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
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Page 1 of 2
- MANUAL HARD COPY DISTRIBUTION DOCUMENT TRANSMITTAL 2023-9826
USER INFORMATION:
GERLACH*ROSEY M EMPL#: 02 8401 CA#: 0363 Address: NUCSA2 Phone#: 542-3194
TRANSMITTAL INFORMATION:
TO: GERLACH*ROSEY M 07/06/2023 LOCATION: USNRC FROM: NUCLEAR RECORDS DOCUMENT CONTROL CENTER (NUCSA-2)
THE FOLLOWING CHANGES HAVE OCCURRED TO THE HARDCOPY OR ELECTRONIC MANUAL ASSIGNED TO YOU. HARDCOPY USERS MUST ENSURE THE DOCUMENTS PROVIDED MATCH THE INFORMATION ON THIS TRANSMITTAL. WHEN REPLACING THIS MATERIAL IN YOUR HARDCOPY MANUAL, ENSURE THE UPDATE DOCUMENT ID IS THE SAME DOCUMENT ID YOU'RE REMOVING FROM YOUR MANUAL. TOOLS OM THE HUMAN PERFORMANCE TOOL BAG SHOULD BE UTILIZED TO ELIMINATE THE CHANCE OF
- RORS.
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
UU..L
- UO 1 L.UL..J
Page 2 of 2 ID: TEXT 3.2.l ADD: REV: 21
REMOVE: REV:20
ANY DISCREPANCIES WITH THE MATERIAL PROVIDED, CONTACT DCS@ X317l OR X3194 FOR ASSISTANCE. UPDATES FOR HARDCOPY MANUALS WILL BE DISTRIBUTED WITHIN 3 DAYS IN ACCORDANCE WITH DEPARTMENT PROCEDURES. PLEASE MAKE ALL CHANGES AND ACKNOWLEDGE COMPLETE IN YOUR NIMS INBOX UPON COMPLETION OF UPDATES. FOR ELECTRONIC MANUAL USERS, ELECTRONICALLY REVIEW THE APPROPRIATE DOCUMENTS AND ACKNOWLEDGE COMPLETE IN YOUR NIMS INBOX.
COLR Rev.21 3.2.1
3.2 Core Operating Limits Report (COLR)
3.2.1 Core Operating Limits Report (COLR)
TRO 3.2.1 The Core.Operating Limits specified in the attached COLR shall be met.
APPLICABILITY: Specified in the referenced Technical Specifications.
ACTIONS
CONDITION REQUIRED ACTION COMPLETION TIME
A. Core Operating Limits A.1 Perform action(s) described in Specified in not met. referenced Technical referenced Technical Specification. Specifications.
TECHNICAL REQUIREMENT SURVEILLANCE=============;========
SURVEILLANCE FREQUENCY
NOTE------------------------------------------- N/A No associated Surveillances. Surveillances are implemented in the applicable Technical Specifications.
SUSQUEHANNA - UNIT 2 TRM / 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
/ 99 01/03/2019 TEXT LOES /
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 03/05/2015
Title:
PLANT SYSTEMS SNUBBERS
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
Title:
ELECTRICAL POWER MOTOR OPERATED VALVES (MOV) THERMAL OVERLOAD PROTECTION -
AUTOMATIC Page 5 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 EXT B3.8.2.l 0 11/19/2002
Title:
ELECTRICAL POWER BASES MOTOR OPERATED VALVES (MOV) THERMAL OVERLOAD PROTECTION -
CONTINUOUS
TEXT B3.8.2.2 2 06/23/2021
Title:
ELECTRICAL POWER BASES MOTOR OPERATED VALVES (MOV) THERMAL OVERLOAD PROTECTION -
AUTOMATIC TEXT B3.8.3 0 11/19/2002
Title:
ELECTRICAL POWER BASES DIESEL GENERATOR (DG) MAINTENANCE ACTIVITIES
TEXT B3.8.4 0 11/19/2002
Title:
ELECTRICAL POWER BASES 24 VDC ELECTRICAL POWER SUBSYSTEM
. TEXT B3. 8. 5 1 11/14/2013
Title:
ELECTRICAL POWER BASES DEGRADED VOLTAGE PROTECTION
TEXT B3.8.6 4 03/05/2019
Title:
ELECTRICAL POWER BASES EMERGENCY SWITCHGEAR ROOM COOLING
TEXT B3.8.7 3 02/25/2021
Title:
BATTERY MAINTENANCE AND MONITORING PROGRAM Page 13 of 15 Report Date: 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 11/19/2002
Title:
RADIOACTIVE EFFLUENTS BASES DOSE - NOBLE GASES
TEXT B 3. 11. 2. 3 0 11/19/2002
Title:
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LOADS CONTROL PROGRAM BASES LIGHT LOADS REQUIREMENTS Page 15 of 15 Report Date: 07/05/23 Rev. 21 PL-NF-23-002 Rev. 1 Page 1 of 72
