ML23195A034
| ML23195A034 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 07/06/2023 |
| From: | Susquehanna |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| PL-NF-23-002, Rev 1 | |
| Download: ML23195A034 (1) | |
Text
U U.L.
VO I L.UL..J MANUAL HARD COPY DISTRIBUTION DOCUMENT TRANSMITTAL 2023-9826 USER INFORMATION:
GERLACH*ROSEY M Address: NUCSA2 Phone#:
542-3194 EMPL#: 02 8401 CA#:
0363 TRANSMITTAL INFORMATION:
TO:
GERLACH*ROSEY M 07/06/2023 LOCATION:
USNRC FROM:
NUCLEAR RECORDS DOCUMENT CONTROL CENTER (NUCSA-2)
Page 1
THE FOLLOWING CHANGES HAVE OCCURRED TO THE HARDCOPY OR ELECTRONIC MANUAL ASSIGNED TO YOU.
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ATTENTION: "REPLACE" directions do not affect the Table of Contents, Therefore no TOC will be issued with the updated material.
TRM2 - TECHNICAL REQUIREMENTS MANUAL UNIT 2 REMOVE MANUAL TABLE OF CONTENTS DATE: 06/30/2023 ADD MANUAL TABLE OF CONTENTS DATE: 07/05/2023 CATEGORY: DOCUMENTS TYPE: TRM2 of 2
UU..L
- UO 1 L.UL..J ID:
TEXT 3.2.l ADD:
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REV:20 Page 2
ANY DISCREPANCIES WITH THE MATERIAL PROVIDED, CONTACT DCS@ X317l OR X3194 FOR ASSISTANCE.
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of 2
Rev.21 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 COMPLETION TIME Specified in referenced Technical Specifications.
=======;==
SURVEILLANCE FREQUENCY
NOTE-------------------------------------------
N/A No associated Surveillances. Surveillances are implemented in the applicable Technical Specifications.
SUSQUEHANNA - UNIT 2 TRM / 3.2-1
SSES MANUAL Manual Name:
TRM2
- .anual
Title:
TECHNICAL REQUIREMENTS MANUAL UNIT 2 Table Of Contents /
Issue Date:
07/05/2023
.\\
Procedure Name
/
Rev
/
Issue Date Change ID Change Nwnber e
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
TEXT 2.2 13
Title:
PLANT PROGRAMS AND TEXT 3.0 TEXT 3.1.1 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 21 07/05/2023
Title:
CORE OPERATING LIMITS REPORT (COLR)
Page 1 of 15 Report Date: 07/05/23
SSES MANUAL Manual Name:
TRM2
'anual
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 6
06/29/2023
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: 07/05/23
SSES MANUAL Manual Name:
TRM2
.lanual'Title: TECHNICAL REQUIREMENTS MANUAL UNIT 2 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:
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
'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: 07/05/23
SSES MANUAL Manual Name:
TRM2
!anual
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 3.7.3.1 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:
PLANT 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: 07/05/23
SSES MANUAL Manual Name:
TRM2
.'.anual
Title:
TECHNICAL REQUIREMENTS MANUAL UNIT 2 TEXT 3.7.5.1 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: 07/05/23
SSES MANUAL 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 ~OOM COOLING TEXT 3.8.7 3
02/25/2021
Title:
BATTERY MAINTENANCE AND MONITORING PROGRAM EXT 3.9.1 0
11/19/2002
Title:
REFUELI].':l"G OPERATIONS DECAY TIME TEXT 3.9.2 0
11/19/2002
Title:
REFUELING OPERATIONS COMMUNICATIONS TEXT 3.9.3 1
03/12/2019
Title:
REFUELING OPERATIONS REFUELING PLATFORM TEXT 3.10.1 1
04/26/2006
Title:
MISCELLANEOUS SEALED SOURCE CONTAMINATION TEXT 3.10.2 1
04/09/2007
Title:
MISCELLANEOUS SHUTDOWN MARGIN TEST RPS INSTRUMENTATION TEXT 3.10.3 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: 07/05/23
