 Average Planar Exposure (MWD)MTU)
AVERAGE PLANAR LINEAR HEAT GENERATION RATE LIMIT VERSUS AVERAGE PLANAR EXPOSURE TWO LOOP OPERATION ATRIUMTM.10 FUEL FIGURE 4.2-1 60000 70000
- 0) 0
PPL Rev. 2 PL-NF-03-001 Rev.3 Page 9 of 36 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 (ATRIUM'-1 0) 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 52-1: 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.
5.3 Average Scram Time Fraction Table 5.3-1 provides the relationship between average scram time to control rod position and scram time fraction. The evaluation of scram insertion time data, as it relates to the attached table should be performed per Reactor Engineering procedures.
SUSQUEHANNA UNIT 2 TRM/3.2-10 EFFECTIVE DATE 10/15/2004
PPL Rev. 2 PL-NF-03-001 Rev. 3 Page 10 of 36 -
EOC-RPT and Main Turbine Bypass Operable SUSQUEHANNA UNIT 2 TRM/3.2-11 EFFECTIVE DATE 10/15/2004
c C-f" Ln CV rn Jo m
Z
- _C=
--i SSES UNIT 2 CYCLE 12 2.3 2.2 2.1 2.0
.I LEE 6
I I
I LEGEND CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 USED IN DETERMINING MFLCPR I
- .1 1__
--I
- la E 1.9 0I co CL 2 1.8 0.
0'L 1.7
-u I-m 1.6 (30,1.54)
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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 w(r-O CD Z
-L 6
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2.0 C.1 SSES UNIT 2 CYCLE 12
=
LEGEND CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME
__._____SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 (25,2.28)
D m DERMNING MFLCPR (30,2.23)
\\'..~t If I 0
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REEEC:T.S. 3.2.2 B
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1.7 1.6 1.5 1.4 1.3 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 (BOO TO EOC)
FIGURE 5.2-2
-u (P
Q o-co, 0) 0 co
-U Fl-z
-L
PPL Rev. 2 PL-NF-03-001 Rev. 3 Page 13 of 36 Main Turbine Bypass Inoperable I EOC-RPT Operable SUSQUEHANNA UNIT 2 TRM/3.2-14 EFFECTIVE DATE 10/15/2004
(=
(**.
C Ln C=
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--i rN3 SSES UNIT 2 CYCLE 12
.2.3 2.2 I
I 1I 4
4 r
I EGEND JRVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME JRVE B: REALISTIC AVERAGE SCRAM INSERTION TIME 2.1 I
I-1
!9 I
I I
I 2.0 I
I 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 V CX,
'-a En E 1.9 4..
! 1.8 0.0.
m u"- 1.7 1.6 I
I AUSED N DETERMINI-NG MFLCPR REE30,1
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IV I-CD
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1.5 1.4 1.3 30 40 50 60 70 80 90 100 110 Total Core Flow (MLB/HR)
MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW MAIN TURBINE BYPASS INOPERABLE / EOC-RPT OPERABLE TWO LOOP OPERATION (BOC TO EOC)
FIGURE 5.2-3 O 3<
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I.(.
)
P1 Z
..- I I l 3.0 2.9 2.8 2.7 2.6 2.5
-4 R
-'al m
T1 m
-4 m
1-5
'-a u,
1-5
.- 2.4
= 2.3 0
O 2.1 a 2.0 L,
2 1.9 1.8 1.7 1.6 1.5 1.4 1.3
-u
-u I-0 (100,1.77) 20 30 40 50 60 70 80 90 Core Power (% RATED)
MCPR OPERATING LIMIT VERSUS CORE POWER MAIN TURBINE BYPASS INOPERABLE I EOC-RPT OPERABLE TWO LOOP OPERATION (BOC to EOC)
FIGURE 5.2-4 100 (0 m (D
co co at
-V z
'1 0Co'6 0
PPL Rev. 2 PL-NF-03-001 ERev. 3 Page 16 of 36 EOC-RPT Inoperable/
Main Turbine Bypass Operable
'HANNA UNIT 2 TRM/3.2-17 EFFECTIVE DATE 10/1 SUSQUE-
./0 SUSQUE L5/2004
C C
e***
VI)
C=
V) 91-C=
t-'
--I N,
SSES UNIT 2 CYCLE 12 2.3 2.2 I*
t 91 LEGEND CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME 2.1 4
4 I
I I
I 2.0 I.
