ML23107A132
| ML23107A132 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 03/31/2023 |
| From: | Susquehanna |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| 2023- 5375 | |
| Download: ML23107A132 (90) | |
Text
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~V~j MANUAL HARD COPY DISTRIBUTION DOCUMENT TRANSMITTAL 2 02 3-5375 USER INFORMATION:
GERLACH*ROSEY M Address: NUCSA2 Phone#:
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TO:
GERLACH*ROSEY M 03 / 31/2023 LOCATION:
USNRC FROM:
NUCLEAR RECORDS DOCUMENT CONTROL CENTER (NUCSA-2)
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of 2
I SSES MANUAL Manual Name :
TRM2
.nual
Title:
TECHNICAL REQUIREMENTS MANUAL UNIT 2 Table Of Contents Issue Date:
03/30/2023 Procedure Name Rev Issue Date Change ID Change Number TEXT LOES 99 01/03/2019
Title:
LIST OF EFFECTIVE SECTIONS TEXT TOC 28 12 / 13 / 2022
Title:
TABLE OF CONTENTS TEXT 1.1 0
11 / 19 / 2002
Title:
USE AND APPLICATION DEFINITIONS TEXT 2.1 1
02/04 / 2005
Title:
PLANT PROGRAMS AND SETPOINTS PLANT PROGRAMS TEXT 2.2 12 12/08/2022
Title:
PLANT PROGRAMS AND SETPOINTS INSTRUMENT TRIP SETPOINT TABLE TEXT 3.0 8
03 / 18/2021
Title:
APPLICABILITY TECHNICAL REQUIREMENT FOR OPERATION (TRO) APPLICABILITY TEXT 3. 1.1 1
11/09 / 2007
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 5
12/18/2017
Title:
REACTIVITY CONTROL SYSTEMS CONTROL ROD BLOCK INSTRUMENTATION TEXT 3.1.4 1
10/12/2020
Title:
REACTIVITY CONTROL SYSTEMS CONTROL ROD SCRAM ACCUMULATORS INSTRUMENTATION AND CHECK VALVE TEXT 3.2.1 20 03/30/2023
Title:
CORE OPERATING LIMITS REPORT (COLR)
Page 1 6f 15 Report Date: 03/31/23
SSES MANUAL Manual Name:
TRM2 Tanual
Title:
TECHNICAL REQUIREMENTS MANUAL UNIT 2 TEXT 3.3.1 0
11/19/2002
Title:
INSTRUMENTATION RADIATION MONITORING INSTRUMENTATION TEXT 3.3.2 3
03/31/2011
Title:
INSTRUMENTATION SEISMIC MONITORING INSTRUMENTATION TEXT 3.3.3 2
11/09/2007
Title:
INSTRUMENTATION METEOROLOGICAL MONITORING INSTRUMENTATION TEXT 3.3.4 11 07/21/2017
Title:
INSTRUMENTATION TRM POST-ACCIDENT MONITORING INSTRUMENTATION TEXT 3.3.5 0
11/19/2002
Title:
INSTRUMENTATION THIS PAGE INTENTIONALLY LEFT BLANK
'EXT 3. 3. 6 5
03/05/2019
Title:
INSTRUMENTATION TRM ISOLATION ACTUATION INSTRUMENTATION TEXT 3.3.7 4
01/17/2022
Title:
INSTRUMENTATION MAIN TURBINE OVERSPEED PROTECTION SYSTEM TEXT 3.3.8 1
10/22/2003
Title:
INTENTIONALLY LEFT BLANK TEXT 3.3.9 3
05/14/2009
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 3.3.12 2
04/02/2019
Title:
WATER MONITORING INSTRUMENTATION Page 2 of 15 Report Date: 03/31/23
SSES MANUAL Manual Name:
TRM2
.tanual
Title:
TECHNICAL REQUIREMENTS MANUAL UNIT 2 TEXT 3.4.1 l
04/26/2006
Title:
REACTOR COOLANT SYSTEM REACTOR COOLANT SYSTEM CHEMISTRY TEXT 3.4.2 1
04/16/2009
Title:
INTENTIONALLY LEFT BLANK TEXT 3.4.3 1
11/09/2007
Title:
REACTOR COOLANT SYSTEM REACTOR COOLANT SYSTEM (RCS)
TEXT 3.4.4 2
05/14/2009
Title:
REACTOR COOLANT SYSTEM REACTOR RECIRCULATION FLOW AND ROD LINE LIMIT TEXT 3.4.5 1
04/26/2006
Title:
REACTOR COOLANT SYSTEM REACTOR VESSEL MATERIALS J
.'EXT 3. 4. 6 1
04/25/2013
Title:
REACTOR RECIRCULATION SINGLE LOOP OPERATION SLO FLOW RATE RESTRICTION TEXT 3.5.1 2
03/05/2019
Title:
ECCS RPV WATER INVENTORY CONTROL AND RCIC SYSTEM ADS MANUAL INHIBIT TEXT 3.5.2 2
03/05/2019
Title:
ECCS RPV WATER INVENTORY CONTROL AND RCIC SYSTEM ECCS RPV WATER INVENTORY CONTROL AND RCIC MONITORING INSTRUMENTATION TEXT 3.5.3 1
03/05/2019
Title:
ECCS RPV WATER INVENTORY CONTROL AND RCIC SYSTEM LONG TERM NITROGEN SUPPLY TO ADS TEXT 3.6.1 0
11/19/2002
Title:
CONTAINMENT VENTING OR PURGING TEXT 3.6.2 3
01/03/2019
Title:
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 15 Report Date: 03/31/23
SSES MANUAL Manual Name:
TRM2 tanual
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 0
11/19/2002
Title:
PLANT SYSTEMS EMERGENCY SERVICE WATER SYSTEM (ESW) SHUTDOWN TEXT 3.7.2 0
11/19/2002
Title:
PLANT SYSTEMS ULTIMATE HEAT SINK (UHS) AND GROUND WATER LEVEL TEXT 3.7.3.l 7
04/21/2022
- Title: PLANT SYSTEMS FIRE SUPPRESSION WATER SUPPLY SYSTEM TEXT 3.7.3.2 3
04/16/2009
Title:
PLANT SYSTEMS SPRAY AND SPRINKLER SYSTEMS
'EXT 3. 7. 3. 3 4
05/16/2016
Title:
PLANT SYSTEMS CO2 SYSTEMS TEXT 3.7.3.4 2
04/16/2009
Title:
PLANT SYSTEMS HALON SYSTEMS TEXT 3.7.3.5 2
04/16/2009
Title:
PLANT SYSTEMS FIRE HOSE STATIONS TEXT 3.7.3.6 2
04/16/2009
Title:
PLANT SYSTEMS YARD FIRE HYDRANTS AND HYDRANT HOSE HOUSES TEXT 3.7.3.7 1
04/26/2006
Title:
)?LANT SYSTEMS FIRE RATED ASSEMBLIES TEXT 3.7.3.8 15 08/02/2021
Title:
PLANT SYSTEMS FIRE DETECTION INSTRUMENTATION TEXT 3.7.4 1
04/26/2006
Title:
PLANT SYSTEMS SOLID RADWASTE SYSTEM Page 4 of 15 Report Date: 03/31/23
SSES MANUAL Manual Name:
TRM2
.'tanual
Title:
TECHNICAL REQUIREMENTS MANUAL UNIT 2 TEXT 3.7.5.l 1
03/05/2015
Title:
PLANT SYSTEMS MAIN CONDENSER OFFGAS HYDROGEN MONITOR TEXT 3.7.5.2 0
11/19/2002
Title:
PLANT SYSTEMS MAIN CONDENSER OFFGAS EXPLOSIVE GAS MIXTURE TEXT 3.7.5.3 1
04/26/2006
Title:
PLANT SYSTEMS LIQUID HOLDUP TANKS TEXT 3.7.6 3
06/04/2012
Title:
PLANT SYSTEMS ESSW PUMPHOUSE VENTILATION TEXT 3.7.7 2
09/05/2008
Title:
PLANT SYSTEMS MAIN CONDENSER OFFGAS PRETREATMENT LOGARITHMIC RADIATION MONITORING INSTRUMENTATION
.'EXT 3.7.8 9
Title:
PLANT SYSTEMS SNUBBERS 03/05/2015 TEXT 3.7.9 2
03/05/2019
Title:
PLANT SYSTEMS CONTROL STRUCTURE HVAC TEXT 3.7.10 2
04/29/2014
Title:
PLANT SYSTEMS SPENT FUEL STORAGE POOLS (SFSPS)
TEXT 3.7.11 2
11/01/2018
Title:
PLANT SYSTEMS TEXT 3.8.1 4
08/02/2021
Title:
ELECTRICAL POWER PRIMARY CONTAINMENT PENETRATION CONDUCTOR OVERCURRENT PROTECTIVE DEVICES TEXT 3.8.2.1 2
11/09/2007
Title:
ELECTRICAL POWER MOTOR OPERATED VALVES (MOV) THERMAL OVERLOAD PROTECTION CONTINUOUS TEXT 3.8.2.2 3
06/23/2021 Page 5
Title:
ELECTRICAL POWER MOTOR OPERATED VALVES (MOV) THERMAL OVERLOAD PROTECTION AUTOMATIC of 15 Report Date: 03/31/23
SSES MANUAL L
Manual Name:
TRM2
!anual
Title:
TECHNICAL REQUIREMENTS MANUAL UNIT 2 TEXT 3.8.3 4