SSES MANUAL Manual Name:
TRM2
.anual
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 1
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 1
04/26/2006
Title:
RADIOACTIVE EFFLUENTS TOTAL DOSE Page 7 of 15 Report Date: 07/05/23
SSES MANUAL Manual Name:
TRM2
- anual
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 l
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: 07/05/23
SSES MANUAL Manual Name:
TRM2
.anual
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 BASES ANTICIPATED TRANSIENT WITHOUT SCRAM ALTERNATE ROD INJECTION (ATWS-ARI) INSTRUMENTATION TEXT B3.1.2 0
11/19/2002
Title:
REACTIVITY CONTROL SYSTEM BASES CONTROL ROD DRIVE (CRD) HOUSING SUPPORT TEXT B3.l.3 4
12/18/2017
Title:
REACTIVITY CONTROL SYSTEM BASES CONTROL ROD BLOCK INSTRUMENTATION EXT B3.l.4 1
10/12/2020
Title:
REACTIVITY CONTROL SYSTEM 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 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: 07/05/23
SSES MANUAL Manual Name:
TRM2
'anual
Title:
TECHNICAL REQUIREMENTS MANUAL UNIT 2 TEXT B3.3.6 7
06/29/2023
Title:
INSTRUMENTATION BASES TRM ISOLATION ACTUATION INSTRUMENTATION TEXT B3.3.7 4
01/17/2022
Title:
INSTRUMENTATION BASES MAIN TURBINE OVERSPEED 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: 07/05/23
SSES MANUAL Manual Name:
TRM2
.:anual
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 B3.7.3.1 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 15 Report Date: 07/05/23
SSES MANUAL Manual Name:
TRM2
- anual
Title:
TECHNICAL REQUIREMENTS 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 l
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.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 15 Report Date: 07/05/23
SSES MANUAL Manual Name:
TRM2
- anual
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.l 2
03/10/2010
Title:
ELECTRICAL POWER BASES PRIMARY CONTAINMENT PENETRATION CONDUCTOR OVERCURRENT PROTECTIVE DEVICES 0
11/19/2002 EXT B3.8.2.l
Title:
ELECTRICAL CONTINUOUS POWER BASES MOTOR OPERATED VALVES (MOV) THERMAL OVERLOAD PROTECTION -
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: 07/05/23
SSES MANUAL Manual Name:
TRM2
- anual
Title:
TECHNICAL REQUIREMENTS MANUAL UNIT 2 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.l 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.ll.1.2 0
11/19/2002
Title:
RADIOACTIVE EFFLUENTS BASES LIQUID EFFLUENTS DOSE TEXT B3.11.l.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.1.5 0
11/19/2002
Title:
RADIOACTIVE EFFLUENTS BASES RADIOACTIVE LIQUID PROCESS MONITORING INSTRUMENTATION TEXT B3.ll.2.1 1
12/14/2004
Title:
RADIOACTIVE EFFLUENTS BASES DOSE RATE Page 14 of 15 Report Date: 07/05/23
SSES MANUAL Manual Name:
TRM2
.ranual
Title:
TECHNICAL REQUIREMENTS MANUAL UNIT 2 TEXT B3. 11. 2. 2 0
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Title:
LOADS CONTROL PROGRAM BASES LIGHT LOADS REQUIREMENTS Page 15 of 15 Report Date: 07/05/23
Rev. 21 Susquehanna SES Unit 2 Cycle 22 PL-NF-23-002 Rev. 1 Page 1 of 72 CORE OPERA TING LIMITS
- REPORT SUSQUEHANNA UNIT 2 TRM / 3.2-2 Nuclear Fuels Engineering June 2023
REV AFFECTED NO.
SECTIONS 0
ALL 1
ALL Rev. 21 PL-NF-23-002 Rev. 1 Page 2 of 72 CORE OPERA TING LIMITS REPORT REVISION DESCRIPTION INDEX DESCRIPTION / PURPOSE OF REVISION Issuance of this COLR is in support of Unit 2 Cycle 22 operation.
Issuance of this COLR revision is to support change in LHGRFACf for base case, EOC-RPT INOP, and Backup Pressure Regulator INOP conditions.