- 1.
LJ SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 L-I
.oO
- E 1.9 0.8 a:3 i) 1.7 USED3IN DETERMINING MFLCPR
... I__
1.6-
-I I
I t
(30,1.54)
P1 r-n
-n
-i 0-4 P1 C)
F-4 N3 (108,1.54)
I I
I 4-A I
1.5 1.4 I
i
IREFERENCE:
T.S. 3.3.4.1 and 3.2.21 1.3 30 40 50 60 70 80 90 100 110 Total Core Flow (MLB/HR)
MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW EOC-RPT INOPERABLE / MAIN TURBINE BYPASS OPERABLE TWO LOOP OPERATION (BOO TO EOC)
FIGURE 5.2-5
-o (0
-L co~
CD
~0
-u z
'1
-L
(I C
C ril CD c
R F-4
--I f\\3
--I CA)
W-
- s.
SSES UNIT 2 CYCLE 12 3.0 2.9 2.8 2.7 2.6 I
T I
I I,
I.
I.
a.
END VE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME VE B: REALISTIC AVERAGE SCRAM INSERTION TIME
- 4.
- 4.
4.-
- 4.
- 4.
4.-
i I
I a
r
- 1 2.5 O_ 2.4 Ei 2.3 m
2.2 o 2.1 m 2.0 1 1.9 II II ____ I I SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 I
(25,2.29)
I I
I I
I 1
2 I
(30,2.23) 1-.
USED IN DETERMINING MFLCPR I
1.8
~ ( 4 0,1.7 )_
I A
REFERENCE:
T.S. 3.3.4.1 ad 3.2(71
__ [E:
T.S.__
3.3.4.__
_(74,1.54) rrl n
-n q
m m
m C-a k-A (7'
S...
1.7 1.6 1.5 1.4 1.3 (100,1.54) 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
-0,3-u
_co $
- 0) co am.
PPL Rev. 2 PL-NF-03-001 Rev. 3 Page 19 of 36 Table 5.3-1 Average Scram Time Fraction Table For Use With Scram Time Dependent MCPR Operating Limits Control Rod Average Scram Time to Position (seconds)
Position 45 0.470 0.480
.0.490 0.500 0.510 0.520 39 0.630 0.676 0.722 0.768 0.814 0.860 25 1.500 1.582 1.664 1.746 1.828 1.910 5
2.700.
2.848 2.996 3.144 3.292 3.440 Scram Time 0.000 0.200 0.400 0.600 0.800 1.000 Fraction Average Scram Realistic Maximum Insertion Time Allowable SUSQUEHANNA UNIT 2 TRM/3.2-20 EFFECTIVE DATE 10/15/2004
PPL Rev. 2 PL-NF-03-001 Rev. 3 Page 20 of 36 6.0 UNEAR HEAT GENERATION RATE (LHGR) 6.1 Technical Specification Reference Technical Specification 3.2.3 and 3.7.6 6.2 Descriition The LHGR limits are specified below as a function of Main Turbine Bypass operability for each fuel type as follows:
Main Turbine Bypass ODerable The LHGR for ATRIUM'-1 0 fuel shall not exceed the LHGR limit determined from Figure 6.2-1.
Main Turbine Bypass Inoperable The LHGR for ATRlUM^-1 0 fuel shall not exceed the LHGR limit determined from Figure 6.2-2.
The LHGR limits in Figures 6.2-1 and 6.2-2 are valid for Two Loop and Single Loop operation.
SUSQUERANNA UNIT 2
'TRM/3.2-21 EFFECTIVE DATE 10/15/2004
CZ
.0 1
s SSES UNIT 2 CYCLE 12 SAFETYANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 14 IREFRNC:T.S 32.
SEDIN DETERMINING FDLRXI.
- .7 12.-
10.b.T ri-..