Susquehanna SES Unit 2 Cycle 22
- - REPORT CORE OPERA TING LIMITS -
Nuclear Fuels Engineering
June 2023
SUSQUEHANNA UNIT 2 TRM / 3.2-2 Rev. 21 PL-NF-23-002 Rev. 1 Page 2 of 72
CORE OPERA TING LIMITS REPORT REVISION DESCRIPTION INDEX REV AFFECTED NO. SECTIONS DESCRIPTION / PURPOSE OF REVISION
0 ALL Issuance of this COLR is in support of Unit 2 Cycle 22 operation.
1 ALL 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 Rev. 21 PL-NF-23-002 Rev. 1 Page 3 of 72
SUSQUEHANNA STEAM ELECTRIC STATION Unit 2 Cycle 22 CORE OPERA TING LIMITS REPORT
Table of Contents
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 RA TE (LHGR).............................................................. 28
7.0 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 PL-NF-23-002 Rev. 1 Page 4 of 72
1.0 INTRODUCTION
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 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
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.
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- =..J : : : : : : : : : : : : : I : : : : I I : I : I : I I I I : I I,, 69000, 7.2
--+--+--~--- ------ ---t---t---+---t---t---t---r---r--+--+--~--- --- --- ---t---t---+---t---t---~---r---r---r--+--~--- --- --- ---..-----~ I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I 1 I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I 6.0 --+--+--~---~--- --- ---+---+---1/2---1/4---1/4---~---~---~--+--+--~---~---~--- ---+---+---+---1/4---~---~---~---~---~--+--+--~---~---~---1 I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I J I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I 1-I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I
--...,..---,---~---~---,---,---~---T---T---~---r---r---~---r--...,..---,---~---,---,---,---~---T---~---r---~---r---r---r---~---,----.---,---,---,---1 I I I I I I I I I I I I I I I I I I I I I I I I I I I I I J I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I 4.0 0 10000 20000 30000 40000 50000 60000 70000 Average Planar Exposure (MWD/MTU) "U "U r;-
Q) z AVERAGE PLANAR LINEAR HEAT GENERATION RATE LIMIT VERSUS cc "Tl AVERAGE PLANAR EXPOSURE - TWO LOOP OPERATION CD I ATRIUM' 11 FUEL co :::0 N 0 CD 'f FIGURE 4.2-1B <O
-. 0 N....>.N Rev.21 PL-NF-23-002 Rev. 1 Page 10 of 72
5.0 MINIMUM CRITICAL POWER RA TIO (MCPR)
5.1 References
Technical Specification 3.2.2, 3.3.4.1, 3.7.6, and 3.7.8
Technical Requirements Manual 3.3.7
5.2 Description
For Unit 2 Cycle 22, the 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: Flow-Dependent MCPR value determined from BOC to EOC for ATRIUM'-10 and ATRIUM' 11 Fuel
Figure 5.2-2: 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: Flow-Dependent MCPR value determined from BOC to EOC for ATRIUM'-10 and ATRIUM' 11 Fuel
Figure 5.2-4: Power-Dependent MCPR value determined from BOC to EOC for ATRIUM'-10 and ATRIUM' 11 Fuel
Figure 5.2-5: Flow-Dependent MCPR value determined from BOC to EOC for ATRIUM'-10 and ATRIUM' 11 Fuel
Figure 5.2-6: 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: Flow-Dependent MCPR value determined from BOC to EOC for ATRIUM'-10 and ATRIUM' 11 Fuel
Figure 5.2-8: Power Dependent MCPR value determined from BOC to EOC for ATRIUM'-10 and ATRIUM' 11 Fuel
e) One Turbine Stop Valve (TSV) or Turbine Control Valve (TCV) Closed
SUSQUEHANNA UNIT 2 TRM / 3.2-11 Rev. 21 PL-NF-23-002 Rev. 1 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 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
- SSES UNIT 2 CYCLE 22 *
- C en 2.6 0 en lEGEND
C 2.5 rn I CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM
- 2.4 - -- INSERTION TIME --
z z
C 2.3 CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME
-; z
N 2.2 SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES
- !: 2.1 7 30.0, 2.06 1 ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2
- J E I I I I
C') 2.0 USED IN DETERMINING MFLCPR
- .: s::::
/ '"
cu
-; Q)... 1.9 ~ '
- a 0 C. I 40.0, 1.86 I :::a
~ 0::: CD
-- C. 1.8 (.,J (.) :<
N N :E I ->.
