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SSES MANUAL Manual Name:

TRMl Manual

Title:

TECHNICAL REQUIREMENTS MANUAL UNIT 1 Table Of Contents Issue Date:

04/04/2024 Procedure Name Rev Issue Date Change ID Change Number TEXT LOEB 96 01/03/2019

Title:

LIST OF EFFECTIVE SECTIONS TEXT TOC 30 11/27/2023

Title:

TABLE OF CONTENTS

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USE AND APPLICATION DEFINITIONS TEXT 2.1 2

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TEXT 3.0

Title:

TECHNICAL REQUIREMENT F.0~.9P~RATI8N (TRO) APPLICABILITY & SURVEILLANCE (TRS)

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11/09/2007 APPLICABILITY TEXT 3.1.1

Title:

REACTIVITY CON;Em2sf~EMS-:ANTICIPATED TRANSIENT WITHOUT SCRAM ALTERNATE ROD INJECTION (AT\\WS--AF.I\\ *I,~SJ'RUMENTATION

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Title* REACTIVITY, CONTROL SYSTEMS CONTROL ROD DRIVE (CRD) HOUSING SUPPORT

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6 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 &

CHECK VALVE TEXT 3.2.1 22 04/04/2024

Title:

CORE OPERATING LIMITS REPORT (COLR)

Page 1 of 16 Report Date: 04/04/24

SSES MANUAL Manual Name:

TRMl Manual

Title:

TECHNICAL REQUIREMENTS MANUAL UNIT 1 TEXT 3.3.1 0

11/18/2002

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 06/29/2017

Title:

INSTRUMENTATION TRM POST-ACCIDENT MONITORING INSTRUMENTATION TEXT 3.3.5 0

11/18/2002

Title:

INSTRUMENTATION THIS PAGE INTENTIONALLY LEFT BLANK TEXT 3.3.6 6

06/29/2023

Title:

INSTRUMENTATION TRM ISOLATION ACTUATION INSTRUMENTATION TEXT 3.3.7 5

08/08/2023

Title:

INSTRUMENTATION MAIN TURBINE OVERSPEED PROTECTION SYSTEM TEXT 3. 3. 8 1

10/22/2003

Title:

INSTRUMENTATION INTENTIONALLY LEFT BLANK TEXT 3.3.9 3

04/17/2008

Title:

OPRM INSTRUMENTATION CONFIGURATION 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 16 Report Date: 04/04/24

SSES MANUAL Manual Name:

TRMl Manual

Title:

TECHNICAL REQUIREMENTS MANUAL UNIT 1 TEXT 3.4.1 1

04/26/2006

Title:

REACTOR COOLANT SYSTEM REACTOR COOLANT SYSTEM CHEMISTRY TEXT 3.4.2 1

04/16/2009

Title:

REACTOR COOLANT SYSTEM INTENTIONALLY LEFT BLANK TEXT 3.4.3 1

11/09/2007

Title:

REACTOR COOLANT SYSTEM HIGH/LOW PRESSURE INTERFACE LEAKAGE MONITORS TEXT 3.4.4 2

04/17/2008

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 TEXT 3.4.6 3

05/13/2022

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 1

11/27/2023

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

11/18/2002

Title:

CONTAINMENT SUPPRESSION POOL ALARM INSTRUMENTATION Page 3 of 16 Report Date: 04/04/24

SSES MANUAL Manual Name:

TRMl Manual

Title:

TECHNICAL REQUIREMENTS MANUAL UNIT 1 TEXT 3.6.4 1

11/27/2023

Title:

CONTAINMENT PRIMARY CONTAINMENT CLOSED SYSTEM BOUNDARIES TEXT 3.7.1 0

11/18/2002

Title:

PLANT SYSTEMS EMERGENCY SERVICE WATER SYSTEM (ESW) SHUTDOWN TEXT 3.7.2 1

11/27/2023

Title:

PLANT SYSTEMS ULTIMATE HEAT SINK (UHS) AND GROUND WATER LEVEL TEXT 3.7.3.1 6

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 TEXT 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:

PLANT SYSTEMS FIRE RATED ASSEMBLIES TEXT 3.7.3.8 14 11/27/2023

Title:

PLANT SYSTEMS FIRE DETECTION INSTRUMENTATION TEXT 3.7.4 2

11/27/2023

Title:

PLANT SYSTEMS SOLID RADWASTE SYSTEM Page 4 of 16 Report Date: 04/04/24

SSES MANUAL Manual Name:

TRMl Manual

Title:

TECHNICAL REQUIREMENTS MANUAL UNIT 1 TEXT 3.7.5.1 1

03/05/2015

Title:

PLANT SYSTEMS MAIN CONDENSER OFFGAS HYDROGEN MONITOR TEXT 3.7.5.2 0

11/18/2002

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 TEXT 3.7.8 5

03/05/2015

Title:

PLANT SYSTEMS SNUBBERS TEXT 3.7.9 3

03/05/2019

Title:

PLANT SYSTEMS CONTROL STRUCTURE HVAC TEXT 3.7.10 1

12/14/2004

Title:

PLANT SYSTEMS SPENT FUEL STORAGE POOLS (SFSPS)

TEXT 3.7.11 1

11/01/2018

Title:

STRUCTURAL INTEGRITY TEXT 3.8.1 3

04/22/2020

Title:

ELECTRICAL POWER PRIMARY CONTAINMENT PENETRATION CONDUCTOR OVERCURRENT PROTECTIVE DEVICES TEXT 3.8.2.1 3

09/19/2023

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 16 Report Date: 04/04/24

SSES MANUAL Manual Name:

TRMl Manual

Title:

TECHNICAL REQUIREMENTS MANUAL UNIT 1 TEXT 3. 8. 3 4

01/28/2020

Title:

ELECTRICAL POWER DIESEL GENERATOR (DG) MAINTENANCE ACTIVITIES TEXT 3.8.4 1

11/27/2023

Title:

ELECTRICAL POWER 24 VDC ELECTRICAL POWER SUBSYSTEM TEXT 3.8.5 1

11/14/2013

Title:

ELECTRICAL POWER DEGRADED VOLTAGE PROTECTION TEXT 3.8.6 2

03/05/2019

Title:

ELECTRICAL POWER EMERGENCY SWITCHGEAR ROOM COOLING TEXT 3.8.7 2

02/25/2021

Title:

BATTERY MAINTENANCE AND MONITORING PROGRAM TEXT 3.9.1 0

11/18/2002

Title:

REFUELING OPERATIONS DECAY TIME TEXT 3.9.2 0

11/18/2002

Title:

REFUELING OPERATIONS COMMUNICATIONS TEXT 3. 9. 3 1

03/12/2019

Title:

REFUELING OPERATIONS REFUELING PLATFORM TEXT 3.10.1 2

11/27/2023

Title:

MISCELLANEOUS SEAL SOURCE CONTAMINATION TEXT 3.10.2 3

06/19/2019

Title:

MISCELLANEOUS SHUTDOWN 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

04/17/2008

Title:

INTENTIONALLY LEFT BLANK Page 6 of 16 Report Date: 04/04/24

SSES MANUAL Manual Na.me:

TRMl Manual

Title:

TECHNICAL REQUIREMENTS MANUAL UNIT 1 TEXT 3. 11. 1. 1 2

11/27/2023

Title:

RADIOACTIVE EFFLUENTS LIQUID EFFLUENTS CONCENTRATION TEXT 3.11.1.2 2

11/27/2023

Title:

RADIOACTIVE EFFLUENTS LIQUID EFFLUENTS DOSE TEXT 3.11.1.3 2

11/27/2023

Title:

RADIOACTIVE EFFLUENTS LIQUID WASTE TREATMENT SYSTEM TEXT 3. 11. 1. 4 3

11/27/2023

Title:

RADIOACTIVE EFFLUENTS LIQUID RADWASTE EFFLUENT MONITORING INSTRUMENTATION TEXT 3. 11. 1. 5 4

11/27/2023

Title:

RADIOACTIVE EFFLUENTS RADIOACTIVE LIQUID PROCESS MONITORING INSTRUMENTATION TEXT 3. 11. 2. 1 5

11/27/2023

Title:

RADIOACTIVE EFFLUENTS DOSE RATE TEXT 3.11.2.2 2

11/27/2023

Title:

RADIOACTIVE EFFLUENTS DOSE -

NOBLE GASES TEXT 3.11.2.3 2

11/27/2023

Title:

RADIOACTIVE EFFLUENTS DOSE -

IODINE, TRITIUM, AND RADIONUCLIDES IN PARTICULATE FORM TEXT 3. 11. 2. 4 1

11/27/2023

Title:

RADIOACTIVE EFFLUENTS GASEOUS RADWASTE TREATMENT SYSTEM TEXT 3.11.2.5 5

11/27/2023

Title:

RADIOACTIVE EFFLUENTS VENTILATION EXHAUST TREATMENT SYSTEM TEXT 3. 11. 2. 6 9

11/27/2023

Title:

RADIOACTIVE EFFLUENTS RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION TEXT 3.11.3 2

11/27/2023

Title:

RADIOACTIVE EFFLUENTS TOTAL DOSE Page 7 of 16 Report Date: 04/04/24

SSES MANUAL Manual Name:

TRMl Manual

Title:

TECHNICAL REQUIREMENTS MANUAL UNIT 1 TEXT 3. 11. 4. 1 7

11/27/2023

Title:

RADIOACTIVE EFFLUENTS MONITORING PROGRAM TEXT 3.11.4.2 3

11/27/2023

Title:

RADIOACTIVE EFFLUENTS LAND USE CENSUS TEXT 3.11.4.3 2

11/27/2023

Title:

RADIOACTIVE EFFLUENTS INTERLABORATORY COMPARISON PROGRAM TEXT 3.12.1 0

11/19/2002

Title:

LOADS CONTROL PROGRAM CRANE TRAVEL-SPENT FUEL POOL STORAGE POOL TEXT 3.12.2 4

04/17/2008

Title:

LOADS CONTROL PROGRAM HEAVY LOADS REQUIREMENTS TEXT 3.12.3 0

11/19/2002

Title:

LOADS CONTROL PROGRAM LIGHT LOADS REQUIREMENT TEXT,4.1 0

08/31/1998

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 2

11/27/2023

Title:

ADMINISTRATIVE CONTROLS PROCEDURES & PROGRAMS TEXT 4.6 0

08/31/1998

Title:

ADMINISTRATIVE CONTROLS RADIATION PROTECTION PROGRAM Page 8 of 16 Report Date: 04/04/24

SSES MANUAL Manual Name:

TRMl Manual

Title:

TECHNICAL REQUIREMENTS MANUAL UNIT 1 TEXT 4.7 1

12/13/2022

Title:

ADMINISTRATIVE CONTROLS PROCEDURES & PROGRAMS TEXT B3.0 6

03/18/2021

Title:

APPLICABILITY BASES TECHNICAL REQUIREMENT FOR OPERATION (TRO) APPLICABILITY TEXT B3.l.l 2

04/29/2014

Title:

REACTIVITY CONTROL SYSTEMS BASES ANTICIPATED TRANSIENT WITHOUT SCRAM ALTERNATE ROD INJECTION (ATWS-ARI) INSTRUMENTATION TEXT B3.l.2 0

11/19/2002

Title:

REACTIVITY CONTROL SYSTEMS BASES CONTROL ROD DRIVE (CRD) HOUSING SUPPORT TEXT B3.l.3 4

12/18/2017

Title:

REACTIVITY CONTROL SYSTEMS BASES CONTROL ROD BLOCK INSTRUMENTATION TEXT B3.l.4 1

10/12/2020

Title:

REACTIVITY CONTROL SYSTEMS BASES CONTROL ROD SCRAM ACCUMULATORS INSTRUMENTATION AND CHECK VALVE TEXT B3.2.l 0

11/19/2002

Title:

CORE OPERATING LIMITS BASES 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 3

12/18/2008

Title:

INSTRUMENTATION BASES METEOROLOGICAL MONITORING INSTRUMENTATION TEXT B3.3.4 8

11/27/2023

Title:

INSTRUMENTATION BASES TRM POST ACCIDENT MONITORING (PAM), INSTRUMENTATION TEXT B3.3.5 2

11/09/2007

Title:

INTENTIONALLY LEFT BLANK Page 9 of 16 Report Date: 04/04/24

SSES MANUAL Manual Name:

TRMl Manual

Title:

TECHNICAL REQUIREMENTS MANUAL UNIT 1 TEXT B3.3.6 7

06/29/2023

Title:

INSTRUMENTATION BASES TRM ISOLATION ACTUATION INSTRUMENTATION TEXT B3.3.7 5

08/08/2023

Title:

INSTRUMENTATION BASES MAIN TURBINE OVERSPEED PROTECTION SYSTEM TEXT B3.3.8 1

10/22/2003

Title:

INTENTIONALLY LEFT BLANK TEXT B3.3.9 4

01/03/2019

Title:

OPRM INSTRUMENTATION TEXT B3.3.10 3

08/09/2010

Title:

INSTRUMENTATION BASES REACTOR RECIRCULATION PUMP MG SET STOPS TEXT B3.3.ll 1

10/22/2003

Title:

INSTRUMENTATION BASES MVP ISOLATION INSTRUMENTATION TEXT B3.3.12 1

04/02/2019

Title:

WATER MONITORING INSTRUMENTATION TEXT B3.4.1 0

11/19/2002

Title:

REACTOR COOLANT SYSTEM BASES REACTOR COOLANT SYSTEM CHEMISTRY TEXT B3.4.2 1

04/16/2009

Title:

INTENTIONALLY LEFT BLANK TEXT B3.4.3 1

11/09/2007

Title:

REACTOR COOLANT SYSTEM BASES HIGH/LOW PRESSURE INTERFACE LEAKAGE MONITOR TEXT B3.4.4 0

11/19/2002

Title:

REACTOR COOLANT SYSTEM BASES REACTOR RECIRCULATION FLOW AND ROD LINE LIMIT TEXT B3.4.5 0

11/19/2002

Title:

REACTOR COOLANT SYSTEM BASES REACTOR VESSEL MATERIALS Page 10 of 16 Report Date: 04/04/24

SSES MANUAL Manual Name:

TRMl Manual

Title:

TECHNICAL REQUIREMENTS MANUAL UNIT 1 TEXT B3.4.6 4

05/13/2022

Title:

REACTOR RECIRCULATION SINGLE LOOP OPERATION SLO FLOW RATE RESTRICTION TEXT B3.5.l 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 1

11/27/2023

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 2

04/17/2008

Title:

CONTAINMENT BASES SUPPRESSION POOL ALARM INSTRUMENTATION TEXT B3.6.4 2

11/27/2023

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 1

11/27/2023

Title:

PLANT SYSTEMS BASES ULTIMATE HEAT SINK (UHS) GROUND WATER LEVEL TEXT B3.7.3.1 4

02/16/2017

Title:

PLANT SYSTEMS BASES FIRE SUPPRESSION WATER SUPPLY SYSTEM TEXT B3.7.3.2 2

04/26/2006

Title:

PLANT SYSTEMS BASES SPRAY AND SPRINKLER SYSTEMS Page 11 of 16 Report Date: 04/04/24

SSES MANUAL Manual Name:

TRMl Manual

Title:

TECHNICAL REQUIREMENTS MANUAL UNIT 1 TEXT B3.7.3.3 1

01/03/2019

Title:

PLANT SYSTEMS BASES CO2 SYSTEMS TEXT B3.7.3.4 4

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 TEXT B3.7.3.8 3

09/27/2012

Title:

PLANT SYSTEMS BASES FIRE DETECTION INSTRUMENTATION TEXT B3.7.4 1

11/27/2023

Title:

PLANT SYSTEMS BASES SOLID RADWASTE SYSTEM TEXT B3.7.5.l 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 SYSTEMS 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 16 Report Date: 04/04/24

SSES MANUAL Manual Name:

TRMl Manual

Title:

TECHNICAL REQUIREMENTS MANUAL UNIT 1 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 2

11/01/2018

Title:

STRUCTURAL INTEGRITY TEXT B3.8.l 2

03/10/2010

Title:

ELECTRICAL POWER BASES PRIMARY CONTAINMENT PENETRATION CONDUCTOR OVERCURRENT PROTECTIVE DEVICES TEXT B3. 8. 2*.1 1

09/19/2023

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 1

11/27/2023

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 3

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 16 Report Date: 04/04/24

SSES MANUAL Manual Name:

TRMl Manual

Title:

TECHNICAL REQUIREMENTS MANUAL UNIT 1 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 1

11/27/2023

Title:

MISCELLANEOUS BASES SEALED SOURCE CONTAMINATION TEXT B3.10.2 1

03/31/2006

Title:

MISCELLANEOUS BASES SHUTDOWN MARGIN TEST RPS INSTRUMENTATION TEXT B3.10.3 3

10/05/2022

Title:

MISCELLANEOUS BASES INDEPENDENT SPENT FUEL STORAGE INSTALLATION (ISFSI)

TEXT B3.10.4 1

04/17/2008

Title:

INTENTIONALLY LEFT BLANK TEXT B3. 11.1. 1 1

11/27/2023

Title:

RADIOACTIVE EFFLUENTS BASES LIQUID EFFLUENTS CONCENTRATION TEXT B3. 11.1. 2 1

11/27/2023

Title:

RADIOACTIVE EFFLUENTS BASES LIQUID EFFLUENTS DOSE TEXT B3. 11.1. 3 1

11/27/2023

Title:

RADIOACTIVE EFFLUENTS BASES LIQUID WASTE TREATMENT SYSTEM TEXT B3. 11. 1. 4 1

11/27/2023

Title:

RADIOACTIVE EFFLUENTS BASES LIQUID RADWASTE EFFLUENT MONITORING INSTRUMENTATION TEXT B3.ll.1.5 1

11/27/2023

Title:

RADIOACTIVE EFFLUENTS BASES RADIOACTIVE LIQUID PROCESS MONITORING INSTRUMENTATION Page 14 of 16 Report Date: 04/04/24

r SSES MANUAL Manual Name:

TRMl Manual

Title:

TECHNICAL REQUIREMENTS MANUAL UNIT 1 TEXT B3. 11. 2. 1 2

11/27/2023

Title:

RADIOACTIVE EFFLUENTS BASES DOSE RATE TEXT B3. 11. 2. 2 1

11/27/2023

Title:

RADIOACTIVE EFFLUENTS BASES DOSE - NOBLE GASES TEXT B3.11. 2. 3 1

11/27/2023

Title:

RADIOACTIVE EFFLUENTS BASES DOSE -

IODINE, TRITIUM, AND RADIONUCLIDES IN PARTICULATES FORM TEXT B3.ll.2.4 1

11/27/2023

Title:

RADIOACTIVE EFFLUENTS BASES GASEOUS RADWASTE TREATMENT SYSTEM TEXT B3.ll.2.5 6

11/27/2023

Title:

RADIOACTIVE EFFLUENTS BASES VENTILATION EXHAUST TREATMENT SYSTEM TEXT B3.ll.2.6 3

11/27/2023

Title:

RADIOACTIVE EFFLUENTS BASES RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION TEXT B3.ll.3 1

11/27/2023

Title:

RADIOACTIVE EFFLUENTS BASES TOTAL DOSE TEXT B3. 11. 4. 1 7

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Title:

RADIOACTIVE EFFLUENTS BASES MONITORING PROGRAM TEXT B3.ll.4.2 1

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Title:

RADIOACTIVE EFFLUENTS BASES LAND USE CENSUS TEXT B3.ll.4.3 1

11/27/2023

Title:

RADIOACTIVE EFFLUENTS BASES INTERLABORATORY COMPARISON PROGRAM

TEXT B3. 12. 1 1

10/04/2007

Title:

LOADS CONTROL PROGRAM BASES CRANE TRAVEL-SPENT FUEL STORAGE POOL TEXT B3.12.2 1

12/03/20],0

Title:

LOADS CONTROL PROGRAM BASES HEAVY LOADS REQUIREMENTS Page 15 of 16 Report Date: 04/04/24

SSES MANUAL Manual Name:

TRMl Manual

Title:

TECHNICAL REQUIREMENTS MANUAL UNIT 1 TEXT B3.12.3 0

11/19/2002

Title:

LOADS CONTROL PROGRAM BASES LIGHT LOADS REQUIREMENTS Page 16 of 16 Report Date: 04/04/24

Rev.22 3.2 CORE OPERATING LIMITS REPORT (COLR) 3.2.1 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 A.1 met.

REQUIRED ACTION Perform action(s) described in referenced Technical Specification.

TECHNICAL REQUIREMENT SURVEILLANCE SUR1/EILLANCE-..

NOTE----

No associated Surveillances. Surveillances are implemented in the applicable Technical Specifications.

COMPLETION TIME.

Specified in referenced Technical '

Specifications FREQUENCY N/A SUSQUEHANNA - UNIT 1 TRM / 3.2-1

Rev. 22 Susquehanna SES Unit 1 Cycle 24 PL-NF-24-003 Rev. O Page 1 of 72 CORE OPERA TING LIMITS SUSQUEHANNA UNIT 1 REPORT TRM / 3.2-2 Nuclear Fuels Engineering

March 2024

REV AFFECTED NO.

SECTIONS 0

ALL FORM NFP-QA-008-2, Rev. 2 SUSQUEHANNA UNIT 1 Rev.22 PL-NF-24-003 Rev. O Page 2 of 72 CORE OPERATING LIMITS REPORT REVISION DESCRIPTION INDEX DESCRIPTION/ PURPOSE OF REVISION Issuance of this COLR is in support of Unit 1 Cycle 24 operation.

TRM / 3.2-3

Rev. 22 SUSQUEHANNA STEAM ELECTRIC STATION Unit 1 Cycle 24 CORE OPERATING LIMITS REPORT Table of Contents PL-NF-24-003 Rev. 0, Page 3 of 72

1.0 INTRODUCTION

......................................................................................................... 4 2.0 DEFINITIONS.............................................................................................................. 5 3.0 SHUTDOWN MARGIN................................................................................................ 6 4.0 AVERAGE PLANAR LINEAR HEAT GENERATION RATE (APLHGR)....................... 7 5.0 MINIMUM CRITICAL POWER RATIO (MCPR)........................................................... 10 6.0 LINEAR HEAT GENERATION RATE (LHGR).............................................................. 28 7.0 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 1 TRM / 3.2-4

Rev.22

1.0 INTRODUCTION

PL-NF-24-003.

Rev. O Page 4 of 72 This CORE OPERATING LIMITS REPORT for Susquehanna Unit 1 Cycle 24 is prepared in accordance with the requirements of Susquehanna Unit 1, Technical Specification 5.6.5. As required by Technical Specifications 5.6.5, core shutdown margin, the core operating limits, RBM setpoints, and OPRM setpoints 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 1 TRM / 3.2-5

Rev.22 2.0 DEFINITIONS PL-NF-24-003 Rev. O 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 LHGRFACf is a multiplier applied to the LHGR limit when operating at less than 108 Mlbm/hr core flow. The LHGRFACt 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 MCPRss.s% 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 MAP RAT is the ratio of the maximum APLHGR calculated by the core monitoring system for each fuel bundle divided 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 MCPRss.s% 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 1 TRM / 3.2-6

Rev.22 PL-NF-24-003 Rev. O Page 6 of 72 3.0 SHUTDOWN MARGIN 3.1 3.2 References Technical Specification 3.1.1 Description The SHUTDOWN MARGIN shall be equal to or greater than:

a) 0.38% Ak/k with the highest worth rod analytically determined OR b) 0.28% Ak/k with the highest worth rod determined by test Since core reactivity will vary during the cycle as a function of fuel depletion and poison burnup, Beginning of Cycle (BOC) SHUTDOWN MARGIN (SOM) tests must also account for changes in core reactivity during the cycle. Therefore, the SOM measured at BOC must be equal to or greater than the applicable requirement from either 3.2.a or 3.2.b plus an adder, "R". The adder, "R", is the difference between the calculated value of maximum core reactivity (that is, minimum SOM) during the operating cycle and the calculated BOC core reactivity. If the value of "R" is zero (that is, BOC is the most reactive point in the cycle) no correction to the BOC measured value is required.