01/28/2020
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 1
11/14/2013
Title:
ELECTRICAL POWER DEGRADED VOLTAGE PROTECTION TEXT 3.8.6 3
.03/05/2019
Title:
ELECTRICAL POWER EMERGENCY SWITCHGEAR ROOM COOLING TEXT 3.8.7 3
02/25/2021
Title:
BATTERY MAINTENANCE AND MONITORING PROGRAM
'EXT 3. 9.1 0
11/19/2002
Title:
REFUELING OPERATIONS DECAY TIME TEXT 3.9.2 0
11/19/2002
Title:
REFITELING OPERATIONS COMMUNICATIONS TEXT 3.9.3 1
03/12/2019
Title:
REFITELING OPERATIONS REFITELING PLATFORM TEXT 3.10.1 1
04/26/2006
Title:
MISCELLANEOUS SEALED SOURCE CONTAMINATION TEXT 3.10.2 1
04/09/2007
Title:
MISCELLANEOUS SHOTDOWN MARGIN TEST RPS INSTRUMENTATION TEXT 3.10.3 4
10/05/2022
Title:
MISCELLANEOUS INDEPENDENT SPENT FUEL STORAGE INSTALLATION (ISFSI)
TEXT 3.10.4 2
04/17/2009
Title:
INTENTIONALLY LEFT BLANK Page 6 of 15 Report Date: 03/31/23
SSES MANUAL Manual Name:
TRM2
.lanual
Title:
TECHNICAL REQUIREMENTS MANUAL UNIT 2 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 TEXT 3. 11. 1. 4 2
10/09/2012
Title:
RADIOACTIVE EFFLUENTS LIQUID RADWASTE EFFLUENT MONITORING INSTRUMENTATION TEXT 3.11.1.5 3
03/05/2015
Title:
RADIOACTIVE EFFLUENTS RADIOACTIVE LIQUID PROCESS MONITORING INSTRUMENTATION
- EXT 3.11.2.1 4
03/12/2019
Title:
RADIOACTIVE EFFLUENTS DOSE RATE TEXT 3.11.2.2 l
04/26/2006
Title:
RADIOACTIVE EFFLUENTS DOSE -
NOBLE GASES TEXT 3.11.2.3 1
04/26/2006
Title:
RADIOACTIVE EFFLUENTS DOSE -
IODINE, TRITIUM, AND RADIONUCLIDES IN PARTICULATE FORM TEXT 3. 11. 2.4 0
11/19/2002
Title:
RADIOACTIVE EFFLUENTS GASEOUS RADWASTE TREATMENT SYSTEM TEXT 3.11.2.5 4
07/03/2013
Title:
RADIOACTIVE EFFLUENTS VENTILATION EXHAUST TREATMENT SYSTEM TEXT 3. 11. 2. 6 8
07/21/2017
Title:
RADIOACTIVE EFFLUENTS RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION TEXT 3.11.3 l
04/26/2006
Title:
RADIOACTIVE EFFLUENTS TOTAL DOSE Page 7 of 15 Report Date: 03/31/23
SSES MANUAL Manual Name:
TRM2 tanual
Title:
TECHNICAL REQUIREMENTS MANUAL UNIT 2 TEXT 3. 11. 4. 1 5
01/03/2022
Title:
RADIOACTIVE EFFLUENTS MONITORING PROGRAM TEXT 3.11.4.2 2
04/26/2006
/
Title:
RADIOACTIVE EFFLUENTS LAND USE CENSUS TEXT 3.11.4.3 1
04/26/2006
Title:
RADIOACTIVE EFFLUENTS INTERLABORATORY COMPARISON PROGRAM TEXT 3. 12. 1' 0
11/19/2002
Title:
LOADS CONTROL PROGRAM CRANE TRAVEL-SPENT FUEL STORAGE POOL TEXT 3.12.2 4
04/17/2008
Title:
LOADS CONTROL PROGRAM HEAVY LOADS REQUIREMENTS
'EXT 3.12.3 0
11/19/2002
Title:
LOADS CONTROL PROGRAM LIGHT LOADS REQUIREMENTS TEXT 4.1 0
09/27/2003
Title:
ADMINISTRATIVE CONTROLS ORGANIZATION TEXT 4.2 1
01/03/2019
Title:
ADMINISTRATIVE CONTROLS REPORTABLE EVENT ACTION TEXT 4.3 1
01/03/2019
Title:
ADMINISTRATIVE CONTROLS SAFETY LIMIT VIOLATION TEXT 4.4 1
12/18/2008
Title:
ADMINISTRATIVE CONTROLS PROCEDURES & PROGRAMS TEXT 4.5 1
07/01/2021
Title:
ADMINISTRATIVE CONTROLS REPORTING REQUIREMENTS TEXT 4.6 0
09/27/2003
Title:
ADMINISTRATIVE CONTROLS RADIATION PROTECTION PROGRAM Page 8 of 15 Report Date: 03/31/23
SSES MANUAL Manual Name; TRM2 tanual
Title:
TECHNICAL REQUIREMENTS MANUAL UNIT 2 TEXT 4.7 1
12/13/2022 Title; ADMINISTRATIVE CONTROLS TRAINING TEXT B3.0 7
03/18/2021
Title:
APPLICABILITY BASES TECHNICAL REQUIREMENT FOR OPERATION (TRO) APPLICABILITY TEXT B3.l.l 2
04/29/2014
Title:
REACTIVITY CONTROL SYSTEM BABES ANTICIPATED TRANSIENT WITHOUT SCRAM ALTERNATE ROD INJECTION (ATWS-ARI) INSTRUMENTATION TEXT B3.1.2 0
11/19/2002
Title:
REACTIVITY CONTROL SYSTEM BABES CONTROL ROD DRIVE (CRD) HOUSING SUPPORT TEXT B3.1.3 4
12/18/2017
Title:
REACTIVITY CONTROL SYSTEM BABES CONTROL ROD BLOCK INSTRUMENTATION
.'EXT B3.1.4 1
10/12/2020
Title:
REACTIVITY CONTROL SYSTEM BABES CONTROL ROD SCRAM ACCUMULATORS INSTRUMENTATION AND CHECK VALVE TEXT B3.2.1 0
11/19/2002
Title:
CORE OPERATING LIMITS BABES CORE OPERATING LIMITS REPORT (COLR)
TEXT B3.3.l 1
01/31/2014 Title; INSTRUMENTATION BASES RADIATION MONITORING INSTRUMENTATION TEXT B3.3.2 2
03/31/2011 Title; INSTRUMENTATION BASES SEISMIC MONITORING INSTRUMENTATION TEXT B3.3.3 2
11/09/2007
Title:
INSTRUMENTATION BASES METEOROLOGICAL MONITORING INSTRUMENTATION TEXT B3.3.4 7
07/21/2017
Title:
INSTRUMENTATION BASES TRM POST ACCIDENT MONITORING (PAM) INSTRUMENTATION TEXT B3.3.5 2
11/09/2007
Title:
INSTRUMENTATION BASES THIS PAGE INTENTIONALLY LEFT BLANK Page 9 of 15 Report Date: 03/31/23
SSES MANUAL Manual Name:
TRM2 Ianual
Title:
TECHNICAL REQUIREMENTS MANUAL UNIT 2 TEXT B3.3.6 6
03/05/2019
Title:
INSTRUMENTATION BASES TRM ISOLATION ACTUATION INSTRUMENTATION TEXT B3.3.7 4
01/17/2022
Title:
INSTRUMENTATION BASES MAIN TURBINE OVERSPEBD PROTECTION SYSTEM TEXT B3.3.8 1
10/22/2003
Title:
INTENTIONALLY BLANK TEXT B3.3.9 4
01/03/2019
Title:
INSTRUMENTATION BASES LPRM UPSCALE ALARM INSTRUMENTATION TEXT B3.3.10 3
02/22/2012
Title:
INSTRUMENTATION BASES REACTOR RECIRCULATION PUMP MG SET STOPS
'EXT B3. 3. 11 1
10/22/2003
Title:
INSTRUMENTATION BASES MVP ISOLATION INSTRUMENTATION TEXT B3.3.12 1
04/02/2019
Title:
WATER MONITORING INSTRUMENTATION TEXT B3.4.l 0
11/19/2002
Title:
REACTOR COOLANT SYSTEM BASES REACTOR COOLANT SYSTEM CHEMISTRY TEXT B3.4.2 1
04/16/2009
Title:
REACTOR COOLANT SYSTEM BASES STRUCTURAL INTEGRITY TEXT B3.4.3 1
11/09/2007
Title:
REACTOR COOLANT SYSTEM BASES HIGH/LOW PRESSURE INTERFACE LEAKAGE MONITOR TEXT B3.4.4 1
01/03/2019
Title:
REACTOR COOLANT SYSTEM BASES REACTOR RECIRCULATION FLOW AND ROD LINE LIMIT TEXT B3.4.5 0
11/19/2002
Title:
REACTOR COOLANT SYSTEM BASES REACTOR VESSEL MATERIALS Page 10 of 15 Report Date: 03/31/23
SSES MANUAL Manual Name:
TRM2
.!a.nual
Title:
TECHNICAL REQUIREMENTS MANUAL UNIT 2 TEXT B3.4.6 2
01/03/2019
Title:
REACTOR RECIRCULATION SINGLE LOOP OPERATION SLO FLOW RATE RESTRICTION TEXT B3.5.1 2
03/17/2020
Title:
ECCS RPV WATER INVENTORY CONTROL AND RCIC SYSTEM ADS MANUAL INHIBIT TEXT B3.5.2 2
03/05/2019
Title:
ECCS RPV WATER INVENTORY CONTROL AND RCIC SYSTEM ECCS RPV WATER INVENTORY CONTROL AND RCIC MONITORING INSTRUMENTATION TEXT B3.5.3
- 2.