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. 21 SUSQUEHANNA STEAM ELECTRIC STATION Unit 2 Cycle 22 CORE OPERA TING LIMITS REPORT Table of Contents PL-NF-23-002 Rev. 1 Page 3 of 72 INTRODUCTION........................................................................................................... 4 DEFINITIONS.....,......................................................................................................... 5 SHUTDOWN MARGIN.................................................................................................. 6 AVERAGE PLANAR LINEAR HEAT GENERATION RATE (APLHGR)....................... 7 MINIMUM CRITICAL POWER RATIO (MCPR)............................................................ 10 LINEAR HEAT GENERATION RA TE (LHGR).............................................................. 28 ROD BLOCK MONITOR (RBMj 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.21
1.0 INTRODUCTION
PL-NF-23-002 Rev. 1 Page 4 of 72 This,CORE OPERATING LIMITS REPORT for Susquehanna Unit 2 Cycle 22 is prepared in accordance with the requirements of Susquehanna Unit 2, Technical Specification 5.6.5.. As required by Technical Specifications 5.6.5, core shutdown margin, the core operating limits, RBM setpoints, and OPRM setpoints presented herein were developed using 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.21 PL-NF-23-002 Rev. 1 Page 5 of 72 2.0 DEFINITIONS Terms used in this COLR but not defined in Section 1.0 of the Technical Specifications or Section 1.1 of the Technical Requirements Manual are provided below.
2.1 The AVERAGE PLANAR EXPOSURE at a specified height shall be equal to the total energy produced per unit length at the specified height divided by the total initial weight of uranium per unit length at that height.
2.2 The PELLET EXPOSURE shall be equal to the total energy produced per unit length of fuel rod at the specified height divided by the total initial weight of uranium per unit length of that rod at that height.
2.3 FDLRX is the ratio of the maximum LHGR calculated by the core monitoring system for each fuel bundle divided by the LHGR limit for the applicable fuel bundle type.
2.4, LHGRFACt is a multiplier applied to the LHGR limit when operating at less than 108 Mlbm/hr core flow. The LHGRFACf multiplier protects against both fuel centerline melting and cladding strain during anticipated system transients initiated from core flows less than 108 Mlbm/hr.
2.5 LHGRFACp is a multiplier applied to the LHGR limit when operating at less than 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 MCPR99.9% 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 MCPR99.9% 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.
2.10 Sp is the OPRM trip setpoint for the peak to average OPRM signal.
2.11 F P is the core flow, in Mlbm / hr, below which the OPRM RPS trip is activated.
SUSQUEHANNA UNIT 2 TRM / 3.2-6
Rev.21 PL-NF-23-002 Rev. 1 Page 6 of 72 3.0 SHUTDOWN MARGIN 3.1 References 3.2 Technical Specification 3.1.1 Description The SHUTDOWN MARGIN shall be equal to or greater than:
a) 0.38% ~k/k with the highest worth rod analytically determined b) 0.28% ~k/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 2 TRM / 3.2-7
Rev. 21 PL-NF-23-002 Rev. 1 Page 7 of 72 4.0 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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10000 20000 30000 40000 50000 Average Planar Exposure (MWD/MTU)
AVERAGE PLANAR LINEAR HEAT GENERATION RATE LIMIT VERSUS AVERAGE PLANAR EXPOSURE - TWO LOOP OPERATION ATRIUM' 11 FUEL FIGURE 4.2-1B 60000 70000 "U
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Rev.21 PL-NF-23-002 Rev. 1 Page 10 of 72 5.0 MINIMUM CRITICAL POWER RA TIO (MCPR) 5.1 References 5.2 Technical Specification 3.2.2, 3.3.4.1, 3.7.6, and 3.7.8 Technical Requirements Manual 3.3.7 Description For Unit 2 Cycle 22, the MCPR99.9% Safety Limit is 1.07 for Two Loop operation and 1.09 for Single Loop operation.