The SHUTDOWN MARGIN limits provided in 3.2a and 3.2b are applicable in MODES 1, 2, 3, 4, and 5. This includes core shuffling.

SUSQUEHANNA UNIT 1 TRM / 3.2-7

Rev. 22 PL-NF-24-003

Rev. O Page 7 of 72 4.0. AVERAGE PLANAR LINEAR HEAT GENERATION RA TE (APLHGR) 4.1 4.2 References Technical Specification 3.2.1 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 4.2-1 B.

The APLHGR limits in Figures 4.2-1A and 4.2-1B 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 1 TRM / 3.2-8

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AVERAGE PLANAR LINEAR HEAT GENERATION RATE LIMIT VERSUS AVERAGE PLANAR EXPOSURE - TWO LOOP OPERATION ATRIUM'-10 FUEL FIGURE 4.2-1A 60000 70000

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Rev.22 PL-NF-24-003 Rev. O Page 10 of 72 5.0 MINIMUM CRITICAL POWER RA TIO {MCPR) 5.1 5.2 References Technical Specification 3.2.2, 3.3.4.1, 3.7.6, and 3.7.8 Technical Requirements Manual 3.3.7 Description The MCPRss.s% 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 EOG for ATRIUM'-10 and ATRIUM' 11 Fuel Power-Dependent MCPR value determined from BOC to EOG 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 EOG for ATRIUM'-10 and ATRIUM' 11 Fuel Power-Dependent MCPR value determined from BOC to EOG 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 EOG for ATRIUM'-10 and ATRIUM' 11 Fuel Power-Dependent MCPR value determined from BOC to EOG 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 EOG for ATRIUM'-10 and ATRIUM' 11 Fuel Power Dependent MCPR value determined from BOC to EOG for ATRIUM'-10 and ATRIUM' 11 Fuel e)

One Turbine Stop Valve (TSV) or Turbine Control Valve (TCV) Closed SUSQUEHANNA UNIT 1 TRM / 3.2-11

Rev. 22 PL-NF-24-003 Rev. O Page 11 of 72

Figure 5.2-9:

Flow-Dependent MCPR value determined from BOC to EOC for ATRIUM'-10 and ATRIUM' 11 Fuel Figure 5.2-10:

Power-Dependent,MCPR value determined from BOC to EOC for ATRIUM'-10 and ATRIUM' 11 Fuel The MCPR limits in Figures 5.2-1 through 5.2-10 are valid for 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 permitted. The evaluation of scram insertion time data, as it relates to the attached table should be performed per Reactor Engineering procedures.

SUSQUEHANNA UNIT 1 TRM / 3.2-12

Rev.22 PL-NF-24-003 Rev. O Page 12 of 72 Main Turbine Bypass/ EOC-RPT /

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T.S. 3.2.2 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)

ATRIUM'-10 AND ATRIUM'11 FUEL FIGURE 5.2-1

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ALL SCRAM INSERTION TIMES 26, 2.57 23, 2.61 CURVE B:

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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 I 9o, 1.50 I 90 100

Rev.22 Main Turbine Bypass Inoperable SUSQUEHANNA UNIT 1 TRM / 3.2-16 PL-NF-24-003 Rev. O

_ Page 15 of 72

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26, 2.62 23, 2.69 CURVED:

26, 2.62 23, 2.69 SSES UNIT 1 CYCLE 24 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 A

CURVE D: CORE POWER s; 26% AND CORE FLOW s; 50 MLBM/HR

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B REALISTIC AVERAGE SCRAM INSERTION TIME

'\\.

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SAFETY ANALYSES ASSUME THAT TWO OR MORE BYPASS VALVES ARE....

INOPERABLE PER SR 3.7.6.1 OR 3.7.6.2

... c............

USED IN DETERMINING MFLCPR

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140, 1.881 l 90, 1.641 I 50, 1.83 I

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REFERENCE:

T.S. 3.7.6 and 3.2.21 8_ H10, 1.65I-H 80, 1.601 190, 1.57~

1100, 1.641 1100, 1.511 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)

ATRIUMTNl-10 AND ATRIUM' 11 FUEL*

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SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES

~

ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 135.0, 1.841 USED IN DETERMINING MFLCPR 135.1, 1.531

40.0, 1.49:

A B

I 40~1, 1.37 I H

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REFERENCE:

T.S. 3.3.4.1 and 3.2.2 1

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)

ATRIUM'-10 AND ATRIUM' 11 FUEL FIGURE 5.2-5 100 L

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CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME i-- 26, 2.57 1--

23, 2.61 CURVE C: CORE POWER s 26% AND CORE FLOW s 50 MLBM/HR MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME

~

CURVE B:

CURVE D: CORE POWERS 26% AND CORE FLOWS 50 MLBM/HR

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.... CURVE C:

PER SR 3.7.6.1 AND 3.7.6.2

._ 26, 2.53

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REFERENCE:

T.S. 3.3.4.1 and 3.2.21 B-n10, 1.s11 l 80, 1.58 I 1so, 1.53L I 100, 1.s9 I I 100, 1.51 I 10 20 30 40 50 60 70 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 80 90 100

o

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Rev. 22 PL-NF-24-003 Rev. 0 Page 21 of 72 Backup Pressure Regulator Inoperable SUSQUEHANNA UNIT 1 TRM / 3.2-22

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I 35.1, 1.53 I

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- I 108.0, 1.221 j

REFERENCE:

T.S. 3.7.8 and 3.2.2j I

I 30 40 50 60 70 80 90 Total Core Flow (MLB/HR)

MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW BACKUP PRESSURE REGULATOR INOPERABLE TWO LOOP OPERATION (BOC TO EOC)