03/05/2019
Title:
ECCS RPV WATER INVENTORY CONTROL AND RCIC SYSTEM LONG TERM NITROGEN SUPPLY TO ADS TEXT B3.6.1 0
11/19/2002
Title:
CONTAINMENT BASES VENTING OR PURGING EXT 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.l 4
02/16/2017 Title1 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 11 of 15 Report Date: 03/31/23
SSES MANUAL Manual Name:
TRM2 lanual
Title:
TECHNICAL REQUIREMEN'I'S MANUAL UNIT 2 TEXT B3.7.3.3 0
11/19/2002
Title:
PLANT SYSTEMS BASES CO2 SYSTEMS TEXT B3.7.3.4 3
06/19/2019
Title:
PLANT SYSTEMS BASES HALON SYSTEMS TEXT B3.7.3.5 1
04/26/2006
Title:
PLANT SYSTEMS BASES FIRE HOSE STATIONS TEXT B3.7.3.6 1
04/26/2006
Title:
PLANT SYSTEMS BASES YARD FIRE HYDRANTS AND HYDRANT HOSE HOUSES TEXT B3.7.3.7 0
11/19/2002
Title:
PLANT SYSTEMS BASES FIRE RATED ASSEMBLIES
.'EXT B3. 7. 3
- 8 3
09/27/2012
Title:
PLANT SYSTEMS BASES FIRE DETECTION INSTRUMENTATION TEXT B3.7.4 0
11/19/2002
Title:
PLANT SYSTEMS BASES SOLID RADWASTE SYSTEM TEXT B3.7.5.1 0
11/19/2002
Title:
PLANT SYSTEMS BASES MAIN CONDENSER OFFGAS HYDROGEN MONITOR TEXT B3.7.5.2 0
11/19/2002
Title:
PLANT SYSTEMS BASES MAIN CONDENSER OFFGAS EXPLOSIVE GAS MIXTURE TEXT B3.7.5.3 0
11/19/2002
Title:
PLANT SYSTJ!:MB BASES LIQUID HOLDUP TANKS TEXT B3.7.6 4
06/04/2013
Title:
PLANT SYSTEMS BASES ESSW PUMPHOUSE VENTILATION TEXT B3.7.7 2
01/31/2008
Title:
PLANT SYSTEMS BASES MAIN CONDENSER OFFGAS PRETREATMENT LOGARITHMIC RADIATION MONITORING INSTRUMENTATION Page 12 of 15 Report Date: 03/31/23
SSES MANUAL Manual Name:
TRM2
.tanual
Title:
TECHNICAL REQUIREMENTS MANUAL UNIT 2 TEXT B3.7.8 4
01/31/2014
Title:
PLANT SYSTEMS BASES SNUBBERS TEXT B3.7.9 3
03/05/2019
Title:
PLANT SYSTEMS BASES CONTROL STRUCTURE HVAC TEXT B3.7.10 1
12/14/2004
Title:
PLANT SYSTEMS BASES SPENT FUEL STORAGE POOLS TEXT B3.7.ll 3
11/01/2018
Title:
STRUCTURAL INTEGRITY TEXT B3.8.1 2
03/10/2010
Title:
ELECTRICAL POWER BASES PRIMARY CONTAINMENT PENETRATION CONDUCTOR OVERCURRENT PROTECTIVE DEVICES
- EXT B3.8.2.l 0
11/19/2002
Title:
ELECTRICAL POWER BASES MOTOR OPERATED VALVES (MOV) THERMAL OVERLOAD PROTECTION CONTINUOUS TEXT B3.8.2.2 2
06/23/2021
Title:
ELECTRICAL POWER BASES MOTOR OPERATED VALVES (MOV) THERMAL OVERLOAD PROTECTION -
AUTOMATIC TEXT B3.8.3 0
11/19/2002
Title:
ELECTRICAL POWER BASES DIESEL GENERATOR (DG) MAINTENANCE ACTIVITIES TEXT B3.8.4 0
11/19/2002
Title:
ELECTRICAL POWER BASES 24 VDC ELECTRICAL POWER SUBSYSTEM TEXT B3.8.5 1
11/14/2013
Title:
ELECTRICAL POWER BASES DEGRADED VOLTAGE PROTECTION TEXT B3.8.6 4
03/05/2019
Title:
ELECTRICAL POWER BASES EMERGENCY SWITCHGEAR ROOM COOLING TEXT B3.8.7 3
02/25/2021
Title:
BATTERY MAINTENANCE AND MONITORING PROGRAM Page 13 of 15 Report Date: 03/31/23
SSES-MANUAL Manual Nam.a:
TRM2
~ual
Title:
TECHNICAL REQUIREMENTS MANUAL UNIT 2 r
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 1
03/12/2019
Title:
REFUELING OPERATIONS BASES REFUELING PLATFORM TEXT B3.10.1 0
11/19/2002
Title:
MISCELLANEOUS BASES SEALED SOURCE CONTAMINATION TEXT B3.10.2 1
04/10/2007
Title:
MISCELLANEOUS BASES SHUTDOWN MARGIN TEST RPS INSTRUMENTATION
- EXT B3. 10. 3 3
10/05/2022
Title:
MISCELLANEOUS BASES INDEPENDENT SPENT FUEL STORAGE INSTALLATION (ISFSI)
TEXT B3. 11. 1. 1 1
05/10/2016
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 TEXT B3.11.1.4 0
11/19/2002
Title:
RADIOACTIVE EFFLUENTS BASES LIQUID RADWASTE EFFLUENT MONITORING INSTRUMENTATION TEXT B3.ll.l.5 0
11/19/2002
Title:
RADIOACTIVE EFFLUENTS BASES RADIOACTIVE LIQUID PROCESS MONITORING INSTRUMENTATION TEXT B3.11. 2.1 1
12/14/2004
Title:
RADIOACTIVE EFFLUENTS BASES DOSE RATE Page 14 of 15 Report Date: 03/31/23
SSES MANUAL Manual Name:
TRM2
.1ao.ual
Title:
TECHNICAL REQUIREMENTS MANUAL UNIT 2 TEXT B3.ll.2.2 0
11/19/2002
Title:
RADIOACTIVE EFFLUENTS BASES DOSE -
NOBLE GASES TEXT B3.ll.2.3 0
11/19/2002
Title:
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IODINE, TRITIUM, AND RADIONUCLIDES IN PARTICULATES FORM TEXT B3. 11. 2. 4 0
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RADIOACTIVE EFFLUENTS BASES RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION
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Title:
RADIOACTIVE EFFLUENTS BASES MONITORING PROGRAM TEXT B3.ll.4.2 0
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Title:
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LOADS CONTROL PROGRAM BASES LIGHT LOADS REQUIREMENTS Page 15 of 15 Report Date: 03/31/23
Rev.20 3.2 Core Operating Limits Report (COLR) 3.2.1 Core Operating Limits Report (COLR)
COLR 3.2.1 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 A.