.I I
I I
I I
I I
I I
I 5
c~)
- s s
s s
s a 67000,7.14 6
0U i--
A ergePlna Ex osr (M
DM U.
s 5
S 5D5 5
r5 5
CD c
Z LINEAR HEAT GENERATION RATE LIMIT VERSUS AVERAGE PLANAR EXPOSURE MAIN TURBINE BYPASS OPERABLE C.
o ATRIUMTM-10 FUEL C
FIGURE 6.2-1
.0 1
SSES UNIT 2 CYCLE 12 SAFETY ANALYSES ASSUME THAT TWO OR MORE BYPASS VALVES ARE!INOPERABLE PER SR 3.7.6.1 OR 3.7.6.2 14.
REFERENCE:
T.S. 3.2.3 and 3.7.6 a
- a.
P.
USED IN DETERMINING FDLRaXa a
O.O,1l.9
~
15000,11.9
.2
-4 r
a a..I PO 0 0
r!1 a
a a
a a
a a
a a
a a
a a
a aaL 6
700,.3 I,.1 a
a I
I a
t a
a a
a a
a a
a a
a 6a70 0 6a 36 CD 4
a a
a a
a a
a a
a a
a a
- n a
a 0a 20a00a 0 30000a 40a000 60a 00 6000a a000a a
a a
a a
a a
a a
a a
aa a
a a
a Average Planar Exposure (MWD1MTU)
LINAR EATGENERATION RATE LIMIT VERSUS AVERAGE PLANAR EXPOSURE MAIN TURBINE BYPASS INOPERABLE ATRIU'M10 FUEL FIGURE 6.2-2
PPL Rev. 2 PL-NF-03-O01 Rev.3 Page 23 of 36 7.0 AVERAGE POWER RANGE MONITOR (APRM) GAIN AND SETPOINTS 7.1 Technical SDecification Reference Technical Specification 32.4 and 3.3.1.1 7.2 Description The APRM flow biased simulated thermal power-upscale scram trip setpoint (S) and flow biased neutron flux-upscale control rod block trip setpoint (SRm) shall be established as specified in Table 7.2-1 and Table 7.2-2, including any adjustments per Technical Specification LCO 3.2.4.
Technical Specification LCO 3.2.4 provides an option to adjust the APRM setpoints when MFLPD is greater than FRACTION OF RATED THERMAL POWER (FRTP). The adjustment applies to both the APRM flow biased simulated thermal power-upscale scram trip setpoint and flow biased neutron flux-upscale control rod block trip setpoint for Two Loop and Single Loop operation. The APRM setpoints for Specification 3.2.4 are established in Tables 7.2-1 and 7.2-2.
SUSQUEHANNA UNIT 2 TRM/3.2-24
.EFFECTIVE DATE 10/15/2004
PPL Rev. 2 PL-NF-03-001 Rev. 3 Page 24 of 36 Table 7.2-1 APRM Setpoint for Two Loop Operation Trip Setpoint Allowable Value S 5 (0.58W + 59%) T TS <5 (6.58W + 62%) T' SRB (O.58W + 50%) T SRB<5 (0.58W + 53%) T Table 7.2-2 APRM Setpoint for Single Loop Operation Trip Setpoint Allowable Value S* (0.58W + 540/6) T S5(0.58W + 57%) T' SRB (0.58W + 45%) T SR8 5 (0.58W + 48%) T where: S and SFO are in percent of RATED THERMAL POWER W
Loop recirculation flow as a percentage of the loop recirculation flow which produces a core flow of 100 million Ibs/hr T =
Lowest value of the ratio of FRTP divided by the MFLPD.2 The FLPD is the actual LHGR divided by the applicable LHGR limit for APRM Setpoints. The LHGR limit for APRM setpoints for ATRIUM-1 0 fuel shall be taken from Figure 7.2-1.
The LHGR for APRM setpoint limits in Figure 7.2-1 are valid for Main Turbine Bypass Operable and Inoperable and EOC-RPT Operable and Inoperable for both Two and Single Loop operation.
For calculated T-values greater than 1.0, a ratio of 1.0 is used in the above equations.
APRM flow biased simulated thermal power-upscale scram allowable value in this table is equal to the value established in Technical Specification 3.3.1.1.