_ ATRIUMTfl!l.10 AND ATRIUM' 11 FUEL FIGURE 5.2-7 100 110

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CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME 26, 2.57 23, 2.61 CURVE C: CORE POWER S 26% AND CORE FLOW S 50 MLBM/HR ALL SCRAM INSERTION TIMES CURVE 8:

26, 2.57 I

23, 2.61 SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2

,_ CURVEC: ----A-B

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REFERENCE:

T.S. 3.7.8 and 3.2.2 1 I 90, 1.50 I 10 20 30 40 50 60 70 Core Power(% RATED)

MCPR OPERATING LIMIT VERSUS CORE POWER BACKUP PRESSURE REGULATOR INOPERABLE TWO LOOP OPERATION (BOC TO EOC)

ATRIUM'-10 AND_ATRIUM'11 FUEL FIGURE 5.2-8 80 90 100 100, 1.53 100, 1.42

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SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES 30 ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2

' I 40.0, 1.85 I USED IN DETERMINING MFLCPR I

A 140.1, 1.59 1 B

REFERENCE:

T.S. 3.2.2 and TRM 3.3.71 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

Operation with one TSV or TCV closed is only supported at power levels S 75% rated power

- I 108.0, 1.37 I 110

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26, 2.57 CURVE C: CORE POWER :5; 26% AND CORE FLOW::;; 50 MLBM/HR 23, 2.61 ALL SCRAM INSERTION TIMES CURVE B:

I 26, 2.57 23, 2.61 SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE A

PER SR 3.7.6.1 AND 3.7.6.2 B-CURVE C:

26, 2.53 I

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50, 1.811 60, 1.72 I I -115, 1.581

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REFERENCE:

T.S. 3.2.2 and TRM 3.3.7:

I 70, 1.61 r 10 20 I

30 40 50 Core Power(% RATED)

MCPR OPERATING LIMIT VERSUS CORE POWER ONE TSV OR TCV CLOSED TWO LOOP OPERATION (BOC TO EOC)

ATRIUM'-10 AND ATRIUM' 11 FUEL FIGURE 5.2-10 60 70 80

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Rev. 22 Table 5.3-1 PL-NF-24-003 Rev. O Page 27 of 72 Average Scram Time Fraction Table For Use With Scram Time Dependent MCPR Operating Limits Control Rod Average Scram Time to Position (seconds)

Position 45 0.470 0.520 39 0.630 0.860 25 1.500 1.910 5

2.700 3.440 Average Scram Realistic Maximum Insertion Time Allowable SUSQUEHANNA UNIT 1 TRM / 3.2-28

Rev. 22 PL-NF~24-003 Rev. O Page 28 of 72 6.0 LINEAR HEAT GENERATION RATE (LHGR) 6.1 References 6.2 Technical Specification 3.2.3, 3.3.4.1, 3.7.6, and 3.7.8 Technical Requirements Manual 3.3.7 Description The maximum LHGR for ATRIUM'-10 and ATRIUM' 11 fuel shall not exceed the LHGR limits determined from Figure 6.2-1A and Figure 6.2-1 B, respectively.

The LHGR limits in Figures 6.2-1A and 6.2-1 B 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 ATRIUM' 11 Fuel d)

Backup Pressure Regulator Inoperable Figure 6.2-8:

Flow-Dependent LHGR Limit Multiplier for ATRIUM'-10 and ATRIUM' 11 Fuel SUSQUEHANNA UNIT 1 TRM / 3.2-29

Figure 6.2-9:

Rev. 22 PL-NF-24-003 Rev. 0 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/6.2-1 Bare 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 1 TRM / 3.2-30

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LINEAR HEAT GENERATION RATE LIMIT VERSUS PELLET EXPOSURE ATRIUM' 11 FUEL FIGURE 6.2-1 B 70000 80000

Rev.22 PL-NF-24-003 Rev. O Page 32 of 72 Main Turbine Bypass/ EOC-RPT /

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POWER DEPENDENT LHGR LIMIT MULTIPLIER ONE TSV OR TCV CLOSED ATRIUM'-10 AND ATRIUM' 11 FUEL FIGURE 6.2-11 70 80

0

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Rev. 22 PL-NF-24-003 Rev. 0 Page47 of72 7.0 ROD BLOCK MONITOR (RBM) SETPOINTS AND OPERABILITY REQUIREMENTS 7.1 References 7.2 Technical Specification 3.3.2.1 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)

Intermediate 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 RBM system is not required to be operable. Table 7.2-2 provides RBM system operability requirements to ensure that fuel design limits are not violated.

SUSQUEHANNA UNIT 1 TRM / 3.2-48

Rev.22 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<1>

28.0 63.0 83.0 123.4 117.4 105.6 PL-NF-24-003 Rev. O Page 48 of 72 Nominal Trip Setpoint 24.9 61.0 81.0 123.0 117.0 105.2

<1>

Power setpoint function (Low, Intermediate, and High Power Range Setpoints) determined in percent of RATED THERMAL POWER. Upscale trip setpoint function (Low, Intermediate, and High Power Range - Upscale) determined in percent of reference level.

Table 7.2-2 RBM System Operability Requirements Thermal Power MCPR <2,3,4>

(% of Rated)

28 and< 90

< 1.78

90 and< 95

< 1.47

~95

< 1.68

<2>

Applicable to Main Turbine Bypass Operable and Inoperable, EOC-RPT Operable and Inoperable, Backup Pressure Regulator Operable and Inoperable, and one TCV/TSV closed.

<3>

Applicable to both Two Loop and Single Loop Operation.

<4>

Applicable to both ATRIUM-10 and ATRIUM 11 Fuel.

SUSQUEHANNA UNIT 1 TRM / 3.2-49

Rev.22 PL-NF-24-003 Rev. O Page49 of 72 8.0 RECIRCULATION LOOPS - SINGLE LOOP OPERATION 8.1 References 8.2 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 3.3.7 Description APLHGR The APLHGR limit for ATRIUM'-10 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 Bare 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 Fuel Power-Dependent MCPR value determined from BOC to EOCforATRIUM'-10andATRIUM' 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 EOC for ATRIUM'-10 and ATRIUM' 11 Fuel c)

EOC-RPT Inoperable Figure 8.2-6: Flow-Dependent MCPR value determined from BOC to EOC 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 1 TRM / 3.2-50

Rev. 22 PL-NF-24-003 Rev.a Page 50 of 72 d)

Backup Pressure Regulator Inoperable Figure 8.2-8:

Figure 8.2-9:

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 Figure 8.2-10:

Flow-Dependent MCPR value determined from BOC to EOC for ATRIUM'-10 and ATRIUM' 11 Fuel Figure 8.2-11:

Power-Dependent MCPR value determined 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% RATED THERMAL 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.