Core Operating Limits not met.
REQUIRED ACTION A.1 Perform action(s) described in referenced Technical Specification.
TECHNICAL REQUIREMENT SURVEILLANCE SURVEILLANCE
NOTE-------------
No associated Surveillances. Surveillances are implemented in the applicable Technical Specifications.
SUSQUEHANNA - UNIT 2 TRM / 3.2-1 COMPLETION TIME Specified in referenced Technical Specifications.
FREQUENCY N/A
Rev.20 Susquehanna SES
. Unit 2 Cycle 22 PL-NF-23-002 Rev.a Page 1 of 72 CORE OP.ERA TING LIMITS
- REPORT SUSQUEHANNA UNIT 2 TRM / 3.2-2 Nuclear Fuels Engineering March 2023
REV AFFECTED NO.
SECTIONS Rev.20 PL-NF-23-002 Rev.0 Page 2 of 72 CORE OPERATING LIMITS REPORT REVISION DESCRIPTION INDEX DESCRIPTION / PURPOSE OF REVISION 0
ALL Issuance of this COLR is in support of Unit 2 Cycle 22 operation.
FORM NFP-QA-008-2, Rev. 2 SUSQUEHANNA UNIT 2 TRM / 3.2-3
1.0 2.0 3.0 4.0 5.0 6.0 7.0 Rev.20 SUSQUEHANNA STEAM ELECTRIC STATION Unit 2 Cycle 22 CORE OPERATING LIMITS REPORT Table of Contents PL-NF-23-002 Rev. O Page 3 of 72 INTRODUCTION......................................................................................................... 4 DEFINITIONS...............*.................................................................................*............ 5 SHUIDOWN MARGIN................................................................................................ 6 AVERAGE PLANAR LINEAR HEAT GENERATION RATE {APLHGR)....................... 7 MINIMUM CRITICAL POWER RATIO (MCPR)........................................................... 10 LINEAR HEAT GENERATION RATE (LHGR)............................................................. 28 ROD BLOCK MONITOR (RBM) SETPOINTS AND OPERABILITY REQUIREMENTS....................................................................................................... 47 8.0 RECIRCULATION LOOPS-SINGLE LOOP OPERATION.........................................49 9.0 POWER/ FLOW MAP....................................................................,..........................*.. 68 10.0 OPRM SETPOINTS.................................................................................................... 70
11.0 REFERENCES
............................................................................................................ 71 SUSQUEHANNA UNIT 2 TRM / 3.2-4
Rev.20
1.0 INTRODUCTION
PL-NF-23-002 Rev.a Page 4 of 72 This CORE OPERATING LIMITS REPORT for Susquehanna Unit 2 Cycle 22 ls 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 setpolnts, and OPRM setpolnts presented herein were developed using NRG-approved methods and are established such that all applicable limits of the plant safety analysis are met.
SUSQUEHANNA UNIT 2 TRM / 3.2-5
Rev.20 2.0 DEFINITIONS PL-NF-23-002 Rev. 0 Page 5 of 72 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 LHGRFAC is a multiplier applied to the LHGR limit when operating at less than 108 Mlbm/hr core flow., The LHGRFAC multiplier protects against both fuel centerline melting and cladding strain during anticipated system transients initiated from core flows less than 108 Mlbm/hr.
2.5 LHGRFACp is a multiplier applied to the LHGR limit when operating at less than RATED THERMAL POWER. The LHGRFACp multiplier protects against both fuel centerline melting and cladding strain during anticipated system transients Initiated from partial power conditions.
- 2. 7 MCPRoo.0% is the cycle-specific safety limit MCPR that ensures at least 99.9% of fuel rods are not susceptible to boiling transition.
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 MAPRA T is the ratio of the maximum APLHGR calculated by the core monitoring system for each fuel bundle dMded by the APLHGR limit for the applicable fuel bundle type.
2.8 OPRM is the Oscillation Power Range Monitor. The Oscillation Power Range Monitor (OPRM) will reliably detect and suppress anticipated stability related power oscillations while providing a high degree of confidence that the MCPRw 9% 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.
2.1 O Sp is the OPRM trip setpoint for the peak to average OPRM signal.
2.11 Fp is the core flow, in Mlbm / hr, below which the OPRM RPS trip is activated.
SUSQUEHANNA UNIT 2 TRM / 3.2-6
Rev.20 PL-NF-23-002 Rev. O Page 6 of 72 3.0 SHUTDOWN MARGIN 3.1 References 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 analytlcally detennlned 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 bumup, Beginning of Cycle (BOC) SHUTDOWN MARGIN (SDM) tests must also account for changes in core reactivity during the cycle. Therefore, the SDM measured at BOC must be equal to or greater than the applicable requirement from either 3.2.a or 3.2.b plus an adder, "R". The adder, "R", ls the difference between the calculated value of maximum core reactivity (that is, minimum SDM) during the operating cycle and the calculated BOC core reactivity. tf the value of *R" is zero (that Is, BOC is the most reactive point in the cycle) no correctlon 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
4.0 Rev.20 PL-NF-23-002 Rev. 0 Page 7 of 72 AVERAGE PLANAR LINEAR HEAT GENERATION RA TE (APLHGR) 4.1 References Technical Specification 3.2.1 4.2 Description The APLHGRs for ATRIUM'-10 fuel shall not exceed the limit shown in Figure 4.2-1A. The APLHGRs for ATRIUM' 11 fuel shall not exceed the limit shown In Figure 4.2-1B.
The APLHGR limits in Figures 4.2-1A and 4.2-18 are valid in Two Loop operation for Main Turbine Bypass Operable and Inoperable, EOC-RPT Operable and Inoperable, Backup Pressure Regulator Operable and Inoperable, and with one Turbine Stop Valve (TSV) or Turbine Control Valve (TCV) closed. The APLHGR limits for Single Loop operation are provided in Section 8.0.
SUSQUEHANNA UNIT 2 TRM / 3.2-8
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Rev.20 PL-NF-23-002 Rev.a Page 10 of 72 5.0 MINIMUM CRITICAL POWER RA TIO (MCPR) 5.1 References Technical Specification 3.2.2, 3.3.4.1, 3.7.6, and 3.7.8 Technical Requirements Manual 3.3.7 5.2 Description For Unit 2 Cycle 22, the MCPRw.9% Safety Limit Is 1.07 for Two Loop operation and 1.09 for Single Loop operation.
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'-10 and ATRIUM' 11) shall be the greater of the Flow-Dependent or the Power-Dependent MCPR, depending on the applicable equipment operability status.
a)
Main Turbine Bypass / EOC-RPT / Backup Pressure Regulator Operable Figure 5.2-1:
Figure 5.2-2:
Flow-Dependent MCPR value determined from BOC to EOC for ATRIUMTM.1Q and ATRIUM' 11 Fuel Power-Dependent MCPR value determined from BOC to EOC for ATRIUM'-10 and ATRIUM' 11 Fuel b)
Main Turbine Bypass Inoperable Figure 5.2-3:
Figure 5.2-4:
Flow-Dependent MCPR value determined from BOC to EOC for ATRIUM'-10 and ATRIUM' 11 Fuel Power-Dependent MCPR value determined from BOC to EOC for ATRIUM'-10 and ATRIUM' 11 Fuel c)
EOC-RPT Inoperable Figure 5.2-5:
Figure 5.2-6:
Flow-Dependent MCPR value determined from BOC to EOC for ATRIUM'-10 and ATRIUM' 11 Fuel Power-Dependent MCPR value determined from BOC to EOC for ATRIUM'-10 and ATRIUM' 11 Fuel d)
Backup Pressure Regulator Inoperable Figure 5.2-7:
Figure 5.2-8:
Flow-Dependent MCPR value determined from BOC to EOC for ATRIUM'-10 and ATRIUM' 11 Fuel Power Dependent MCPR value determined from BOC to EOC for ATRIUM'-10 and ATRIUM' 11 Fuel e)
One Turbine Stop Valve (TSV) or Turbine Control ValVe (TCV) Closed SUSQUEHANNA UNIT 2 TRM / 3.2-11
Rev.20 PL-NF-23-002 Rev.0 Page 11 of 72 Figure 5.2-9:
Flow-Dependent MGPR value detennined from BOC to EOG for ATRIUM'-10 and ATRIUM' 11 Fuel Figure 5.2-10:
Power-Dependent MCPR value detennined from BOC to EOG for ATRIUM'-10 and ATRIUM' 11 Fuel The MGPR limits in Figures 5.2-1 through 5.2-10 are valid fot Two Loop operation and are applicable to both ATRIUM'-10 and ATRIUM' 11 Fuel.