2 For the calculation of T, the value of MFLPD shall be the maximum value of FDLRC.
SUSQUEHANNA UNIT 2 TRM/3.2-25 EFFECTIVE DATE 10/15/2004
C0 1
SSES UNIT 2 CYCLE 12 0I0 tjJ.tJ.J1..0J0t 0.0,5.0: : :
REFERENCE:
rS. 3.24 :
14 S
0 5
0 0
0 0-0 0
C C
m8
.I.I.I0TIaI.4.I..:....I r....
6 -
S S
S S
S 0
6I5 0
0 I5 I.
I I0I0 5
0.
0-0-*0..
0r 5
0 5
50 0.0 00 0
3000 4
5 I0000 5 S0 5
0 0
6 0o 5
7000 ATR0SIUM0 5
0 S
0 5
0
-0 FUEL Co) 0 0
0 5
0 5
0 0
0 0
U FIGURE 57 0 : : :
2 5
0 0
- 1*
~
PPL Rev. 2 PL-NF-03-001 Rev. 3 Page 26 of 36 8.0 RECIRCULATION LOOPS - SINGLE LOOP OPERATION 8.1 Technical Specification Reference Technical Specification 3.2.1, 3.2.2, 3.2.3, 3.2.4, 3.3.4.1, 3.4.1, and 3.7.6 8.2 DescriDtion APLHGR The APLHGR limit for ATRIUMm-1O 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 limit for all fuel types (ATRIUMm-1 0) shall be the greater of:
a)
Flow-Dependent MCPR value determined from Figure 82-2 OR b)
The Power-Dependent MCPR value determined from one of the following figures, as appropriate:
Figure 82-3: EOC-RPT and Main Turbine Bypass Operable from BOC to EOC Figure 8.2-4: Main Turbine Bypass Inoperable / EOC-RPT Operable from BOC to EOC Figure 8.2-5: EOC-RPT Inoperable / Main Turbine Bypass Operable from BOO to EOC The MCPR limits in Figures 8.2-2 through 8.2-5 are valid only for Single Loop operation.
Linear Heat Generation Rate Limit The LHGR limits for Single Loop Operation are defined in Section 6.0.
SUSQUEHANNA UNIT 2 TRM/3.2-27 EFFECTIVE DATE 10/15/2004
PPL Rev. 2 PL-NF-03-001 Rev. 3 Page 27 of 36 Average Power Ranae Monitor (APRM) Gain And Setpoints APRM setpoints and the LHGR limit for APRM setpoints for Single Loop operation are defined In Section 7.0.
SUSQUEHANNA UNIT 2 TRM/3.2-28 EFFECTIVE DATE 10/15/2004
16
- -:::SSES UNIT 2 CYCLE 12
.2-
.P......
.J1......I J,
L
[L I
I I
S S
S 6
6 1
,.....EER.C..S.34...d3..
-4 u
.5 USED.I.D.TEMININGMAPRA S.
S
~
I II C-)
~
I S
~
~
S
~
S
~
~
S S
S S
S
~
g S
.5 5700S0 S4I8
~.
f~
s
~
sI4I Ln 0
S I
2000300 400 I
S.6000700 PO.
~
I
- ~
~.
C:)
Avers~
a ge Pl-nar Exposur (MWDMTU CD s
s s
s r-o ATRIUT.21 10-0.0,9.2 2 :
- :5000,9.:;: : :FIGURE 8.2-
(C k._-_
c, (n
r-'
SSES UNIT 2 CYCLE 12 2.6
'9 1
Y Y
I I
I I
2.5
'I 4
LEGEND CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME 2.4 9
'9 C
I I
I I
-I4
-S W"
'E 2.3 C
! 2.2 0
C.)
n 2.1 I
- 4.
.9
.9 I
USED IN DETERMINING MFLCPR
.i-T--
U-.
S (30,2.20)
I I
l I In t-9
-u
-u
.20)
Ad
'3
. i C,1I.
F-4 P1 t-aj C),
-.P 2.0 1.9
REFERENCE:
T.S. 3.4.1 and 3.2.
1.8 30 40 50 60 70 80 90 100 110 Total Core Flow (MLB/HR)
MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW SINGLE LOOP OPERATION (BOC to EOC)
FIGURE 8.2-2 toCD 0,
co 6
co~ 0
- 0)
As
(C; I,-,
(n C=
Lrn
- UCD, c-m
-4l SSES UNIT 2 CYCLE 12 3.5 3.4 3.3 3.2 3.1 IGEND I
I CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 3.0 I--&
DI 2.9 m 2.8 E 2.7 0.