SUSQUEHANNA UNIT 1 TRM / 3.2-51

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Rev. O Page 53 of 72 Main Turbine Bypass/ EOC-RPT /

Backup Pressure Regulator Operable SUSQUEHANNA UNIT 1 TRM / 3.2-54

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MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW MAIN TURBINE BYPASS/ EOC-RPT / BACKUP PRESSURE REGULATOR OPERABLE SINGLE LOOP OPERATION (BOC TO EOC)

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10 20 30 40 50 60 70 Core Power (% RA TED)

MCPR OPERA TING LIMIT VERSUS CORE POWER MAIN TURBINE BYPASS/ EOC-RPT / BACKUP PRESSURE REGULATOR OPERABLE SINGLE LOOP OPERATION (BOC TO EOC)

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Rev. 22 Main Turbine Bypass Inoperable SUSQUEHANNA UNIT 1 TRM / 3.2-57 PL-NF-24-003 Rev. 0 Page 56 of 72

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USED IN DETERMINING MFLCPR 26, 2.64 D

23, 2.71 126.01, 2.44 140, 2.04 A

150, 2.01 I 160, 2.01 I 26.01, 2.25 I 67.2, 2.01 I 140, 2.01 B- ~ 50, 2.01 I 160, 2.01 67.2, 2.01 I

~

REFERENCE:

T.S. 3.4.1, 3.7.6, and 3.2.2:

10 20 30 40 50 60 Core Power(% RATED)

MCPR OPERA TING LIMIT VERSUS CORE POWER MAIN TURBINE BYPASS INOPERABLE SINGLE LOOP OPERATION (BOC TO EOC)

ATRIUM'-10 AND ATRIUM' 11 FUEL FIGURE 8.2-5 70

~

80

SUSQUEHANNA UNIT 1 Rev.22 EOC-RPT Inoperable TRM / 3.2-60 PL-NF-24-003 Rev. 0 Page 59 of 72

en 3.0 C

en 0

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0 1.8 j\\J

iE I 0) 1.6 1.4 1.2 1.0 SSES UNIT 1 CYCLE 24 I

LEGEND CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME I

I I

SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 W3o, 1.95 1 I

USED IN DETERMINING MFLCPR

~

135, 1.841 140, 1.491 A

I 35.1, 1.53 I 8

140.1, 1.371 j52, 1.341

\\

REFERENCE:

T.S. 3.4.1, 3.3.4.1, and 3.2.2 30 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)

ATRIUM'-10 AND ATRIUM' 11 FUEL FIGURE 8.2-6 60 65 70

(f) 4.4 C

(f) 0 4.2 C m

r:

)>

4.0 z z

)>

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-I 3.6 3.4 E 3.2

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c,.:,

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1.4 10 SSES UNIT 1 CYCLE 24 LEGEND CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME CURVE A:

CURVE C: CORE POWER :;;; 26% AND CORE FLOW:;;; 50 MLBM/HR 26, 2.59 MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME 23, 2.63 CURVE D: CORE POWER:;;; 26% AND CORE FLOW:;;; 50 MLBM/HR REALISTIC AVERAGE SCRAM INSERTION TIME CURVE B:

26, 2.59 23, 2.63 SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 CURVEC:

A I

I I

26, 2.55 B

I USED IN DETERMINING MFLCPR 23, 2.63 I

C o- ---i 26.01, 2.42; CURVED:

26, 2.55 23, 2.63

40, 2.03 A-n5o, 2.031 160, 2.01 y 67.2, 2.01 I 126.01, 2.20 I 140, 2.01 r 8-M50, 2.011 160, 2.01 67.2, 2.01 I I

REFERENCE:

T.S. 3.4.1, 3.3.4.1, and 3.2.2 I

20 30 40 50 60 Core Power (% RA TED)

MCPR OPERA TING LIMIT VERSUS CORE POWER EOC-RPT INOPERABLE SINGLE LOOP OPERATION (BOC TO EOC)

ATRIUM'-10 AND ATRIUM'11 FUEL FIGURE 8.2-7 70

~

80

Rev. 22 PL-NF-24-003 Rev.O Page 62 of 72 Backup Pressure Regulator Inoperable SUSQUEHANNA UNIT 1 TRM / 3.2-63

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1.6 1.4 1.2 1.0 SSES UNIT 1 CYCLE 24 LEGEND CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME I

SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 USED IN DETERMINING MFLCPR f-130, 1.951

~

135, 1.841 140, 1.491 A

B I 35.1, 1.53 I I

40.1, 1.31 I 152, 1.341 I

REFERENCE:

T.S. 3.4.1, 3.7.8, and 3.2.2 30 35 40 45 50 55 60 Total Core Flow (MLB/HR)

MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW BACKUP PRESSURE REGULATOR INOPE;RABLE SINGLE LOOP OPERATION (BOC TO EOC)

ATRIUM'-10 AND ATRIUM' 11 FUEL FIGURE 8.2-8 65 70

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-- CURVE A:

-- 26, 2.59 CURVE C: CORE POWER::; 26% AND CORE FLOW::; 50 MLBM/HR

._ 23, 2.63 ALL SCRAM INSERTION TIMES CURVE 8:

.... 26, 2.59

.... 23, 2.63 SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2

'- CURVE C:

A -s I

I I

I

.... 26, 2.55 USED IN DETERMINING MFLCPR 23, 2.63 C-M 26.01, 2.421 j40, 2.07 A

...... ~ -......... _

ISO, 2.01 I 160, 2.01

26.01, 2.24:

67.2, 2.011 140, 2.01 8 ~ 50, 2.0_1 1 I 60, 2.01 L__I 67.2, 2.011 W

REFERENCE:

T.S. 3.4.1, 3.7.8, and 3.2.2 !