->. 1.7
~
1.6
1.5 140.1, 1.41 I 1.4 A B
1.3 I
REFERENCE:
T.S. 3.2.2
1.2 -1108.0, 1.221 30 40 50 60 70 80 90 100 110 Total Core Flow (MLB/HR) -u -u (0 I D> r MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW CD z MAIN TURBINE BYPASS/ EOC-RPT / BACKUP PRESSURE REGULATOR OPERABLE ->. 71 TWO LOOP OPERATION (BOC TO EOC) vJ :::0 N ATRIUM'-10 AND ATRIUM'11 FUEL -<o 0 CD Cf
--i. 0 N ->-N FIGURE 5.2-1
- SSES UNIT 2 CYCLE 22
- Cl) 4.0 C I I I I I I...
Cl) 0 C 3.8 LEGEND -
m. -
- c
)> 3.6 CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME *. -
z z -
)> CURVE 8: REALISTIC AVERAGE SCRAM INSERTION TIME -
C 3.4 z CURVE C: CORE POWER~ 26% AND CORE FLOW s 50 MLBM/HR -
-I CURVE A:
N 3.2 26, 2.61 ALL SCRAM INSERTION TIMES -
23, 2.84 -
- !: 3.0
- J E CURVE B: SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE -
C) 2.8 26, 2.61 " A -
.I C 23, 2.84 \\. PER SR 3.7.6.1 AND 3.7.6.2 e 2.6 C ' B -
-I Cl) I
- .o Q. CURVEC
- : 26.01, 2.41 USED IN DETERMINING MFLCPR r ;.o s: 0 26, 2.59
(.,,) 0 a. 23, 2.84........ ~
- c::: 2.4 N N== I.................
..... 2.2 (J1 I I'"' - ~... 140, 2.071 I ""'"... _ 50, 2.071
I 26,01, 2.23 I........... "'II-------........., :so, 1.s6:
2.0................. r,70, 1.79;
1.8 :4o, 1.90: --- :so,1.73: --........... *-- A -
- 50, 1.89: ""- -- :9o, 1.&2I-.........
1.6 :so, 1.71: - -B -------1100, 1.561
- 10, 1.ss:
1.4 H
REFERENCE:
T.S. 3.2.2 I : 80, 1.57: -----190, 1.s2r 1100, 1.42!
1.2 '
10 20 30 40 50 60 70 80 90 100 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 Rev. 21 PL-N F-23-002 Rev. 1 Page 15 of 72
Main Turbine Bypass
SUSQUEHANNA UNIT 2 TRM / 3.2-16
- SSES UNIT 2 CYCLE 22 *
- en 2.5 C
en LEGEND -
D C 2.4 m CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME
- c
)>
z 2.3 CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME -
z
)> I I I I I -
C 2.2 z SAFETY ANALYSES ASSUME THAT TWO OR MORE BYPASS VALVES ARE
-I INOPERABLE PER SR 3.7.6.1 OR 3.7.6.2 N 2.1 M3o, 2.061.
USED IN DETERMINING MFLCPR
~ I
- J E 2.0
0)
- I C 1.9 '
- 4o, 1.ss:
-I 4) e
- a C. " " ;a s
- 0 1.8 ~ (D
-.. c.. <
w (.) N N :E 1.7 I...>.
-.J 1.6 :40.1, 1.56:
- A B 1.5
1.4 I
REFERENCE:
T.S. 3.7.6 and 3.2.2 I - 108, 1.341 1.3
1.2 30 40 50 60 70 80 90 100 110 Total Core Flow (MLB/HR).
MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW '
MAIN TURBINE BYPASS INOPERABLE TWO LOOP OPERATION (BOC TO EOC)
ATRIUM'-10 AND ATRIUM' 11 FUEL FIGURE 5.2-3
- SSES UNIT 2 CYCLE 22 *
- r:n 4.3 C
r:n LEGEND -
D 4.1 C CURVE A: CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM -
m I 26, 3.16 -INSERTION TIME
)> 3.9 23, 3.51 -
z z CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME -
)> 3.7 C -
z CURVE B: CURVE C: CORE POWER s 26% AND CORE FLOW s 50 MLBM/HR I-
-I 3.5 26, 3.16 \\A MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME I-N 23, 3.51 -
3.3 \\ B CURVE D: CORE POWERS 26% AND CORE FLOWS 50 MLBM/HR -
.... REALISTIC AVERAGE SCRAM INSERTION TIME I-
- e 3.1 CURVEC: I I I I I '
- i 26, 2.59 SAFETY ANALYSES ASSUME THAT TWO OR MORE BYPASS VALVES ARE i-a, 23, 2.84 C
~ 2.9 INOPERABLE PER SR 3.7.6.1 OR 3.7.6.2 -
-I Cl> ' \\
- o Q. 2.7 CURVED
- -c s: 0 a:: 26, 2.59 ' USED IN DETERMINING MFLCPR ~
- ll.. 23, 2.84 D :
w 0 2.5 26.01, 2.44:
i-.J :ii I to.........
OJ 2.3
.... -... 1... 40, 2.01i
~ -... ISO, 2.071 2.1 j 26.01, 2.25 j '-,..,.......... "II--------*...., -... :
...... - H 60, 1.86 A 1.9 10, 1.02 i I................. lso, 1.14L 140,1.901 --....._ ---------------- J90, 1.69I-_,_ *-----
1.7 150, 1.90 1....... 1100, 1.691
~
- 60, 1.71 ~ 1100, 1.ss 1 1.5 W
REFERENCE:
T.S. 3.7.6 and 3.2.21 B_ ~ 70, 1.66 I I BO, 1.58 I 190, 1.551
1.3 I 10
- 20 30 40 50 60 70 80 90 100 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 Rev. 21 PL-NF-23-002 Rev. 1 Page 18 of 72
SUSQUEHANNA UNIT 2 TRM / 3.2-19
- SSES UNIT 2 CYCLE 22 *
- CJ) 2.6 C
CJ) LEGEND 0
C 2.5 -
m CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM I - INSERTION TIME 2.4 -
z z CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME
C 2.3 -
z
--l,...._
N 2.2 SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2,...._
- l 30.0, 2.06 I
'§ 2.1
- J K USED IN DETERMINING MFLCPR L C'I 2.0
- C
E! 1.9
--l a, I40.0, 1.86 I
- o C. ;;o s
- 0 0
- : 1.8 "' ' CD
{.,.) (.) C. <
- N rv 2 I _,._
N 1.7 0
1.6
1.5 140.1, 1.411 1.4 - A B
1.3 1
REFERENCE:
T.S. 3.3.4.1 and 3.2.2 :
I 108.0, 1.221 1.2 30 40 50 60 70 80 90 100 110 Total Core Flow (MLB/HR) "U "U
!l) ~
MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW ca Z CD ;,
EOC-RPT INOPERABLE co ;;CJ N -->. I TWO LOOP OPERATION (BOC TO EOC) -<o 0 CD Cf ATRIUM'-10 AND ATRIUM' 11 FUEL ----i* 0 FIGURE 5.2-5 N -"-N
- SSES UNIT 2 CYCLE 22 *
- en 4.3 C
en LEGEND 0 4.1 C
m CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM
- c
)> -3.9 INSERTION TIME z
z CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME
)> CURVE A:
C 3.7 26, 2.61 z 23, 2.84 CURVE C: CORIE POWER :s: 26% AND <::ORE FLOW :s: 50 MLBM/HR
-I 3.5 MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME N
3.3 CURVE B: CURVE D: CORIE POWER :s: 26% AND CORE FLOW :s: 50 MLBM/HR
- 26, 2.61 REALISTIC AVERAGE SCRAM INSERTION TIME E 3.1 23, 2.84
- J C) SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE
- . 2.9 C - CURVE C
ltl
... _ 26, 2.59 '-A PER SR 3.7.6.1 AND 3.7.6.2
-I a, 23, 2.84 I t
- a C. 2.7 0 c---\\B ;a s
- a: USED IN DETERMINING MFLCPR (D
-- D. u.) (.) 2.5 CURVED: _D_ 7 26.01, 2.411 :<
N 2 N I 26, 2.59....>.