0° 2.6 C.5 2 2.5
-i--(25,2.73)-
I USED IN DETERMINING MFLCPR
I 1
t-I
- 1 I
Y (30,2.67) -t t
I I
1 4-2.4 (39.4,!2.2_0-A--)
S c-n rn
!:i Ia) m-S P-S 2.3 2.2 2.1 2.0 1.9 (100,2.20)
I
.1 I
[ENCE:
T.S. 3.4.1 and 3.2.2 I.
-I 4
4
.6 4.
a I
I
- q.
- q.
.9 4.
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
-U D)
CD (D
0 co 0
D c.
-o z
'1 6
a4
C-c:
CA m
--I SSES UNIT 2 CYCLE 12 3.5 3.4 3.3 3.2 3.1 3.0 co Eg 2.9 o 2.8 CLG 2.7 0.
0° 2.6 s 2.5
._I I
I I
LEGEND
_ CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM
_ -INSERTION TIME CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME (25,3.01)
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 (4.7.0 )-
.(55.7,2.20) r-
-o I-0t 2.4 rr nr m
Cn
-I C-4 m
- -Im
~-S 2.3 2.2 2.1 2.0 1.9 (100,2.20)
I I.
REFERENCE:
T.S. 3.4.1, 3.7.6, and 3.2.2 I
5
- 4.
- 4.
I I
I I
I
.5 5
I.
S 20 30 40 50 60 Core Power (% RATED) 70 80 90 100 MCPR OPERATING LIMIT VERSUS CORE POWER MAIN TURBINE BYPASS INOPERABLE / EOC-RPT OPERABLE SINGLE LOOP OPERAtION (BOC to EOC)
FIGURE 8.2-4 Pa (0
ID Co 0
0)
CD CD,
-u z
'1 6
t R..
(t (C
Ln A:,
-i SSES UNIT 2 CYCLE 12 3.5 3.4 3.3 3.2 3.1 I
I I
I t
tLe."=l4Lu a: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME 1: REALISTIC AVERAGE SCRAM INSERTION TIME t
4 4-
- 4.
4 4-3.0 I
I l
SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 CO co CO
-n-n C,)
--I P1 I.
CD1 W 2.9
- 3 m 2.8 -
! 2.7 a
0° 2.6 -
a-0 E 2.5 2.4.
2.3 2.2 2.1 2.0 1.9 -
I t
4 4-4 I K
-(25,2.74)-
.1%
1 UUSED IN DETERMINING MFLCPR I
I Y
_(30.2.1L.-A o1 I
I
-u
-u I-(D 4
4 4
I 4
4 (39.4,2.20)
(100,2.20)
I I.
I
REFERENCE:
T.S. 3.4.1, 3.3.4.1, and 3.2.2 I
I
-4 I
- 4.
4 I
I I
20 30 40 50 60 70 Core Power (% RATED) 80 90 100 MCPR OPERATING LIMIT VERSUS CORE POWER EOC-RPT INOPERABLE I MAIN TURBINE BYPASS OPERABLE SINGLE LOOP OPERATION (BOC to EOC)
FIGURE 8.2-5 10 m t; (D
r
., X -
co 6
CI0 0
0 )
PPL Rev. 2 PL-NF-03-001 Rev. 3 Page 33 of 36 9.0 POWER / FLOW MAP 9.1 Technical Specification Reference Technical Specification 3.4.1 9.2 Description Monitor reactor conditions to maintain THERMAL POWER / core flow outside of Stability Regions I and 11 of the Power/ Flow map, Figure 9.1.
SUSQUEHANNA UNIT 2
. TRM/3.2-34 EFFECTIVE DATE 10/15/2004
PPL Rev. 2 PL-NF-03-001 Rev. 3 Page 34 of 36
. 120 120 110.
100W 90.
I-I.
I I...
