HARD COPY DISTRIBUTION DOCUMENT TRANSMITTAL 2019-3·191

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02/28/2019

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·zkM2 - TECHNICAL REQUIREMENTS MANUAL UNIT 2

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'· I

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,., • .J ;: Man~al Name : TRM2

SSES MANUAL

h .-,I· ... , .' ·:;;;J Manual Title: TECHNICAL REQUIREMENTS MANUAL UNIT 2

Table Of Content~ Issue Date: 03/12/2019

Procedure Name Rev Issue Date

TEXT LOES 99 01/03/2019

Title: LIST OF EFFECTIVE SECTIONS

TEXT TOC 27 03/05/2019

Title: TABLE OF CONTENTS

TEXT 1.1 0 11/19/2002

Title: USE AND APPLICATION DEFINITIONS

TEXT 2.1 1 02/04/2005

Title: PLANT PROGRAMS AND SETPOINTS PLANT PROG

. TEXT 2,2 ' .

t ;.· li Title: PLANT PROGRAMS AND ·--=J

TEXT 3.0

11

7

Change ID Change Number

SETPOINT TABLE

Title: APPLICABILITY TECHNICAL REQUIREMENT FOR OPERATION (TRO) APPLICABILl:TY

TEXT 3.1.1 1 11/09/2007

Title: REACTIVITY CONTROL SYSTEMS ANTICIPATED TRANSIENT WITHOUT SCRA,M ALTERNATE ROD INJECTION (ATWS-ARI) INSTRUMENTATION

TEXT 3 .1.2 0 11/19/2002

Title: REACTIVITY CONTROL SYSTEMS CONTROL ROD DRIVE (CRD) HOUSING SUPPORT

TEXT 3 .1.3 5 12/18/2017

Title: REACTIVITY CONTROL SYSTEMS CONT~OL ROD BLOCK INSTRUMENTATION

TEXT 3 .1.4 0 11/19/2002

Title: REACTIVITY CO~TROL SYSTEMS CONTROL ROD SCRAM ~CCUMULA~ORS INSTRUMENTATION AND CHECK VALVE

TEXT 3.2.1 14 02/27/2019

Title: CORE OPERATING LIMITS ~EPORT (COLR)

Page .!. of 15 Report Date: 03/28/19

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.f ):

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. , Manual Name : TRM2

SSES MANUAL

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1 . · .~.} Manual 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

I TEXT 3.3.6 5 03/05/2019 i ..

Title: INSTRUMENTATION TRM ISOLATION ACTUATION INSTRUMENTATION

TEXT 3.3.7 2 11/10/2015

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 1 03/05/2015

Title: WATER MONITORING INSTRUMENTATION

Page£ of 15 Report Date: 03/28/19

SSES MANUAL

Manual Name: TRM2

\_~ Manual Title: TECHNICAL REQUIREMENTS MANUAL UNIT 2

TEXT 3.4.1 1 Ot/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

TEXT 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

Pagel of 15 Report Date: 03/28/19

SSES MANUAL

Manual Name: TRM~ , __ )

·· .::,···· Manual Title: TECHNICAL REQUIREMENTS MANUAL UNIT 2

TEXT 3.6.4 0 11/19/2002

Title: CONTAINMENT PRIMARY CONTAINMENT CLOSED SYSTEM BOUNDARIES

TEXT 3.7.1 0 11/19/2002

Title: PLANT SYSTEMS EMERGENCY SERVICE WATER SYSTEM (ESW) SHUTDOWN

TEXT3.7.2 0 11/19/2002

Title: PLANT SYSTEMS ULTIMATE HEAT SINK (UHS) AND-GROUND WATER LEVEL

TEXT 3.7.3.1 5 . 02/16/2017

Title: PLANT SYSTEMS FIRE SUPPRESSION WATER SUPP~Y SYSTEM

TEXT 3.7.3.2 3 04/16/2009

Title: PLANT SYSTEMS SPRAY AND SPRINKLER SYSTEMS

TEXT 3.7.3.3 4 05/16/2016

Title: PLANT SYSTEMS CO2 SYSTEMS

TEXT 3.7.3,4 2 04/16/2009

Title: PLANT SYSTEMS HALON SYSTEMS

TEXT 3.7.3.-5 2 04/16/2009

Title: PLANT SYSTEMS FIRE HOSE STATIONS

TEXT 3.7.3.6 2 04/16/2009

Title: PLANT SYSTEMS YARD FIRE HYDRANTS AND HYDRANT HOSE HOUSES

TEXT 3.7.3.7 1 04/26/2006

Title: PLANT SYSTEMS FIRE RATED ASSEMBLIES

TEXT 3.7.3.8 14 12/18/2017

Title: .PLANT SYSTEMS FIRE DETECTION INSTRUMENTATION

rEXT 3.7.4 1 04/26/2006

Title: PLANT SYSTEMS SOLID RADWASTE SYSTEM

Page_! of 15 Report Date: 03/28/19

$SES.MANUAL

Manual Name: TRM2 l

I j}

'·--:I Manual 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

'.DEXT 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

TEXT 3.7.8 9 03/05/2015

Title: PLANT SYSTEMS SNUBB~RS

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 3 06/20/2012

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 2 12/14/2004

Page 2.