The MGPR 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 MCJ?R, 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 ATRIUM'-10 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
Figure 5.2-9:
Figure 5.2-10:
Rev. 21 PL-NF-23-002 Rev. 1 Page 11 of 72 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
, 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 2 TRM / 3.2-12
Rev.21 PL-NF-23-002 Rev. 1 Page 12 of 72 Main Turbine Bypass/ EOC-RPT /
Backup Pressure Regulator Operabie SUSQUEHANNA UNIT 2 TRM / 3.2-13
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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)
ATRIUM'-10 AND ATRIUM'11 FUEL FIGURE 5.2-1
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26, 2.61 ALL SCRAM INSERTION TIMES 23, 2.84 CURVE B:
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10 20 30 40 50 60 70 80 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 90 100
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Rev. 21 Main Turbine Bypass Inoperable SUSQUEHANNA UNIT 2 TRM / 3.2-16 PL-N F-23-002 Rev. 1 Page 15 of 72
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MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW MAIN TURBINE BYPASS INOPERABLE TWO LOOP OPERATION (BOC TO EOC)
ATRIUM'-10 AND ATRIUM' 11 FUEL FIGURE 5.2-3 100 110
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CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM 26, 3.16 INSERTION TIME 23, 3.51 CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME CURVE B:
CURVE C: CORE POWER s 26% AND CORE FLOW s 50 MLBM/HR I-26, 3.16
\\A MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME I-23, 3.51
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- 20 30 40 50 60 70 Core Power(% RATED)
MCPR OPERATING LIMIT VERSUS CORE POWER MAIN TURB[NE BYPASS INOPERABLE TWO LOOP OPERATION (BOC TO EOC)
ATRIUM'-10 AND ATRIUM' 11 FUEL FIGURE 5.2-4 80 90 100
SUSQUEHANNA UNIT 2 Rev. 21 EOC-RPT Inoperable TRM / 3.2-19 PL-NF-23-002 Rev. 1 Page 18 of 72
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USED IN DETERMINING MFLCPR I40.0, 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)
ATRIUM'-10 AND ATRIUM' 11 FUEL FIGURE 5.2-5 100 L
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26, 2.61 23, 2.84 CURVE B:
26, 2.61 23, 2.84
- CURVE C:
_ 26, 2.59 23, 2.84 CURVED:
26, 2.59 23, 2.84 SSES UNIT 2 CYCLE 22 LEGEND CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME CURVE C: CORIE POWER :s: 26% AND <::ORE FLOW :s: 50 MLBM/HR MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME CURVE D: CORIE POWER :s: 26% AND CORE FLOW :s: 50 MLBM/HR REALISTIC AVERAGE SCRAM INSERTION TIME SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE
'-A PER SR 3.7.6.1 AND 3.7.6.2 c---\\B I
t USED IN DETERMINING MFLCPR
_D_ 7 26.01, 2.411 I 40, 2.121 J 50, 2.121
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REFERENCE:
T.S. 3.3.4.1 and 3.2.21 180, 1.60 I 190, 1.57 r 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
- a (D
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Rev.21 PL-NF-23-002 Rev. 1 Page 21 of 72 Backup Pressure Regulator Inoperable SUSQUEHANNA UNIT 2 TRM / 3.2-22
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I 2.2 SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES 2.1 H 30.0, 2.06 :
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REFERENCE:
T.S. 3.7.8 and 3.2.2:
1.2 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)
ATRIUM'-10 AND ATRIUM' 11 Fl:JEL FIGURE 5.2-7
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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 ALL SCRAM INSERTION TIMES CURVE B:
26, 2.61 I
23, 2.84 A
SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES
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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
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Rev. 21 One TSV or TCV Closed SUSQUEHANNA UNIT 2 TRM / 3.2-25 PL-NF-23-002 Rev. 1 Page 24 of 72
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SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2
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REFERENCE:
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MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW ONE TSV OR TCV CLOSED*
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SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE
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PER SR 3.7.6.1 AND 3.7.6.2 a-*
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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)
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~---....
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Rev.21 Table 5.3-1 PL-NF-23-002 Rev. 1 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 2 TRM / 3.2-28 J
Rev.21 PL-NF-23-002 Rev. 1 Page 28 of 72 6.0 LINEAR HEAT GENERATION RATE (LHGR) 6.1 6.2 References 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 6.2-18, 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 2 TRM / 3.2-29
Figure 6.2-9:
Rev. 21 PL-NF-23-002 Rev. 1 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 6.2-1 O:
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/6.2-1B 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
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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 2 TRM / 3.2-48
Rev. 21 Function Low Power Range Setpoint Table 7.2-1 RSM 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. 1 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.