The MCPR limits for Single Loop operation are provided in Section 8.0.
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 pennitted. 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 / 3.2-12
Rev.20 PL-NF-23-002 Rev. O Page 12 of 72 Main Turbine Bypass / EOC-RPT /
Backup Pressure Regulator Operable SUSQUEHANNA UNIT 2 TRM / 3.2-13
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1.6 1.5 1.4 1.3 1.2 7 30.0, 2.06 I 140.0, 1.861 140.1, 1.41 I
~
SSES UNIT 2 CYCLE 22 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 I
I I
I USED IN DETERMINING MFLCPR A
B
- a Cl) <
I\\)
0 I
REFERENCE:
T.S. 3.2.2 30 40 50 60 70 80 90 100 Total Core Flow (MLB/HR)
MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW MAIN TURBINE BYPASS/ EOC-RPT / BACKUP PRESSURE REGULATOR OPERABLE TWO LOOP OPERATION (BOC TO EOC)
ATRJUM'-10 AND ATRIUM' 11 FUEL FIGURE 5.2-1
-1108.0, 1.221 110
en 4.0 C en D
C 3.8 rn
- r:
~
3.6 z
)>
C 3.4 z
-I I'\\.)
3.2
= 3.0 E
- i Cl 2.8 C
E 2.6
-I CD
- a C.
s::
0 0::
2.4 D.
w 0
~
- i I......
2.2 01 2.0 1.8 1.6 1.4 1.2 CURVE A:
26, 2.61 23, 2.84
~
CURVEB:
26, 2.61 23, 2.84 CURVEC:
26, 2.59 23, 2.84 SSES UNIT 2 CYCLE 22 I
I I
T T
I LEGEND CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME I-CURVE C: CORE POWER :S 26% AND CORE FLOW :S 50 MLBM/HR ALL SCRAM INSERTION TIMES
" A SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE...
\\.
PER SR 3.7.6.1 AND 3.7.6.2 B
C '
I I
126.01, 2.41 USED IN DETERMINING MFLCPR r
I 1........
140, 2.011 lso, 2.011 1 26.01, 2.23 1
- 60, 1.86:
A-H 10, 1.79 ~
- 40, 1.90:
............._ ----- ~
1 so, 1.73:
I 50, 1.89 1
~-
- 90, 1.62 I-
- so, 1.71:
B I
I I 70, 1,65 I
- a CD <
I'\\.)
0
~
REFERENCE:
T.S. 3.2.2
~
I I
7 80, 1.57, l 90, 1.52 I 1100, 1.561 1100, 1.42 I 10 20 I
30 40 50 60 70 80 90 Core Power(% RATED)
MCPR OPERATING LIMIT VERSUS CORE POWER MAIN TURBINE BYPASS/ EOC-RPT / BACKUP PRESSURE REGULATOR OPERABLE TWO LOOP OPERATION (BOC TO EOC)
ATRIUM'-10 AND ATRIUM' 11 FUEL FIGURE 5.2-2 100
Rev.20 Main Turbine Bypass Inoperable SUSQUEHANNA UNIT 2 TRM / 3.2-16 PL-NF-23--002 Rev.O Page 15 of 72
C/)
2.5 C
C/)
D C
2.4 m
- c
~
2.3 z
)>
C 2.2 z
-I I\\:)
2.1
=
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- i CD C
1.9
-I g_
- 0 0
1.8 s:
0::
D.
uJ u
N
~ 1.7 I......
-...J 1.6 1.5 1.4 1.3 1.2 SSES UNIT 2 CYCLE 22 LEGEND CURVE A:. MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME I
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 H30, 2.osi I
~
USED IN DETERMINING MFLCPR
- 40, 1.86:
- 40.1, 1.56:
A B
I
REFERENCE:
T.S. 3.7.6 and 3.2.2 l 108, 1.341 30 40 50 60 70 80 90 Total Core Flow (MLB/HR)
MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW MAIN TURBINE BYPASS INOPERABLE TWO LOOP OPERATION (BOC TO EOC)
ATRIUMTM-10AND ATRIUMT11 11 FUEL FIGURE. 5.2-3 100 110
(J) 4.3 C
(J)
D 4.1 C m I )>
3.9 z z
)>
C 3.7 z
=i 3.5 N
3.3
=
E 3.1
- J DI C
~ 2.9
~
- a Q. 2.7 s
- :
0 0::
- a.
(.,)
(.) 2.5 i,.,
==
I......
- 0) 2.3 2.1 1.9 1.7 1.5 1.3 CURVE A:
26, 3.16 23, 3.51 CURVE B:
26, 3.16 A
23, 3.51
\\
\\
B '
CURVEC:
26, 2.59 23, 2.84
'\\
\\
CURVED: -c 28, 2.59
\\
23, 2.84 D
- 26.01, 2.44:
- 26.01, 2.25:
SSES UNIT 2 CYCLE 22 LEGEND CURVE A-. MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME CURVE C: CORE POWER s 26% AND CORE FLOW s 50 MLBM/HR MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME --
CURVE D: CORE POWER s 26% AND CORE FLOWS 50 MLBM/HR REALISTIC AVERAGE SCRAM INSERTION TIME I
SAFETY ANALYSES ASSUME THAT TWO OR MORE BYPASS VALVES ARE i-INOPERABLE PER SR 3.7.6.1 OR 3.7.6.2 USED IN DETERMINING MFLCPR
~
a 140, 2.01 i 150, 2.07 I
! 60, 1.86 A
~ 70, 1.82 i
--i---.......
180,1.741
- 40, 1.90 I
!90, 1.69~
I 150, 1.90 I
- 60, 1.71 !
B_
f N
0
REFERENCE:
T.S. 3.7.6 and 3.2.21
~70, 1.66 I 180, 1.58 I I eo, 1.ss I 1100, 1.s9 I 1100, 1.s5 I I
10 20 30 40 50 60 70 Core Power(% RATED)
MCPR OPERATING LIMIT VERSUS CORE POWER MAIN TURBINE BYPASS INOPERABLE TWO LOOP OPERATION (BOC TO EOC)
ATRIUMTll-10 AND ATRIUM' 11 FUEL FIGURE 5.2-4 80 90 100
SUSQUEHANNA UNIT 2 Rev.20 EOC-RPT Inoperable TRM / 3.2-19 PL-NF-23-002 Rev. 0 Page 18 of 72
(/)
2.6 C
(/)
0 C
2.5 m
- c 2.4 z z
)>
C 2.3 z
--l N
2.2
==
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- J C) 2.0 C
~ 1.9
--l g_
- o 0
s: --
~ 1.8 ll.
c,J 0
i-,)
- i:
I N 1.7 0
1.6 1.5 1.4 1.3 1.2 SSES UNIT 2 CYCLE 22 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 I 30.0, 2.061 K
USED IN DETERMINING MFLCPR 140,0, 1.86 I 140.1, 1.411
~
A B
1
REFERENCE:
T.S. 3.3.4.1 and 3.2.2 :
30 40 50 60 70 80 90 Total Core Flow (MLB/HR)
MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW EOC-RPT INOPERABLE TWO LOOP OPERATION (BOC TO EOC)
ATRJUM'-10 AND ATRIUMTII 11 FUEL FIGURE 5.2-5 100 1--
-L
- o CD <
N 0
I108.0, 1.221 110
""CJ
""CJ 0l r
CC I
CD z
71 (0 ;o I\\)
a~6
--..i*
0 NOI\\J
en 4.3 C en 0
4.1 C m I )>
3.9 z z C
3.7 z
-I 3.5 N
3.3
~
E 3.1
- J C)
C l 2.9
-I
- a 0
2.7
~
ix:
D.
c,J 0
2.5 N
- e N
2.3 2.1 1.9 1.7 1.5 1.3 SSES UNIT 2 CYCLE 22 LEGEND CURVE A". MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME CURVE A:.
CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME 26, 2.61 23, 2.84 CURVE C: CORE POWER :S: 26% AND CORE FLOW :s: 50 MLBM/HR MAXIMUM AL[OWABLE AVERAGE SCRAM INSERTION TIME CURVEB:
CURVE D: CORE POWER :s: 26% AND CORE FLOW :S: 50 MLBM/HR 26, 2.61 REALISTIC AVERAGE SCRAM INSERTION TIME 23, 2.84 SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE CURVEC:
PER SR 3.7.6.1 AND 3.7.6.2 26, 2.59
'-A 23, 2.84 c-\\CI J
t USED IN DETERMINING MFLCPR CURVED: ___ o_
H2s.01, 2.41 i 26, 2.59 23, 2.84 140, 2.121150, 2.121 I
1""'-
i 60, 1.99 1 26.01, 2.23 1 A_
H 10, 1.00 ~
I so, 1.741 190, 1.73~
- 4o, 1.90:
I 1-.............
-.... ~---------------
150, 1.89 I I 60, 1.72 B_ LJ10, 1.61L LJ I
REFERENCE:
T.S. 3.3.4.1 and 3.2.2 I 180, 1.60 I 190, 1.571 I
I I
- a CD N
0 1100, 1.731 1100, 1.56 I 10 20 30 40 50 60 70 80 90 100 Core Power(% RATED)
MCPR OPERATING LIMIT VERSUS CORE POWER EOC-RPT INOPERABLE TWO LOOP OPERATION (BOC TO EOC)
ATRIUM'-10 AND ATRIUM' 11 FUEL FIGURE 5.2-6
Rev.20 PL-NF-23-002 Rev. 0 Page 21 of 72 Backup Pressure Regulator Inoperable SUSQUEHANNA UNIT 2 TRM / 3.2-22
en 2.6 C en 0
C 2.5 m
I )>
2.4 z z C
2.3 z
-I N
2.2
~ 2.1 E
- j CJJ 2.0 C !
1.9
-I g_
- 0 0
s:: --
~ 1.8 Cl.
w (J
N r{.,
1.7 w
1.6 1.5 1.4 1.3 1.2 SSES UNIT 2 CYCLE 22 I
I I
LEGEND CUR~ k. MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME I
I I
SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES H 30.o, 2.0&:
ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2
~
I I
I I
USED IN 'DETERMINING MFLCPR I
- 40.0, 1.86 1 140.1, 1.411 A
B t
REFERENCE:
T.S. 3.7.8 and 3.2.2:
30 40 50,
60 70 80 90 Total Core Flow (MLB/HR)
MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW BACKUP PRESSURE REGULA TOR INOPERABLE TWO LOOP OPERATION (BOC TO EOC)
ATRIUM'-10 AND ATRIUMTM 11 FUEL FIGURE 5.2-7 100 i
- 0
~
N 0
- I 108.0, 1.221
, 110
'1J
'1J Ill r;-
cg z
N 7'
I\\.) :::0 I\\.)
0 CD W
-<6 0
I\\) 0 I\\.)
(/l 4.0 C
(/l 0
C 3.8 m
- r:
~
3.6 z
C 3.4 z
-I N
3.2
= 3.0 E
- J 01 2.8 C ! 2.6 CD
- o Cl.
0 s:
~
ll.
2.4 w
0 N
- IE
~
2.2
.i:,.
2.0 1.8 1.6 1.4 1.2 CURVE A:.
26, 2.61 23, 2.84 CURVE B:
26, 2.61 23, 2.84
" A
\\.
'"CURVEC:
B
""26, 2.59
-c 23, 2.84 j 26.01, 2.411
~......
- 26.01, 2.23 : '--
I SSES UNIT 2 CYCLE 22 I
I I
I LEGEND CURVE A:. MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME
~
CURVE C: CORE POWERS 26% AND CORE FLOWS 50 MLBM/HR ALL SCRAM INSERTION TIMES
~
SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES
~
ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 I
I I
I I
USED IN DETERMINING MFLCPR 140, 2.01i
'ISO, 2.071
- 60, 1.86:
A rl 70, 1.79:
40, 1.97 I
~
150, 1.93 I
~------
- so, 1.73:
~ '--------. ~-
- oo, 1.621-160, 1,831 B
~-----
rl 70, 1.65:
- o CD N
0
REFERENCE:
T.S. 3.7.8 and 3.2.21 ISO, 1.571 190, 1.521 1100. 1.ss I 1100, 1.42!
10 20 30 40 50 60 70 Core Power(% RATED)
NICPR OPERATING LIMIT VERSUS CORE POWER BACKUP PRESSURE REGULA TOR INOPERABLE TWO LOOP OPERATION (BOC TO EOC)
ATRIUM'-10 AND ATRIUMTM 11 FUEL FIGURE 5.2-8 80 90 100
Rev.20 One TSV or TCV Closed SUSQUEHANNA UNIT 2 TRM / 3.2-25 PL-NF-23-002 Rev. 0 Page 24 of 72
2.6 en C
2.5 en D
C m 2.4 I )>
z z 2.3
)>
C z 2.2
-I N
2.1
- t::
E 2.0
- i CS)
C 1.9 E
CD
-I C.
- o 0
1.8 s;:
D::
ll.
(,J
(.)
1.7 i-.,
- i:
I N
- 0) 1.6 1.5 1.4 1.3 1.2 SSES U.2 CYCLE 22
, LEGEND CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME I
I H30.o, 2.16:
SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES
~
ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 I
USED IN DETERMINING MFLCPR 140.0, 1.941 I
140.1, 1.591 A
B H
REFERENCE:
T.S. 3.2.2 and TRM 3.3.71 30 40 50 60 70
, 80 90 Total Core Flow (MLB/HR)
MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW ONE TSV OR TCV CLOSED*
TWO LOOP OPERATION (BOC TO EOC)
ATRIUM'-10 AND ATRIUM' 11 FUEL FIGURE 5.2-9 100
- o CD <
N 0
-I108.0, 1.371 110
en 4.0 C en 0
C 3.8 m
I
)>
3.6 z z
)>
C 3.4 z
N 3.2
- t::
3.0 E
- J Cl 2.8 C
I!
2.6 CD
- a
- 0.
~
0 0::
2.4 CL w
0 N
- E I N 2.2
-...J 2.0 1.8 1.6 1.4 1.2 SSES UNIT 2 CYCLE 22 I
I I
I' LEGEND CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME CURVE A:.
26, 2.61 CURVE C: CORE POWER s 26% AND CORE FLOWS: 50 MLBMiHR 23, 2.84 ALL SCRAM INSERTION TIMES CURVE B:
I I
I 26, 2.61 23, 2.84 A
SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2
~, e-CURVE C:
I
~
I
- -C I
26, 2.59 126.01, 2.41HUSED IN DETERMINING MFLCPR
~
23, 2.84
- 40, 2.07 A-.so, 2.01:
I............
lo,,._
26.01, 2.23,
- so, 1.86:
I 70, 1.79 I
- 40,1.90 B
I 75, 1.76 I
- 50, 1.89: ----.......
I
- 60, 1.11:
- 15, 1.61 I 70, 1.65:
7
REFERENCE:
T.S. 3.2.2 and TRM 3.3.71 10 20 30 40 50 Core Power(% RATED)
MCPR OPERATING LIMIT VERSUS CORE POWER ONE TSV OR TCV CLOSED TWO LOOP OPERATION (BOC TO EOC)
ATRIUMTU..1 O AND ATRIUM' 11 FUEL FIGURE 5.2-10 60 70 80
- a (tl <
N 0
Rev.20 Table 5.3-1 PL-NF-23-002 Rev.a Page 27 of 72 Average Scram Time Fractiol'.l Table For Use With Scram Time Dependent MCPR Operating Limits Control Rod Average Scram Time to Position (seconds)
Posltlon 45 0.470 0.520 39 0.630 0.860 25 1.500 1.910 5
2~700 3.440 Average Scram Reallstlc Ma:xlrnum Insertion Time Allowable SUSQUEHANNA UNIT 2 TRM / 3.2~28
Rev.20 PL-NF-23-002 Rev.a Page 28 of 72 6.0 LINEAR HEAT GENERATION RATE (LHGR) 6.1 References Technical Specification 3.2.3, 3.3.4.1, 3.7.6, and 3.7.8 Technical Requirements Manual 3.3.7 6.2 Description The maximum LHGR for ATRIUM'-10 and ATRIUM' 11 fuel shall not exceed the LHGR limlts determined from Figure 6.2-1A and Figure 6.2-1 B, respectively.
The LHGR limits in Figures 6.2-1A and 6.2-1B are valid for Main Turbine Bypass Operable and Inoperable, EOC-RPT Operable and Inoperable, Backup Pressure Regulator Operable and Inoperable, and with one Turbine Stop Valve (TSV) or Turbine Control Valve (TCV) closed.