Title: ELECTRICAL POWER MOTOR OPERATED VALVES (MOV) THERMAL OVERLOAD PROTECTION -AUTOMATIC

of 15 Report Date: 03/28/19

SSES MANUAL

Manual Name: TRM2 I i! ·~=3" Manual Title: TECHNICAL REQUIREMENTS MANUAL UNIT 2

TEXT 3.8.3 3 03/05/2019

Title: ELECTRICAL POWER DIESEL GENERATOR (DG) MAINTENANCE ACTIVITIES

TEXT 3.8.4 1 02/04/2005

Title: ELECTRICAL POWER 24 VDC ELECTRICAL SUBSYSTEM

TEXT 3.8.5 1 11/14/2013

Title: ELECTRICAL POWER DEGRADED VOLTAGE PROTECTION

TEXT 3.8.6 3 03/05/2019

Title: ELECTRICAL POWER EMERGENCY SWITCHGEAR ROOM COOLING

TEXT 3.8.7 2 10/22/2009

Title: BATTERY MAINTENANCE AND MONITORING PROGRAM

TEXT 3.9.1 0 11/19/2002

Title: REFUELING OPERATIONS DECAY TIME

TEXT 3.9.2 0 11/19/2002

Title: REFUELING OPERATIONS COMMUNICATIONS

TEXT 3.9.3 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 2 06/15/2010

Title: MISCELLANEOUS INDEPENDENT SPENT FUEL STORAGE INSTALLATION (ISFSI)

TEXT 3.10.4 2 04/17/2009

Title: MISCELLANEOUS LEADING EDGE FLOW METER (LEFM)

Page.§_ 1of 15 Report Date: 03/28/19

SSES MANUAL

Manual Name: TRM2 , _ _J ··.___: .. , Manual Title: TECHNICAL REQUIREMENTS MANUAL UNIT 2

:1 .,·i'

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'.l.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

TEXT 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 1 of 15 Report Date: 03/28/19

SSES MANUAL

; Manual Name: TRM2 t . 1 ~ Manual Title: TECHNICAL REQUIREMENTS MANUAL UNIT 2

TEXT 3.11.4.1 4 03/05/2015

Title: RADIOACTIVE EFFLUENTS MONITORING PROGRAM

TEXT 3.11.4.2 2 04/26/2006

Title: RADIOACTIVE EFFLUENTS LAND USE CENSUS

TEXT 3.11.4.3 1 04/26/2006

Title: RADIOACTIVE EFFLUENTS INTERLABORATORY COMPARISON PROGRAM

TEXT 3.12.1 0 11/19/2002

Title: LOADS CONTROL PROGRAM CRANE TRAVEL-SPENT FUEL STORAGE POOL

TEXT 3.12.2 4 04/17/2008

Title: LOADS CONTROL PROGRAM HEAVY LOADS ;R.EQUIREMENT.s

I, ... ) TEXT 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 0 09/27/2003

Title: ADMINISTRATIVE CONTROLS REPORTING REQUIREMENTS

TEXT 4.6 0 09/27/2003

Title: ADMINISTRATIVE CONTROLS RADIATION PROTECTION PROGRAM

,. ,;

~J· •

Page~ of 15 Report Date: 03/28/19

SSES MANUAL

Manual Name: TRM2

'· ...:.5/ Manual Title: TECHNICAL REQUIREMENTS MANUAL UNIT 2

TEXT 4.7 0 09/27/2003

Title: ADMINISTRATIVE CONTROLS TRAINING

TEXT B3.0 6 03/05/2015

Title: APPLICABILITY BASES TECHNICAL REQUIREMENT FOR OPERATION (TRO) APPLICABILITY

TEXT B3 .1.1 2 04/29/2014

Title: REACTIVITY CONTROL SYSTEM BASES ANTICIPATED TRANSIENT WITHOUT SCRAM ALTERNATE ROD INJECTION (ATWS-ARI) INSTRUMENTATION.