(2)
(3)
Table 7.2-2 RSM System Operability Requirements Thermal Power MCPR (2,3Al
(% of Rated)
- 28 and< 90
< 1.78
- 90 and< 95
< 1.47
~95
< 1.68 Applicable to Main Turbine Bypass Operable and Inoperable, EOC-RPT Operable and Inoperable, Backup Pressure Regulator Operable and Inoperable, and one TCV/TSV closed.
Applicable to both Two Loop and Single Loop Operation.
(4l Applicable to both ATRIUM-10 and ATRIUM 11 Fuel.
SUSQUEHANNA UNIT 2 TRM / 3.2-49
8.0 Rev. 21 PL-NF-23-002 Rev. 1 Page 49 of 72 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 EOC for ATRIUM'-10 and ATRIUM' 11 Fuel b)
Main Turbine Bypass Inoperable c)
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 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 2 TRM / 3.2-50
Rev. 21 PL-N F-23-002 Rev. 1 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% RA TED 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.
RSM Setpoints and Operability Requirements The RSM setpoints and operability requirements for Single Loop Operation are defined in Section 7.0.
SUSQUEHANNA UNIT 2 TRM / 3.2-51
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AVERAGE PLANAR LINEAR HEAT GENERATION RATE LIMIT VERSUS AVERAGE PLANAR EXPOSURE - SINGLE LOOP OPERATION ATRIUM' 11 FUEL FIGURE 8.2-1 B 60000 70000
-a
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I Rev. 21 PL-NF-23-002 Rev. 1 Page 53 of 72 Main Turbine Bypass/ EOC-RPT /
Backup Pressure Regulator Operable SUSQUEHANNA UNIT 2 TRM / 3.2-54
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1 (J1 (J1 1.6 1.4 1.2 1.0 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 3.7.6.2 130.0, 2.06 I r---,.....__
I USED IN DETERMINING MFLCPR I
---.... ~
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- A B 140.1, 1.41 I I 52.0, 1.38 I
REFERENCE:
T.S. 3.4.1 and 3.2.21 30 35 40 45 50 55 60 65 Total Core Flow (MLB/HR)
MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW MAIN TURBINE BYPASS / EOC-RPT I BACKUP PRESSURE REGULATOR OPERABLE SINGLE LOOP OPERATION (BOC TO EOC)
ATRIUM'-10 AND ATRIUM' 11 FUEL FIGURE 8.2-2 70
- u CD <
N
Cl) 4.0 C
Cl) 0 C
3.8 m
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CURVE C: CORE POWER :s; 26% AND CORE FLOW :s; 50 MLBM/HR
- 26, 2.63 23, 2.86 ALL SCRAM INSERTION TIMES I
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- CURVE B:
SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES 26, 2.63 ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2
- 23, 2.86
\\. A
\\.. B USED IN DETERMINING MFLCPR CURVE C:
C '
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- 26.01, 2.43 :
40, 2.09 A-H 5o, 2.09:
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, so, 2.00 67.2, 2.00 I H
REFERENCE:
T.S. 3.4.1 and 3.2.2:
10 20 30 40 50 60 70 Coire Power(% RATED)
MCPR OPERATING LIMIT VERSUS CORE POWER MAIN TURBJNE BYPASS/ EOC-RPT / BACKUP PRESSURE REGULATOR OPERABLE SINGLE LOOP OPERATION (BOC TO EOC)
ATRIUM'-10 AND ATRIUM' 11 FUEL FIGURE 8.2-3 I
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Rev.21 Main Turbine Bypass Inoperable SUSQUEHANNA UNIT 2 TRM / 3.2-57 PL-NF-23-002 Rev. 1 Page 56 of 72
en 3.0 C en 0
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I USED IN DETERMINING MFLCPR 30
---.... ~
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REFERENCE:
T.S. 3.4.1, 3.7.6, and 3.2.2 I 35 40 45 50 55 Total Core Flow (MLB/HR)
MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW MAIN TURBINE BYPASS INOPERABLE SINGLE LOOP OPERATION (BOC TO EOC)
ATRIUM'-'10 AND ATRIUM' 11 FUEL FIGURE 8.2-4 60 65 L
70
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LEGEND CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM CURVE A:
INSERTION TIME 26, 3.18 23, 3.54 CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME A
CURVE C: CORE POWER :s; 26% AND CORE FLOW :s; 50 MLBM/HR CURVE B:
I
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MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME 26, 3.18
\\
____ B 23, 3.54
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CURVE D: CORE POWER::. 26% AND CORE FLOW::. 50 MLBM/HR REALISTIC AVERAGE SCRAM INSERTION TIME
... CURVE C:
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... 23, 2.86 VALVES ARE INOPERABLE PER SR 3.7.6.1 OR 3.7.6.2
-c \\.