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 in the following figures:
a)
Main Turbine Bypass/ EOC-RPT / Backup Pressure Regulator Operable Figure 6.2-2:
Figure 6.2-3:
Flow:-Dependent LHGR Limit Multiplier for ATRIUM'-10 and ATRIUM' 11 Fuel Power-Dependent LHGR Limit Multiplier for ATRIUM'-10 and ATRIUM' 11 Fuel b)
Main Turbine Bypass Inoperable Figure 6.2-4:
Figure 6.2-5:
Flow-Dependent LHGR Limit Multiplier for ATRIUM'-10 and ATRIUM' 11 Fuel Power-Dependent LHGR Limit Multiplier for ATRIUM'-10 and ATRIUM' 11 Fuel c)
EOC-RPT Inoperable Figure 6.2-6:
Figure 6.2-7:
Flow-Dependent LHGR Limit Multiplier for ATRIUM'-10 and ATRIUM' 11 Fuel Power-Dependent LHGR Limit Multiplier for ATRIUM'-10 and ATRILJMTM 11 Fuel d)
Backup Pressure Regulator Inoperable Figure 6.2-8:
SUSQUEHANNA UNIT 2 Flow-Dependent LHGR Limit Multiplier for ATRIUM'-10 and ATRIUM' 11 Fuel TRM / 3.2-29
Figure 6.2-9:
Rev. 20 PL-NF-23-002 Rev. O Page 29 of 72 Power-Dependent LHGR Limit Multiplier for ATRIUM'-10 and ATRIUM' 11 Fuel e)
One Turbine Stop Valve {TSV) or Turbine Control Valve {TCV) Closed Figure 6.2-10:
Flow-Dependent LHGR Limit Multiplier for ATRIUM'-10 and ATRIUM' 11 Fuel Figure 6.2-11:
Power-Dependent LHGR Limit Multiplier for ATRIUM'-10 and ATRIUM' 11 Fuel The LHGR limits in Figures 6.2-1A/6.2-18 are valid for both Two Loop and Single Loop operation and are fuel type specific. The LHGR limit multipliers in Figures 6.2.2 through 6.2.11 are valid for both Two Loop and Single Loop operation and are applicable to both ATRIUM'-10 and ATRIUM' 11 Fuel.
SUSQUEHANNA UNIT 2 TRM / 3.2-30
en C en 0
C m
- c
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z z C z
-I I\\)
-I
- o s
- -
(.,,.')
rv I w SSES UNIT 2 CYCLE 22 16.0,.....-,--T-,.......,,.......,---r--,.--r--r-r--r---,---.---.--.--.--r-.,.-,--..--...--,--,.......,,--,,--,---,,--r--.---r---.---.--.....-.--.--.--.,.--.---r--1 14.0
- t::*
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- J s
=
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Cl)
'i
- c la 8.0 G)
C
- J 6.0 I
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- I *1-n:-*17*--r, **r I-I **11**r*r-,
I *1**1,*1-r*r*r1 *r-r-I I -r, -,1**rr1 -r, 71*1*- I -*r*r*1*1-*,-
I I
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l I
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0.0, 13.4 ;-+-*'--r-*r 18900, 13.4 I i-1-+-t--r**~*r
REFERENCE:
T.S. 3.2.3 I
I I I I 1'
I I
I,
1 l
I I I 1 j 1
I I I I I
-..J--1---1--.. ___.._..J __.,.. __ f, *+*-
--1--1....J... r-+-1--t--1--*-+--l.--1---+-.. --
USED IN DETERMINING FDLRX i I ! ! i ! I i I i I I
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- 1.., 1 *
- 1 * * *, 1, * * ~ 1 *
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Rev. 20 PL-NF-23-002 Rev. 0 Page47 of 72 7.0 ROD BLOCK MONITOR (RBM) SETPOINTS AND OPERABILITY REQUIREMENTS 7.1 References 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, d)
Low Power Range - Upscale, e) lntennediate Power Range - Upscale, and f)
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, EOC-RPT Operable and Inoperable, Backup Pressure Regulator Operable and Inoperable, and with one Turbine Stop Valve {TSV) or Turbine Control Valve {TCV) closed.
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 RSM 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 / 3.2-48
Rev.20 Function Low Power Range Setpoint Table 7.2-1 RBM Setpoints Intermediate Power Range Setpoint High Power Range Setpoint Low Power Range - Upscale Intermediate Power Range - Upscale High Power Range - Upscale Allowable Value<1l 28.0, 63.0 83.0 123.4 117.4 107.6 PL-NF-23-002 Rev. 0 Page 48 of 72 Nominal Trip Setpoint 24.9 61.0 81.0 123.0 117.0 107.2 (1)
Power setpoint function (Low, Intermediate, and High Power Range Setpoints) determined in percent of RATED THERMAL POWER. Upscale trip setpoint function (Low, Intermediate, and High Power Range - Upscale) determined in percent of reference level.
Table 7.2-2 RBM System Operability Requirements Thermal Power MCPR <2,3Al
(% of Rated)
~ 28 and< 90
< 1.78
~ 90 and< 95
< 1.47
~95
< 1.68
<2l Applicable to Main Turbine Bypass Operable and Inoperable, EOC-RPT Operable and Inoperable, Backup Pressure Regulator Operable and Inoperable, and one TCVffSV closed.
<3>
Applicable to both Two Loop and Single Loop Operation.
<4>
Applicable to both ATRIUM-10 and ATRIUM 11 Fuel.
SUSQUEHANNA UNIT 2 TRM / 3.,2-49
Rev.20 8.0 RECIRCULATION LOOPS - SINGLE LOOP OPERATION 8.1 References Technical Specification 3.2.1, 3.2.2, 3.3.4.1, 3.4.1, 3.7.6, and 3.7.8 Technical Requirements Manual 3.~.7 8.2 Description APLHGR PL-NF-23-002 Rev. 0 Page 49 of 72 The APLHGR limit for ATRIUMTM.1Q fuel shall be equal to the APLHGR Limit from Figure 8.2-1A. The APLHGR limit for ATRIUM' 11 fuel shall be equal to the APLHGR Limit from Figure 8.2-1 B.
The APLHGR limits In Figures 8.2-1A and 8.2-1 B are valid in Single Loop operation for Main Turbine Bypass Operable and Inoperable, EOC-RPT Operable and Inoperable, Backup Pressure Regulator Operable and Inoperable, and with one Turbine Stop Valve {TSV) or Turbine Control Valve {TCV) closed.
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'-10 and ATRIUM' 11) shall be the greater of the Flow-Dependent or the Power-Dependent MCPR, depending on the applicable equipment operability status.
a)
Main Turbine Bypass / EOC-RPT / Backup Pressure Regulator Operable Figure 8.2-2:
Figure 8.2-3:
Flow-Dependent MCPR value determined from BOC to EOC for ATRIUM'-10 and ATRIUM' 11 Puel Power-Dependent MCPR value determined from BOC to EOC for ATRIUM'-10 and ATRIUM' 11 Fuel b)
Main Turbine Bypass Inoperable Figure 8.2-4: Flow-Dependent MCPR value determined from BOC to EOC for ATRIUM'-10 and ATRIUM' 11 Fuel Figure 8.2-5: Power-Dependent MCPR value determined from BOC to EOG for ATRIUM'-10 and ATRIUM' 11 Fuel c)
EOC-RPT Inoperable Figure 8.2-6: Flow-Dependent MCPR value determined from BOC to EOG for ATRIUM'-10 and ATRIUM' 11 Fuel Figure 8.2-7: Power-Dependent MCPR value determined from BOC to EOC for ATRIUM'-10 and ATRIUM' 11 Fuel SUSQUEHANNA UNIT 2 TRM / 3.2-50
Rev.20 PL-NF-23-002 Rev.0 Page 50 of 72 d)
Backup Pressure Regulator Inoperable Figure 8.2-8:
Figure 8.2-9:
Flow-Dependent MCPR value detennined from BOC to EOC for ATRIUM'~10 and ATRIUM' 11 Fuel Power-Dependent MCPR value detennined from BOC to EOC for ATRIUM'-10 and ATRIUM' 11 Fuel e)
One Turbine Stop Valve (TSV) or Turbine Control Valve (TCV) Closed Figure 8.2-10:
Flow-Dependent MCPR value detennined from BOC to EOC for ATRIUM'-10 and ATRIUM' 11 Fuel Figure 8.2-11:
Power-Dependent MCPR value detennined from BOC to EOC for ATRIUM'-10 and ATRIUM' 11 Fuel The MCPR limits in Figures 8.2-2 through 8.2-11 are applicable to both.