N 23, 2.84............ I
....>. 2.3...
... _ 40, 2.121 J 50, 2.121 2.1 26.01, 2.231 -.................... =-""-............ -------* -... 160,1.99 1
_ A_ H10, 1.90: _________
1.9 -.........._..
--........_ -... 180,1.741 _ 190, 1.73 ~
- 4o, 1.90:......
I 1-............. -..... --------------- 1100, 1.731 1.7 150, 1.891 I 60, 1.72 8_ U10, 1.61L LJ I 1100, 1.s6I 1.5
REFERENCE:
T.S. 3.3.4.1 and 3.2.21 180, 1.60 I 190, 1.57 r
1.3 10 20 30 40 50 60 70 80 90 100 Core Power(% RATED)
MCPR OPERATING LIMIT VERSUS CORE POWER EOC-RPT INOPERABLE TWO LOOP OPERATION (BOC TO EOC)
ATRIUM'-10 AND ATRIUM' 11 FUEL FIGURE 5.2-6 Rev.21 PL-NF-23-002 Rev. 1 Page 21 of 72
Backup Pressure Regulator Inoperable
SUSQUEHANNA UNIT 2 TRM / 3.2-22
- SSES UNIT 2 CYCLE 22 *
- en 2.6 I C
en LEGEND 0
C 2.5 m CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM
- r
)> 2.4 INSERTION TIME -
z z
)>
C 2.3 CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME z
-I I I I I N 2.2 SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES
~ 2.1 H 30.0, 2.06 : ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 ~
E I I I I
- i ~ USED IN DETERMINING MFLCPR ~
Cl) 2.0 I
- l C
-I Q) I:! 1.9 :4o.o, 1.ss 1
- o Q. ~
s: 0 0:: 1.8 "*
- 0.
w (.)
N al I N 1.7 w
1.6
1.5 140.1, 1.411 1.4 - A B
1.3 i
REFERENCE:
T.S. 3.7.8 and 3.2.2:
1.2 -1108.0, 1.221 30 40 50 60 70 80 90 100 110 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
- SSES UNIT 2 CYCLE 22 * *
(J) 4.0 C -
(J) 0 C 3.8 LEGEND m
I
)> 3.6 CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM...
z INSERTION TIME z
)>
C 3.4 CURVE A: CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME z 26, 2.61
-I 23, 2.84 CURVE C: CORE POWER :s; 26% AND CORE FLOW :s; 50 MLBM/HR N 3.2 ALL SCRAM INSERTION TIMES
- !: 3.0 CURVE B:
E 26, 2.61 I
- J 23, 2.84 '- A SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES
C) 2.8
- .:: C... CURVE C: \\ B ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 cu I
... 2.6 26, 2.59 ' -c ~
-I Cl) C. 23, 2.84 USED IN DETERMINING MFLCPR
- a 0 - I 26.01, 2.411 :::a
~ 0:: (D
- C. 2.4................... :<
w u N N 2 I... 1......
N 2.2... 1 40, 2.07)
~ -- - so, 2.011 26.01, 2.23 I 1---..... _... ________....... 60, 1.86:
2.0......... _ A-7 40, 1.97 I... t::..-----70, 1.79:
1.8 : 50, 1.93:............. : 80, 1.73:............ ---------
160, 1.831............. ~- : 90, 1.62 ~
1.6....