TEXT B3.l.2 0 11/19/2002

Title: REACTIVITY CONTROL SYSTEM BASES CONTROL ROD DRIVE (CRD) HOUSING SUPPORT

TEXT B3.1.3 4 12/18/2017

Title: REACTIVITY CONTROL SYSTEM BASES CONTROL ROD BLOCK INSTRUMENTATION

TEXT B3 .1.4 ··;/

0 11/19/2002

Title: REACTIVITY CONTROL SYSTEM BASES CONTROL ROD SCRAM ACCUMULATORS INSTRUMENTATION AND CHECK VALVE

TEXT B3.2.1 0 11/19/2002

Title: CORE OPERATING LIMITS BASES CORE OPERATING LIMITS REPORT (COLR)

TEXT B3.3.1 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~ of 15 Report Date: 03/28/19

SSES MANUAL

Manual ·Name: TRM2 jj

1 ··-· Manual Title: TECHNICAL REQUIREMENTS MANUAL UNIT 2

TEXT B3 . 3 . 6 \ 6 03/05/2019

Title: INSTRUMENTATION BASES TRM ISOLATION ACTUATION INSTRUMENTATION

TEXT B3.3.7 2 11/10/2015

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

j TEXT B3 . 3 . 11 ..,:/

1 10/22/2003

Title: INSTRUMENTATION BASES MVP ISOLATION INSTRUMENTATION

TEXT B3.3.12 0 04/16/2009

Title: WATER MONITORING INSTRUMENTATION

TEXT B3 .4 .. 1 0 11/19/2002

Title: REACTOR COOLANT SYSTEM BASES REACTOR COOLANT SYSTEM CHEMISTRY

TEXT B3.4.2 1 04/16/2009

Title: 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


SSES MANUAL

Manual Name: TRM2

1·· ca./\ Manual 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 1 03/05/2019

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.S.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

TEXT B3.6.2 0 11/19/2002

Title: CONTAINMENT BASES SUPPRESSION CHAMB~R-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 L~VEL

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


SSES MANUAL

Manual Name: TRM2

\._~,.,,,/ Manual 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 2 04/29/2014

Title: PLANT SYSTEMS BASES HALON SYSTEMS

TEXT B3.7 .. 3.5 1 04/26/2006

Title: PLANT SYSTEMS BASES FIRE HOSE STATIONS

TEXT B3.7.3.6 1 04/26/2006

Title: PLANT SYSTEMS BASES YARD FIRE HYDRANTS AND HYDRANT HOSE HOUSES

TEXT B3.7.3.7 0 11/19/2002

Title: PLANT SYSTEMS BASES FIRE RATED ASSEMBLIES

TEXT B3.7.3.8 3 09/27/2012

Title: PLANT SYSTEMS BASES FIRE DETECTION INSTRUMENTATION

TEXT B3.7.4 0 11/19/2002

Title: PLANT SYSTEMS BASES SOLID RADWASTE SYSTEM

TEXT B3.7.5.1 0 11/19/2002

Title:. PLANT SYSTEMS BASES MAIN CONDENSER OFFGAS HYDROGEN MONITOR

TEXT B3.7.5.2 0 11/19/2002

Title: PLANT SYSTEMS BASES MAIN CONDENSER OFFGAS EXPLOSIVE GAS MIXTURE

TEXT B3.7.5.3 0 11/19/2002

Title: PLANT 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


SSES MANUAL

Manual Name: TRM2 )

'._--:0 :=l Manual 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 B3.7.11 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

'TEXT B3.8.2.1 0 11/19/2002 •1•-w,..,,._~v"7

Title: ELECTRICAL POWER BASES MOTOR OPERATED VALVES (MOV) THERMAL OVERLOAD PROTECTION -CONTINUOUS

TEXT B3.8.2.2 1 09/17/2004

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 2 06/04/2013

Title: BATTERY MAINTENANCE AND MONITORING PROGRAM


SSES MANUAL

Manual Naine: TRM2

Manual 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

TEXT B3.10.3 0 11/19/2002

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 !33 . 11 . 1. 2 0 11/19/2002

Title: RADIOACTIVE EFFLUENTS BASES LIQUID EFFLUENTS DOSE

TEXT B3 .11.1. 3 0 11/19/2002

Title: RADIOACTIVE EFFLUENTS BASES LIQUID WASTE TREATMENT SYSTEM

TEXT B3 . 11 . 1. 4 0 11/19/2002

Title: RADIOACTIVE EFFLUENTS BASES LIQUID RADWASTE EFFLUENT MONITORING INSTRUMENTATION

TEXT B3 . 11. 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


SSES MANUAL

Manual Name: TRM2 il

\.--,,/ Manual Title: TECHNICAL REQUIREMENTS MANUAL UNIT 2

TEXT B3 .11. 2. 2 0 11/19/2002 .