I
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CURVED: -o USED IN DETERMINING MFLCPR
\\
26, 2.61 23, 2.86 I 26.01, 2.46
..... -... i.....,
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- 26.01, 2.27 :
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- 40, 2.00 8- ~50, 2.00:
- 60, 2.00 67.2, 2.00 I H
REFERENCE:
T.S. 3.4.1, 3.7.6, and 3.2.2 1 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 r
80
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(Q I
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SUSQUEHANNA UNIT 2 Rev. 21 EOC-RPT Inoperable TRM / 3.2-60 PL-NF-23-002 Rev. 1 Page 59 of 72
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I I
I SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 130, 2.061 r-----.........
I USED IN DETERMINING MFLCPR I
30
............. ~
140, 1.861 A
B I 40.1, 1.41 I 152, 1.38 I
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)
ATRIUM'-'10 AND ATRIUM'11 FUEL FIGURE 8.2-6 60 65 70
- u CD <
N
CJ) 4.4 C
CJ) 0 4.2 C m
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3.4 E 3.2
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w
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N 2.4 2.2 2.0 1.8 1.6 1.4 SSES UNIT 2 CYCLE 22 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, 2.63 MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME
... 23, 2.86 CURVE D: CORE POWER :s; 26% AND CORE FLOW :s; 50 MLBM/HR REALISTIC AVERAGE SCRAM INSERTION TIME
... CURVE B:
26, 2.63
,.. 23, 2.86 SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 CURVE C:
'- A I
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26, 2.61.
'\\. B USED IN DETERMINING MFLCPR 23, 2.86 -c '
D
- 26.01, 2.43 :
_CURVED:
26, 2.61 23, 2.86 40,2.14[
A Jso,2.14I I 26.01, 2.25 i l 60, 2.01 67.2, 2.00 t
- 4o, 2.00 B-7 50, 2.00:
160, 2.00 67.2, 2.00 I
REFERENCE:
T.S. 3.4.1, 3.3.4.1, and 3.2.2 I 10 20 30 40 50 60 Core Power (% RA TED)
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 80
- 0 CD N
7J 7J ID r
(0 I
CD z
- 0) 71
->. :::0 N 0
CD Cf
-<o
-....i*
0 N
->. N
Rev. 21 PL-NF-23-002 Rev. 1 Page 62 of 72 Backup Pressure Regulator Inoperable SUSQUEHANNA UNIT 2 TRM / 3.2-63
Cl) 3.0 C
Cl) 0 C m 2.8
- c
)> z z
)>
C 2.6 z
N 2.4
.... *e 2.2
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C
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0 s:
ll.
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t.)
1.8 N
- a; I
O')
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1.6 1.4 1.2 1.0 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 3.7.6.2 130, 2.06 I USED IN DETERMINING MFLCPR
--..... ~
140, 1.861 A
B I 52, 1.38 I 140.1, 1.41 I 7
REFERENCE:
T.S. 3.4.1, 3.7.8, and 3.2.2 1
30 35 40 45 50 55 60 Total Core Flow (MLB/HR)
MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW BACKUP PRESSURE REGULATOR INOPERABLE SINGLE LOOP OPERATION (BOC TO EOC)
ATRIUM'--10 AND ATRIUM' 11 FUEL FIGURE 8.2-8 65 70
- o CD <
N
(/)
4.0 C
(/)
0 C
3.8 m
I )>
z 3.6 z
)>
C 3.4 z
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N 2.4 I
~
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Cl)
CJ1 C.
0 2.2 a:::
D.