B ----------......... : 70, 1.65: 1100, 1.56 I 1.4 7
REFERENCE:
T.S. 3.7.8 and 3.2.21 I 80, 1.57 I ---------1100, 1.421 I 90, 1.52 I
1.2 10 20 30 40 50 60 70 80 90 100 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 Rev. 21 PL-NF-23-002 Rev. 1 Page 24 of 72
SUSQUEHANNA UNIT 2 TRM / 3.2-25
... SSES U. CYCLE 22
- 2.6
(/) LEGEND C 2.5
(/)
0 CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM C INSERTION TIME m 2.4
- c
)> - -. CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME z 2.3 z
)>
I I C
z 2.2 ---130.0, 2.16: SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES
-I N 2.1 ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2
- !: -~ I I E 2.0 ' USED IN DETERMINING MFLCPR
- i 140.0, 1.941 I C)
- i 1.9 C l! "
Cl)
-I C.
- o 0 1.8
- ;o s;: a:: ~
(.,.) (.) 1.7
- a.. N N :a!! I.....
N 1 40.1, 1.501
- 0) 1.6 A B 1.5
1.4 - I 108.0, 1.37 I
1.3 7
REFERENCE:
T.S. 3.2.2 and TRM 3.3.71
1.2 30 40 50 60 70 80 90 100 110
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
- SSES UNIT 2 CYCLE 22 * *
(J) 4.0 C I I I I -
(J) 0 C 3.8 LEGEND -
m
- r: -
)> 3.6 CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME -
z z -
)> CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME C 3.4 - CURVE A: -
z - 26, 2.61 CURVE C: CORE POWER :s; 26% AND CORE FLOW :s; 50 MLBM/HR -
-I 23, 2.84 ALL SCRAM INSERTION TIMES -
N 3.2 -
- I
- ! 3.0 - I I CURVE B:
E - -26, 2.61.
- J 23, 2.84 '- A SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE
- 0) 2.8 - \\. PER SR 3.7.6.1 AND 3.7.6.2 -
s:::
- ... 2.6 CURVEC
- -C ' a-* I I -
-I a., -.... 26, 2.59
- a Q. - 23, 2.84 126~01, 2.41 Jl USED IN DETERMINING MFLCPR s
- 0 0:: 2.4 r
-w (.) CL - -............... I N :ii I........... -.., : 40, 2.07 I N 2.2......_ 150, 2.071 A
-.J _
I 26.01, 2.23 I ~ ----------.--.............. _ 160, 1.s6:
2.0............._ -......... _
--........... -...... _______ 70, 1.79 1.8 :4o, 1.90 B 150, 1.89 I ---............ ~---.... I 75, 1.76 I
1.6 :so,1.11: 75,1.611 70, 1.65:
1.4 H
REFERENCE:
T.S. 3.2.2 and TRM 3.3.7:
1.2 10 20 30 40 50 60 70 80 Core Power(% RATED) ""O ""O
!l) r;-
MCPR OPERATING LIMIT VERSUS CORE POWER ~ z ONE TSV OR TCV CLOSED N '71 TWO LOOP OPERATION (BOC TO EOC) O> ;a N 0 (D Cf ATRIUMTM..10 AND ATRIUM'11 FUEL -<O
-.J. 0 FIGURE 5.2-10 N....>.N Rev.21 PL-NF-23-002 Rev. 1 Page 27 of 72 Table 5.3-1
Average Scram Time Fraction Table For Use With Scram Time Dependent MCPR Operating Limits
Control Rod Average Scram Time to Position (seconds)
Position 45 0.470 0.520 39 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 References
Technical Specification 3.2.3, 3.3.4.1, 3.7.6, and 3.7.8
Technical Requirements Manual 3.3.7
6.2 Description
The maximum LHGR for ATRIUM'-10 and ATRIUM' 11 fuel shall not exceed the LHGR 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: Flow-Dependent LHGR Limit Multiplier for ATRIUM'-10 and ATRIUM' 11 Fuel
Figure 6.2-3: Power-Dependent LHGR Limit Multiplier for ATRIUM'-10 and ATRIUM' 11 Fuel
b) Main Turbine Bypass Inoperable
Figure 6.2-4: Flow-Dependent LHGR Limit Multiplier for ATRIUM'-10 and ATRIUM' 11 Fuel
Figure 6.2-5: Power-Dependent LHGR Limit Multiplier for ATRIUM'-10 and ATRIUM' 11 Fuel
Figure 6.2-6: Flow-Dependent LHGR Limit Multiplier for ATRIUM'-10 and ATRIUM' 11 Fuel
Figure 6.2-7: 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 Rev. 21 PL-NF-23-002 Rev. 1 Page 29 of 72
Figure 6.2-9: 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.