I
Purpose:
Ii Infal/Date:
/
r STANIUTY REG"O I UAWTE SUM 0
MWUR LAW Of,28.C STABtUIYREON n JME=ATMLY EXITlRON 1AWON2754m I ' l
- f i t 8 8 o i l l f l l l
_9
,S m
JJ I
II H
it-'
t I~~~
l j,
RESTCTEDREWON (ft ddW~d Inbtfn G to sAmnn
.,S 1.-
-a E
0c.
a' 80 70 60 50 40 30S 20' 10 0
, T Ia
'T I -r--
Ti,--r r a T-
.LJ J..'..L IJ L JJ..L I 4J_
J-II as,, il til 4 -I--
- 4. 4 - a-I--
4-A-LJ _1_
LJ J
- JI_
4* '
I I It I I I
I a
ILJ J#L.
J
.J..l.
L J J-l
.r Ti-i t
-1t1_
liiil lii I SI Slj T
I I
a T
4_I 111I JJI rbsm-u Sc.rarnn-I-lI I
@I I II
~
l I I
I I
I I
I-I I
11 I
1 Approx I 1 1'...
30%
L.4...I
- Tia-,-
Tr I V
1,- 1 1
.1 Two Pump l'-
, J..,..
a
^4\\
I Il
.J.4_1 4.4.J.l_
44
-I-I I I I I I I I I
I\\ aS I a
a 110 100 90 80 70 60 50 40 30 20 10 I
Ij
- 1.J
-i.-I.
-..1 -I V a a a I 1 I
I I Ia I I -I
- 1.
LI-,
'aIX a
0aaai 0
10 20 30 40 50
.0 60 70 80 90 100 110 Total Core Flow (Mlbmlhr)
Figure 9.1 Power / Flow Map SUSQUEHANNA UNIT 2 TRM/3'. 2-35 EFFECTIVE DATE 10/15/2004
PPL Rev. 2 PL-NF-03-001 Rev. 3 Page 35 of 36 1
0.0 REFERENCES
10.1 The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC, specifically those described in the following documents:
- 1. PL-NF-90-001 -A, "Application of Reactor Analysis Methods for BWR Design and Analysis," July 1992.
- 2. PL-NF-90-001, Supplement 1-A, "Application of Reactor Analysis Methods for BWR Design and Analysis: Loss of Feedwater Heating Changes and Use of RETRAN MOD 5.1," August 1995.
- 3. PL-NF-90-001, Supplement 2-A, "Application of Reactor Analysis Methods for BWR Design and Analysis: CASMO-3G Code and ANFB Critical Power Correlation," July 1996.
- 4. PL-NF-90-O01, Supplement 3-A, "Application of Reactor Analysis Methods for BWR Design and Analysis: Application Enhancements," March 2001.
- 5. XN-NF-80-19(A), Volume 1, and Volume 1 Supplements 1 and 2 (March 1983),
and Volume 1 Supplerient 3 (November 1990), "Exxon Nuclear Methodology for Boiling Water Reactors: Neutronic Methods for Design and Analysis,"
Exxon Nuclear Company, Inc.
- 6. XN-NF-80-1 9(P)(A), Volumes 2, 2A, 2B, and 2C "Exxon Nuclear Methodology for Boiling Water Reactors: EXEM BWR ECCS Evaluation Model," September 1982.
- 7. XN-NF-80-19(P)(A), Volume 3 Revision 2 "Exxon Nuclear Methodology for Boiling Water Reactors Thermex: Thermal Umits Methodology Summary Description," 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, Inc. June 1986.
- 9. XN-NF-85-67(P)(A), Revision 1, "Generic Mechanical Design for Exxon Nuclear Jet Pump BWR Reload Fuel," Exxon Nuclear Company, Inc.,
September 1986.
- 10. ANF-524(P)(A), Revision 2 and Supplement 1, Revision 2, "Advanced Nuclear Fuels Corporation Critical Power Methodology for Boiling Water Reactors,"
November 1990.
- 11. NE-092-OO1A, Revision 1, "Ucensing Topical Report for Power Uprate With Increased Core Flow," Pennsylvania Power & Light Company, December 1992 and NRC SER (November 30, 1993).