ATRIUM'-10 and ATRIUM' 11 Fuel, are valid only for Single Loop operation, and support power levels Up to 67 2% RA TED 1HERMAL POWER and core flows up to 52 Mlbm/hr. These conditions conservatively bound Single Loop Operation in accordance with Technical Specification 3.4.1.
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.
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- 60, 2.00 67.2, 2.00 I 7
REFERENCE:
T.S. 3.4.1, 3.7.6, and 3.2.2 1 10 20 30 40 50 60 Core Power(% RATED)
MCPR OPERATING LIMIT VERSUS CORE POWER MAIN TURBINE BYPASS INOPERABLE SINGLE LOOP OPERATION (BOC TO EOC)
ATRIUMTM..10 AND ATRIUMlll 11 FUEL FIGURE 8.2-5 70 r
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SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE! PER SR 3.7.6.1 AND 3.7.6.2 130, 2.osl I
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REFERENCE:
T.S. 3.4.1, 3.3.4.1, and 3.2.2 I 35 40 45 50 55 Total Core Flow (MLB/HR)
MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW EOC-RPT INOPERABLE SINGLE LOOP OPERATION (BOC TO EOC)
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CURVE C: CORE POWERS 26% AND CORE FLOW s 50 MLBM/HR 26, 2.63 MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME 23, 2.88 CURVE D: CORE POWER s 26% AND CORE FLOW s 50 MLBM/HR REALISTIC AVERAGE SCRAM INSERTION TIME CURVEB:
26, 2.63 I
23, 2.86 SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 CURVEC:
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REFERENCE:
T.S. 3.4.1, 3.3.4.1, and 3.2.2 I 10 20 30 40 50 60 Core Power(% RATED)
MCPR OPERATING LIMIT VERSUS CORE POWER EOC-RPT INOPERABLE SINGLE LOOP OPERATION (BOC TO EOC)
ATRIUM'-10 AND ATRIUM' 11 FUEL FIGURE 8.2-7 70
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Rev.20 PL-NF-23-002 Rev.O Page 62 of 72 Backup Pressure Regulator Inoperable SUSQUEHANNA UNIT 2 TRM / 3.2-63
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SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 130, 2.061 USED IN DETERMINING MFLCPR r----......._
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REFERENCE:
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MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW BACKUP PRESSURE REGULATOR INOPERABLE SINGLE LOOP OPERATION (BOC TO EOC)
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,.... CURVE A:
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REFERENCE:
T.S. 3.4.1, 3.7.8, and 3.2.2 I 10 20 30 40 50 60 Core Power(% RATED)
MCPR OPERATING LIMIT VERSUS CORE POWER BACKUP PRESSURE REGULATOR INOPERABLE SINGLE LOOP OPERATION (BOC TO EOC)
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T.S. 3.4.1, 3.2.2, and TRM 3.3. 7:
10 20 I
30 40 50 60 Core Power(% RATED)
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ATRIUMTM..10 AND ATRIUM' 11 FUEL FIGURE 8.2-11 70 80
Rev.20 9.0 POWER/ FLOW MAP 9.1
.References Technical Specification 3.3.1.1 9.2 Description j
PL-NF-23-002 Rev. 0 Page 68 of 72 Monitor reactor conditions to maintain THERMAL POWER/ core flow outside of Stability Regions I and II of the Power I Flow map, Figure 9.1.
If the OPRM Instrumentation Is OPERABLE per TS 3.3.1.1, Region I of the Power I Flow map is considered an immediate exit region.
If the OPRM Instrumentation is inoperable per TS 3.3.1.1, Region I of the Power /
Flow map is considered an immediate scram region.
Region II of the Power I Flow map is considered an immediate exit region regardless_ of the operability of the OPRM Instrumentation.
SUSQUEHANNA UNIT 2 TRM / 3.2-69
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110 SUSQUEHANNA UNIT 2 TRM / 3.2-70
Rev. 20 10.0 OPRM SETPOINTS 10.1 References Technical Specification 3.3.1.1 10.2 Description PL-NF-23-002 Rev. 0 Page 70 of 72 Setpolnts 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 MCPRee.9% Safety limit is not violated. The setpoints are described In Section 2.0 and are listed below:
=
=
=
SUSQUEHANNA UNIT 2 1.12 16 60 Mlbm/ hr TRM / 3.2-71
Rev.20
11.0 REFERENCES
PL-NF-23-002 Rev. O Page 71 of 72
- 11. 1 The analytical methods used to detemiine the core operating limits shall be those previously reviewed and approved by the NRC, specifically those described in the following documents:
- 1. XN-NF-81-58(P)(A), Revision 2 and Supplements 1 and 2, "RODEX2 Fuel Rod Thermal-Mechanical Response Evaluation Model," Exxon Nuclear Company, March 1984.
- 2. EMF-2361(P)(A), Revision 0, "EXEM BWR-2000 ECCS Evaluation Model,"
Framatome ANP, May 2001.
- 3. EMF-2292(P)(A), Revision 0, "ATRIUM'-10: Appendix K Spray Heat Transfer Coefficients," Siemens Power Corporation, September 2000.
41 XN-NF-80-19(P)(A), Volume 1 and Supplements 1 and 2, "Exxon Nuclear Methodology for Bolling Water Reactors: Neutronic Methods for Design and Analysis; Exxon Nuclear Company, March 1983.
- 5. XN-NF-80-19(P)(A), Volume 3 Revision 2 *Exxon Nuclear Methodology for Bolling Water Reactors Thermex: Thermal Limits Methodology Summary Description,* Exxon Nuclear Company, January 1987.
- 6. XN-NF-80-19(P)(A), Volume 4, Revision 1, *Exxon Nuclear Methodology for Boiling Water Reactors: Application of the ENC Methodology to BWR Reloads, n Exxon Nuclear Company, June 1986.
- 7. 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.
- 8. ANF-89-98(P)(A) Revision 1 and Supplement 1, "Generic Mechanical Design Criteria for BWR Fuel Designs," Advanced Nuclear Fuels Corporation, May 1995.
- 9. EMF-2209(P)(A), Revision 3, *spcs Critical Power Correlation," AREVA NP, September 2009.
- 10. 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.
- 11. EMF-2158{P)(A), Revision 0, "Siemens Power Corporation Methodology for Boiling Water Reactors: Evaluation and Validation of CASMO-4/Microburn-82," Siemens Power Corporation, October 1999.
- 12. 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.
SUSQUEHANNA UNIT 2 TRM / 3.2-72
Rev.20 PL-NF-23-002 Rev.0 Page 72 of72
- 13. NED0-32465-A, "BWROG Reactor Core Stability Detect and Suppress Solutions Licensing Basis Methodology for Reload Appllcations," August 1996.
- 14. ANF-1358(P){A), Revision 3, "The Loss of Feedwater Heating Transient in Boiling Water Reactors," Framatome ANP, September 2005.
- 15. BAW-10247PA, Revision 0, "Realistic Thermal-Mechanical Fuel Rod Methodology for Bolling Water Reactors," AREVA, Inc., April 2008.
- 16. ANP-10340P-A, Revision 0, "Incorporation of Chromla-Doped Fuel Properties in AREVA Approved Methods," Framatome Inc., May 2018.
- 17. ANP-10335P-A, Revision 0, "ACE/ATRIUM-11 Critical Power Correlation,"
Framatome Inc., May 2018.
- 18. ANP-10300P-A, Revision 1, "AURORA-B: An Evaluation Model for Bolling Water Reactors; Application to Transient and Accident Scenarios,"
Framatome Inc., January 2018.
- 19. ANP-10332P-A, Revision 0, "AURORA-B: An Evaluation Model for Boiling Water Reactors; Application to Loss of Coolant Accident Scenarios,"
Framatome Inc., March 2019.
- 20. ANP-10333P-A, Revision 0, "AURORA-B: An Evaluation Model for Boiling Water Reactors; Application to Control Rod Drop Accident (CRDA),"
Framatome Inc., March 2018.
- 21. ANP-10307PA, Revision 0, "AREVA MCPR Safety Limit Methodology for Boiling Water Reactors," AREVA, Inc., June 2011.
- 22. BAW-1024 7P-A Supplement 1 P-A, Revision 0, "Realistic Thermal-Mechanical Fuel Rod Methodology for Boiling Water Reactors, Supplement 1:
Qualification of RODEX4 for Recrystallized Zircaloy-2 Cladding," AREVA Inc.,
April 2017.
- 23. BAW-10247P-A Supplement 2P-A, Revision 0, "Realistic Thermal-Mechanical Fuel Rod Methodology for Boiling Water Reactors, Supplement 2:
Mechanical Methods, n Framatome Inc., August 2018.
SUSQUEHANNA UNIT 2 TRM / 3.2-73