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LINEAR HEAT GENERATION RATE LIMIT VERSUS PELLET EXPOSURE ATRIUM' 11 FUEL FIGURE 6.2-1B Rev. 21 PL-NF-23-002 Rev. 1 Page 32 of 72
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I l I I I I I 1 I I I I I l l 1 I l I I I I 1 I I I I I I I I I J I I I I I I I I I I I 0.80 -------i--------~-------+-------t--------r-------1 I I I I I I I J I I I I I I ------t-------+-------i--------r-------+-------+--------r-------i--------t-------
I I I ! I l l I 1 I I I t I I 1, u I 1 1 1 1 1 r, 1 1 1 1
~--------i-------l I I I I I I I I i I I J I I !J 50.0, 0.72,--------~ -------1/4-------+-------~--------i-------+-------+-------1--------~--------i-------
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- I I I I I I I I I l I I J l w I I I I I I 1 I 1 I I I I I I N I 0.60 -------1--------r--I J I I I I I I I I I ~ ---r-------1--------,-------1--------r-------r-------1--------r-------r-----1 RE FE RE Ne E = r.s. 3.2.3 f
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I I I I I I I I I I I I I I I I I I I I I I I I I I I t I I I I I I 1 I I
- ------~--------~-------I I I I I 1 t I I I I I I I I...... ~------~------~-r-------~--------~-------~-------,---*----~--ww*--~--------T------* 1*---*---~--------~-------
I I I I I 1 l I I I J I I I I I I I I J J I I f I I I I I I I I I I I 1 I I I I I I I I I I I I I I l 1 I l I I I I I I 0.30 30.0 40.0 50.0 60.0 70.0 80.0 90.0 100.0 110.0 Total Core Flow (MLB/HR) '"C '"C ca Ill r; FLOW DEPENDENT LHGR LIMIT MULTIPLIER (J) z MAIN TURBINE BYPASS/ EOC-RPT / BACKUP PRESSURE REGULATOR OPERABLE w T' w ::0 N ATRIUM'-10 AND ATRIUM' 11 FUEL 0 (I) Cf FIGURE 6.2-2 <O
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POWER DEPENDENT LHGR LIMIT MULTIPLIER MAIN TURBINE BYPASS / EOC-RPT / BACKUP PRESSURE REGULATOR OPERABLE ATRIUM'-10 AND ATRIUM'11 FUEL FIGURE 6.2-3 Rev. 21 PL-NF-23-002 Rev.1 Page 35 of 72
Main Turbine Bypass Inoperable
SUSQUEHANNA UNIT 2 TRM / 3.2-36 SSES UNIT 2 CYCLE 22
(/) 1.10 I I C
(/) I I I I D ------- --------+--------~-----------~--------~-------~ -------J--------~--------:--------i--------~-------+-------4--------~-------I 1 I I l I I l I I I l I I C I I I I I I I I I I 1 I J 1 rn I I I I I I I I l I I 1 J J J
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REFERENCE:
T.S. 3.2.3 and 3.7.6 I I I I I I I I I I l..
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-30 40 50 60 70 80, 90 100 110 Total Core Flow (MLB/HR) "'O "'O ll) r I (0 z FLOW DEPENDENT LHGR LIMIT MULTIPLIER (I) 71 MAIN TURBINE BYPASS INOPERABLE w I CJ) :::0 I\\.)
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(J) 1.10 C
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0.30 20 30 40 50 60 70 80 90 100 Core Power{% RATED) 'lJ 'lJ (Cl I Ill r POWER DEPENDENT LHGR LIMIT MULTIPLIER CD z,,
MAIN TURBINE BYPASS INOPERABLE (J.) ~
ATRIUM'-10 AND ATRIUM'11 FUEL ~ :::0 <.v
- ~ 6 FIGURE 6.2-5 --....i* 0 N -" N Rev.21 PL-NF-23-002 Rev. 1 Page 38 of 72
SUSQUEHANNA UNIT 2 TRM / 3.2-39
- SSES UNIT 2 CYCLE 22
(/) 1.10
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(/) I I I I I I I I I I I I I 0 -------~--------r--------,--------T--------r-------~--------r--------r-------,--------r-------~--------T--------r*------,--------r-------I I I I I I I I I I I I I I I C 1 I I I I I I I I II I I I m l l l l l l l l l l j 87.0, 1.00 ll l l l
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REFERENCE:
T.S. 3.2.3 and 3.3.4.1......