SUSQUEHANNA UNIT 2 TRM/3.2-36 STEFFECTIVE DATE 10/15/2004
PPL Rev. 2 PL-NF-03-001 Rev. 3 Page 36 of 36
- 12. ANF-89-98(P)(A) Revision I and Revision 1 Supplement 1, 'Generic Mechanical Design Criteria for BWR Fuel Designs," Advanced Nuclear Fuels Corporation, May 1995;
- 13. ANF-91-048(P)(A), Advanced Nuclear Fuels Corporaftn Methodology for Boiling Water Reactors EXEM BWR Evaluation Model," January 1993.
- 14. XN-NF-79-71 (P)(A) Revision 2, Supplements 1, 2, and 3, Exxon Nuclear Plant Transient Methodology for Boiling Water Reactors," March 1986.
- 15. EMF-1 997(P)(A) Revision 0, 'ANFB-1 0 Critical Power Correlation,' July 1998, and EMF-1 997(P)(A) Supplement 1 Revision 0, 'ANFB-1 0 Critical Power Correlation : High Local Peaking Results," July 1998.
- 16. Caldon, Inc., 'TOPICAL REPORT: Improving Thermal Power Accuracy and Plant Safety While Increasing Operating Power Level Using the LEFM~'
System," Engineering Report - 80P, March 1997.
- 17. Caldon, Inc., S.U~plement to Topical Report ER-8OP: Basis for a Power Uprate with the LEFM' or LEFM CheckPlus7 System," Revision 0, Engineering Report ER-60P, May 2000.
- 18. EMF-85-74(P)(A), "RODEX2A (BWR) Fuel Rod Thermal-Mechanical Evaluation Model," Revision 0, Supplements 1 and 2, February 1998.
- 19. EMF-2158(P)(A), Revision 0, 'Siemens Power Corporation Methodology for Boiling Water Reactors: Evaluation and Validation of CASMO-4/Microbum-B2," Siemens Power Corporation, October 1999.
- 20. EMF-CC-074(P)(A), Volume 4, Revision 0, "BWR Stability Analysis:
Assessment of STAIF with Input from MICROBURN-B2," November 1999.
SUSQUEHANNA UNIT 2 TRM/3.2 EFFECTIVE DATE 10/15/2004
VENTILATION EXHAUST TREATMENT SYSTEM PPL Rev.2 B 3.11.2.5 B 3.11.2.5 VENTILATION EXHAUST TREATMENT SYSTEM BASES TRO This TRO ensures that the appropriate portions of the VENTILATION EXHAUST TREATMENT SYSTEM, as describedin the Offsite Dose Calculation Manual (ODCM) are OPERABLE at all times. The TRO is modified by a Note which requires that the appropriate portions of the VENTILATION EXHAUST TREATMENT SYSTEM be used to reduce radioactive materials in gaseous waste prior to their discharge when projected doses due to gaseous effluent releases from either reactor unit to areas at and beyond the SITE BOUNDARY would exceed 0.3 mrem to any organ in a 31 day period. This requirement provides reasonable assurance that the releases of radioactive materials in gaseous effluents will be kept "as low as reasonably achievable." This TRO implements the requirements of 10 CFR Part 50.36a, General Design Criterion 60 of Appendix A to 10 CFR Part 50, and the design objectives given in Section ll.D of Appendix I to 10 CFR Part 50. The limits governing the use of appropriate portions of the systems were specified as a suitable fraction of the dose design objectives set forth in Sections ll1.B and I.C of Appendix I, 10 CFR Part 50, for gaseous effluents (Ref. 1).
The VENTILATION EXHAUST TREATMENT SYSTEM is comprised of the following Unit 2 systems, as described in the ODCM:
The Unit 2 Reactor Building filtered exhaust system, including the following filters:
2F216A, 2F216B, 2F217A, 2F217B, 2F218A, 2F218B, 2F255A, 2F255B, 2F257A, 2F257B, 2F258A AND 2F258B.
The Unit 2 Turbine Building filtered exhaust system, including the following filters:
2F157A, 2F157B, 2F158A, and 2F158B.
(continued)
SUSQUEHANNA - UNIT 2 TRM / B 3.11-21 EFFECTIVE DATE 10/15/2004
VENTILATION EXHAUST TREATMENT SYSTEM B 3.11.2.5 PPL Rev. 2 B 3.11.2.5 VENTILATION EXHAUST TREATMENT SYSTEM BASES TRO (continued)
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.1 This section of the TRM is part of the ODCM (Ref. 2) and implements the requirements of the Radiological Effluent Controls Program (Ref. 3).