(.) a 2.0 1.8 1.6 1.4 SSES UNIT 2 CYCLE 22 LEGEND CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME
-- CURVE A:
26, 2.63 CURVE C: CORE POWER~ 26% AND CORE FLOW~ 50 MLBM/HR
'-- 23, 2.86 ALL SCRAM INSERTION TIMES CURVE B:
- 26, 2.63 SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES*
..., 23, 2.86 A
\\.
ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2
\\. B I
... CURVE C:
C '
.... 26, 2.61 USED IN DETERMINING MFLCPR 23, 2.86 I 26.01, 2.43 I l
- 4o, 2.os A H so, 2.os:
-r--,.....__
I 26.01, 2.25 I
~ GO, 2*00 h 67.2, 2.00 I 1----------.... ____
- 40, 2.00 B* H so, 2.90:
I
- so, 2.00 67.2, 2.00 I
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)
ATRIUM'-10 AND ATRIUM'11 FUEL FIGURE 8.2-9 70 80
- a CD l'v
Rev. 21 One TSV or TCV Closed SUSQUEH~NNA UNIT 2 TRM / 3.2-66 PL-NF-23-002 Rev. 1 Page 65 of 72
C/)
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)>
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C =
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s:
0 0::
c..
w
(.)
is.>
~
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--...j SSES UNIT 2 CYCLE 22 3.0 LEGEND 2.8 CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME 2.6 CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME 2.4 I.
SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES 2.2 H3o, 2.16 1 ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 2.0 ~
~
I I
- 40, 1.941 USED IN DETERMINING MFLCPR I
I 1.8 A
B 1.6 152, 1.551 I 40.1, 1.59 I 1.4 1.2
REFERENCE:
T.S. 3.4.1, 3.2.2, and TRM 3.3.7 I 1.0 30 35 40 45 50 55 Total Core Flow (MLB/HR)
MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW ONE TSV OR TCV CLOSED SINGLE LOOP OPERATION (BOC TO EOC)
ATRIUM'-10AND ATRIUM'11 FUEL FIGURE 8.2-10 60 65 70
(J) 4.0 C
(J) 0 C
3.8 m
I )>-z 3.6 z
)>
C 3.4 z
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3.2 E
3.0
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2.8 cu...
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s:
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ll.
w
(.)
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- iE 2.4 I en OJ 2.2 2.0 1.8 1.6 1.4 SSES UNIT 2 CYCLE 22 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, 2.63 ALL SCRAM INSERTION TIMES 23, 2.86 I
I I
SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES CURVE 8:
26, 2.63 ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 23, 2.86
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REFERENCE:
T.S. 3.4.1, 3.2.2, and TRM 3.3.7:
10 20 I
I 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 80
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Rev.21 P L-N F-23-002 Rev. 1 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/ 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/ 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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-<****-*--*-*1-->-1--r---:--;-- --;-7--:--1-+***-**1--*--*-1 PL-NF-23-002 Rev. 1 Page 69 of 72 120 110 100 90 80 70 60 50 40 30 20 10 D..-:;=:j...+-,i-jP"l\\\\!::::.-i---i--i-+oi!=:j...-l-+-,i-,i--i..4-i--+-i-++4'-+'-+'+!..1..~*,4',4'-+'-'-++++--1-+-,.....,i--i..4-+-i--i-++++-+-
O 0
10 20 SUSQUEHANNA UNIT 2 30 40 50 00 70 80 Total core Flow (Mlbmlhr)
Figure 9.1 SSES Unit 2 Cycle 22 Power I Flow Map TRM /3.2-70 90 100 110
Rev. 21 10.0 OPRM SETPOINTS 10.1 References Technical Specification 3.3.1.1 10.2 Description PL-NF-23-002 Rev. 1 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 MCPR99.9% 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. 21
11.0 REFERENCES
PL-NF-23-002 Rev. 1 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-82," Siemens Power Corporation, October 1999.
- 12. EMF-CC-074(P)(A), Volume 4, Revision 0, 11BWR Stability Analysis -
Assessment of STAIF with Input from MICROBURN-82," Siemens Power Corporation, August 2000.
SUSQUEHANNA UNIT 2 TRM / 3.2-72
Rev. 21 PL-NF-23-002 Rev.1 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, lnc., 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 2 TRM / 3.2-73