10 20 30 40 50 60 Core Power (% RA TED)

MCPR OPERATING LIMIT VERSUS CORE POWER BACKUP PRESSURE REGULATOR INOPERABLE SINGLE LOOP OPERATION (BOC TO EOC)

ATRIUM'-10 AND ATRIUM' 11 FUEL FIGURE 8.2-9 70 80

o CD N

I\\J

Rev.22 One TSV or TCV Closed SUSQUEHANNA UNIT 1 TRM / 3.2-66 PL-NF-24-003 Rev. O Page 65 of 72

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-...J 1.6 1.4 1.2 1.0 SSES UNIT 1 CYCLE 24 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 3.7.6.2 130, 2.031 I

I USED IN DETERMINING MFLCPR 30 I

--.......... ~

140, 1.851 A

B 140.1, 1.59 I 152, 1.55 I I

REFERENCE:

T.S. 3.4.1, 3.2.2, and TRM 3.3.7 I 35

~

Total Core Flow (MLB/HR)

MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW ONE TSV OR TCV CLOSED SINGLE LOOP OPERATION (BOC TO EOC)

ATRIUM'-10 AND ATRIUM'-11 FUEL FIGURE 8.2-10 I

65 70

(J) 4.0 C

(J) 0 C

3.8 m

c z

3.6 z

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l:

2.4 I

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CX) 2.2 2.0 1.8 1.6 1.4 SSES UNIT 1 CYCLE 24 I

I I

I LEGEND CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME CURVE A:

CURVE C: CORE POWER :s; 26% AND CORE FLOW :s; 50 MLBM/HR

- 26, 2.59 23, 2.63 ALL SCRAM INSERTION TIMES I

I I

SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES CURVE B:

26, 2.59 ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2

- 23, 2.63 A

USED IN DETERMINING MFLCPR CURVE C:

-a

- 26, 2.55 23, 2.63 C

126.01, 2.421 40,. 2.01 L A _

J5o, 2.011 160, 2.01 67.2, 2.01:

126.01, 2.20 I I

140, 2.01 8- ~ 50, 2.01:

I 60, 2.01 LJ 67.2, 2.01 I

-J

REFERENCE:

T.S. 3.4.1, 3.2.2, and TRM 3.3. 7 !

10 20 30 40 50 60 Core Power(% RATED)

MCPR OPERATING LIMIT VERSUS CORE POWER ONE TSV OR TCV CLOSED SINGLE LOOP OPERATION (BOC TO EOC)

ATRIUM'-10 AND ATRIUM' 11 FUEL-FIGURE 8.2-11 70 I

80

a

~

I\\.)

Rev. 22 PL-NF-24-003 Rev.0 Page 68 of 72 9.0 POWER/ FLOW MAP 9.1 References 9.2 Technical Specification 3.3.1.1 Description 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 regi_on.

If the OPRM Instrumentation is inoperable per TS 3.3.1.1, Region I of the Power I Flow map is considered an immediate §£[fil!J. region.

Region 11 of the Power I Flow map is considered an immediate exit region regardless of the operability of the OPRM Instrumentation.

SUSQUEHANNA UNIT 1 TRM / 3.2-69

Q UJ i 110 100 90 Rev.22

Purpose:

Initial f Date:

I

.STABILITY REGfON I

--r-1--r-:--

IF OPRM INOPERABLE IMMEDIATELY

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SCRAM IAW APPLICABLE PROCEDURE-IFOl'RMOl'ERABLSIMMEDIATELY II-EXI r_lli_W_A_P_P_L_1c_*A_s_L_e_P_R_o_c_E_D_u_R_E. ____ -I *=tttt:

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I I

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I t

30 40 50 60 70 80 100 Total Core Flow (Mlbmlhr)

Figure 9.1 SSES Unit 1 Cycle 24 Power/ Flow Map 40 30 20 10 0

110 SUSQUEHANNA UNIT 1 TRM / 3.2-70

Rev. 22 10.0 OPRM SETPOINTS 10.1 References Technical Specification 3.3.1.1 10.2 Description PL-NF-24-003 Rev. O Page 70 of 72 Setpoints for the OPRM Instrumentation are established that will reliably detect and suppress anticipated stability related power oscillations while providing a high degree of confidence that the MCPRss.s% Safety limit is not violated. The setpoints are described in Section 2.0 and are listed below:

=

SUSQUEHANNA UNIT 1 1.11 15 60 Mlbm / hr TRM / 3.2-71

Rev. 22

11.0 REFERENCES

PL-NF-24-003 Rev. O Page 71 of 72 11.1 The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC, specifically those described in the following documents:

1. XN-NF-81-58(P)(A), Revision 2 and Supplements 1 and 2, "RODEX2 Fuel Rod Thermal-Mechanical Response Evaluation Model," Exxon Nuclear Company, March 1984.

2. EMF-2361 (P)(A), Revision 0, "EXEM BWR-2000 ECCS Evaluation Model,"

Framatome ANP, May 2001.

3. EMF-2292(P)(A), Revision 0, "ATRIUM'-10: Appendix K Spray Heat Transfer Coefficients," Siemens Power Corporation, September 2000.

4. XN-NF-80-19(P)(A), Volume 1 and Supplements 1 and 2, "Exxon Nuclear Methodology for Boiling 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 Boiling 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," 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, "SPCB 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-B2," 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 1 TRM / 3.2-72

Rev.22 PL-NF-24-003 Rev. O Page 72 of 72

13. NEDO-32465-A, "BWROG Reactor Core Stability Detect and Suppress Solutions Licensing Basis Methodology for Reload Applications," 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 Boiling Water Reactors," AREVA, Inc., April 2008.

16. ANP-10340P-A, Revision 0, "Incorporation of Chromia-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 Boiling 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-10247P-A Supplement 1P-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," Framatome Inc., August 2018.

SUSQUEHANNA UNIT 1 TRM / 3.2-73

ML24103A216

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