ACTIONS The ACTIONS are defined to ensure proper corrective measures are taken in response to the inoperable components. Dose evaluations are performed when evolutions occur which result in an effluent path to the environment with some level of degraded treatment. In effect, degraded treatment renders the monthly dose projection per TRS 3.11.2.5.1 questionable. The dose evaluation is an estimated projection under the degraded conditions.
Dose evaluations should be performed under the following conditions:
- 1. When bypassing a treatment system (a preliminary evaluation prior to bypassing the filter and a follow-up evaluation after the bypass);
(continued)
SUSQUEHANNA - UNIT 2 TRM / B3.11-22 EFFECTIVE DATE 10/15/2004
VENTILATION EXHAUSTTREATMENTSYSTEM PPL Rev. 2 B 3.11.2.5 B 3.11.2.5 VENTILATION EXHAUST TREATMENT SYSTEM BASES ACTIONS
- 2. When placing an inoperable filter train in service (a preliminary l
(continued) evaluation prior to starting the system and a follow-up evaluation after the system is in service);
- 3. If a surveillance on a treatment system fails while the filter is in service; and
- 4. Any other event which results in degraded treatment l
The appropriate portion of the VENTILATION EXHAUST TREATMENT I
SYSTEM will be declared inoperable if any of the following conditions exist l
1.- Failure of a surveillance test; l
- 2. Broken or non-functional component which prevents the system from being run (e.g. both 100% fans or one 50% fan in the system); or l
- 3. Bypass or degradation of system filtration in which effluent flow continues without full treatment l
A.1 With any portion of the VENTILATION EXHAUST TREATMENT SYSTEM inoperable, action must be taken to restore it to OPERABLE status. The 31 day Completion Time is a reasonable time frame to repair the inoperable components.
B.1 If the Required Action and Completion Time of Condition A are not met, or.
gaseous waste is being discharged without treatment and in excess of the TRO limits, a Special Report must be prepared and submitted to the Commission. The 30 day Completion Time is reasonable for preparation of the report. The Special Report should include the following information:
- 1. Identification of the inoperable equipment or subsystems and the reason for inoperability-,
- 2. Action(s) taken to restore the inoperable equipment to OPERABLE status; and l
- 3. Summary description of action(s) taken to prevent a recurrence.
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SUSQUEHANNA - UNIT 2 TRM / B3.11-23 EFFECTIVE DATE 04/02/2002
VENTILATION EXHAUST TREATMENT SYSTEM B 3.11.2.5 PPL Rev. 2 B 3.11.2.5 VENTILATION EXHAUST TREATMENT SYSTEM BASES TRS The TRSs are performed at the specified Frequency to ensure that the VENTILATION EXHAUST TREATMENT SYSTEM is maintained OPERABLE.
I TRS 3.11.2.5.1 This surveillance requires that a dose projection be performed in accordance with the methodology and parameters in the ODCM. The dose projection is performed based on the most recently available effluent data.
If it is known prior to performing the dose projection that a treatment system will be out of service, and if data exists which indicates how the lack of treatment will impact effluents, these factors will be considered when performing the dose projection. The 31 day Frequency is consistent with Reference 3.
TRS 3.11.2.5.2 This surveillance verifies that the VENTILATION EXHAUST TREATMENT SYSTEM is OPERABLE by operating the system 210 minutes. Operation of the system for at least 10 minutes provides sufficient time to verify the appropriate parameters are within their normal operating range. The Frequency of 92 days is appropriate considering the performance of modnthly dose projections.
This TRS is modified by a Note which states that the TRS is not required to be performed if the appropriate system has been utilized to process radioactive gaseous effluents during the previous 92 days. This allowance is appropriate because actual processing of radioactive gaseous effluents demonstrates system OPERABILITY.
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REFERENCES
- 1. 10 CFR Part 50.
- 3. Technical Specification 5.5.4 - Radioactive Effluent Controls program.
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I SU§QUEHANNA - UNIT 2 TRM / B 3.11-23a EFFECTIVE DATE 4/212002