I I I I I I I I I
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CJ) 1.10 C I CJ) I I
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REFERENCE:
T.S. 3.2.3 and 3.3.4.1 I I I I I I I I I 7 I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I 0.50 -------~- ------t--------~--------i--------t--------~--------l 1 I I I I I I I I I.-------t--------~-------+-----
I I I I I I I I I I I I I I I I I I I I USED IN DETERMINING FDLRX I I I I I I I I I I
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0.40 -------~- _j 26,0, 4 0 '--~-------J-------t--------~------SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES I : I I I I 23, 0.35, I 26,0.39 I ! ! ! ! ARE OPERABLE PER SR 3. 7.6.1 AND 3. 7.6.2 I *
- I I I I
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Backup Pressure Regulator Inoperable
SUSQUEHANNA UNIT 2 TRM / 3.2-42 en SSES UNIT 2 CYCLE 22 C 1.10
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en I I I I I I 0 -------,--------r-------"'T"'-------T--------r-------~--------r--------r-------,--------r-------~--------T--------r-------,--------~-------I I I I I I I I I I I I I I I C 1 I I I I I I I I I ! I I I I m I I I I I I I I I I I 87 0 1 00 I' I I I I
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I I I I I I I I I I I I I z I I I I I I I I I I I I I z I I I I I I I I I I I I I I I I I I I I I I I I I I I I
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C. I I I I I I I I I I I I I I I Cl) N C 0.60 -------l-------i-- ---+-------~--------~-------~--------t-------+-------~-j
REFERENCE:
T.S. 3.2.3 and 3. 7.8....,.
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, ; 1 1 I I SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 0.41D -j. ', I ; ; 1 1 '--,,------,-----,----....,...----,-----,,------,-----,----....,...-----' 30.0 0.42 ~-~-------+-------~--------l--------~------
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FLOW DEPENDENT LHGR LIMIT MULTIPLIER co CD z BACKUP PRESSURE REGULATOR INOPERABLE.i:,. I N ::0 N ATRIUM'-10 AND ATRIUM' 11 FUEL 0 <O CD Cf FIGURE 6.2-8 --.._]. 0 N....>.N
- SSES UNIT 2 CYCLE 22
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)> CURVE B: CORE POWER s; 26% AND CORE FLOW s; 50 MLBM/HR -----4--------~--------1-----I I I 1 I I I I I I I I I I I I I I I I I I C I I I I I I I I I I I I I I z o.9o -------1--------r--------:-------1--------t--------;-------1-------~--------:-------7------I I I I I I I
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'C I I I I I I I I I I I I I I C I I I I I I I I I I I I I I Q) I I I I I I I I I I I I I I I :::0 C. I I I I I I I I I I I I I I I CD Q) -------~-- ---+--------~-------~--------+--------~-------~--------+--------~--------+--------+--------~--------+-------- --------~-------; I I ; ; ; ; ; ; ; ( : ; ; ;
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REFERENCE:
T.S. 3.2.3 and 3. 7.8 I I I I I I I I I I I I I I I I I I I I I I I I I I I I 0.50 -------i- ------t--------~-------1--------t--------~-------1--------t--------~-------+-----I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I USED IN DETERMINING FDLRX
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o.4o --~---~- --126, o.4o L~-------~--------i--------~------ SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES 23, 0,35 1 I --~--------*--------~-------1--------T--------~------,__ I._ __.,. 26,: 0.39 I ___ __,_ I I I I i i i i _________________________________..J~ ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2
123, 0.351 i i i i I I I I I 0.30 20 30 40 50 60 70 80 90 100
Core Power(% RATED) "U "U
!l) r I co z POWER DEPENDENT LHGR LIMIT MULTIPLIER CD "'Tl BACKUP PRESSURE REGULATOR INOPERABLE ~ I w :::0 N ATRIUM'-10AND ATRIUM'11 FUEL 0 CD 'f FIGURE 6.2-9 ---..J :< 0 0 N --"N Rev.21 PL-NF-23-002 Rev. 1 Page 44 of 72
SUSQUEHANNA UNIT 2 TRM / 3.2-45
- SSES UNIT 2 CYCLE 22 *
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