Title: RADIOACTIVE EFFLUENTS BASES DOSE - NOBLE GASES

TEXT B3.11.2.3 0 11/19/2002

Title: RADIOACTIVE EFFLUENTS BASES DOSE - IODINE, TRITIUM, AND RADIONUCLIDES PARTICULATES FORM

TEXT B3.11.2.4 0 11/19/2002

Title: RADIOACTIVE EFFLUENTS BASES GASEOUS RADWASTE TREATMENT SYSTEM

TEXT B3.ll.2.5 5 07/03/2013.

Title: RADIOACTIVE EFFLUENTS BASES VENTILATION EXHAUST TREATMENT SYSTEM

TEXT B3.ll.2.6 2 09/08/2016

Title: RADIOACTIVE EFFLUENTS BASES RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION

TEXT B3 . 11. 3 0 11/19)2002

Title: RADIOACTIVE EFFLUENTS BASES TOTAL DOSE

TEXT B3.ll.4.1 5 03/05/2015

Title: RADIOACTIVE EFFLUENTS BASES MONITORING PROGRAM

TEXT B3.ll.4.2 0 11/19/2002

Title: RADIOAC'.I'IVE EFFLUENTS BASES LAND USE CENSUS

TEXT B3.ll.4.3 0 11/19/2002

Title: RADIOACTIVE EFFLUENTS BASES INTERLABORATORY COMPARISON PROGRAM

TEXT B3.12.l 1 10/04/2007

Title: .LOADS CONTROL PROGRAM BASES CRANE TRAVEL-SPENT FUEL STORAGE POOL

TEXT B3.12.2 1 12/03/2010

Title: LOADS CONTROL PROGRAM BASES HEAVY LOADS REQUIREMENTS

TEXT B3.12.3 0 11/19/2002

Title: LOADS CONTROL PROGRAM BASES LIGHT LOADS REQUIREMENTS

IN


Rev. 14 Core Operating Limits Report (COLR)

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

A. Core Operating Limits not A.1 Perform action(s) met. described in referenced

Technical Specification.

TECHNICAL REQUIREMENT SURVEILLANCE

SURVEILLANGE

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

SUSQUEHANNA - UNIT 2 3.2-1

COMPLETION TIME

Specified in referenced · Technical Specifications.

FREQUENCY

N/A

Rev. 14

Susquehanna SES Unit 2 Cycle 19

PL-NF-17~001 Rev. 1 Page 1 of 62

CORE OPERA TING LIMITS - -REPORT -

SUSQUEHANNA UNIT 2 3.2-2

-

Nuclear Fuels Engineering

February 2019

Rev. Affected No. Sections

0 ALL

1 6.0

ALL

Rev. 14 PL-NF-17-001 Rev. 1 Page 2 of 62

CORE OPERATING LIMITS REPORT REVISION DESCRIPTION INDEX

Description/Purpose of Revision

Issuance of this COLR is in support of Unit 2 Cycle 19 operation.

Figures 6.2-2 through 6.2-4 (editorial) and 6.2-5 (technical) are revised to account for the cycle achieving a greater core average exposure than what was assumed to initially analyze Unit 2 Cycle 19 (U2C19). Updated U2C19 licensing analysis results (Framatome, formerly AREVA, report ANP-3536, Rev. 3) at a bounding core average exposure only affect the power-dependent, eq~ipment out-of-service Linear Heat Generation Rate (LHGR) multipliers.

On pages 27, 29, and 32, text supporting these Figures is also updated.

Removed page count prefix TRM/ and Effective Date from footer to align formatting with the new process.

FORM NFP-QA-008-2, Rev. 1 SUSQUEHANNA UNIT 2 3.2-3

"

Rev. 14

SUSQUEHANNA STEAM ELECTRIC STATION Unit 2 Cycle 19

CORE OPERATING LIMITS REPORT

Table of Contents

PL-NF-17-001 Rev. 1 Page 3 of 62

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) ........................................................... 9

6.0 LINEAR HEAT GENERATION RATE (LHGR).. ........................................................... 27

7.0 ROD BLOCK MONITOR (RBM) SETPOINTS AND OPERABILITY REQUIREMENTS ........................................................................................................ 38

8.0 RECIRCULATION LOOPS - SINGLE LOOP OPERATION ........................................ .40

9.0 POWER/ FLOW MAP ................................................................................................ 58

10.0 OPRM SETPOINTS .................................................................................................... 60

11.0 REFERENCES ............................................................................................................ 61


Rev. 14

1.0 INTRODUCTION


This CORE OPERATING LIMITS REPORT for Susquehanna Unit.2 Cycle 19 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.


Rev. 14

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 LHGRFACr is a multiplier applied to the LHGR limit when operating at less than 108 Mlbm/hr core flow. The LHGRFACt multiplier protects against both fuel centerline melting and cladding strain during anticipated system transients initiated from core flows less than 108 Mlbm/hr.

2.5 LHGRFACp is a multiplier applied to the LHGR limit when operating at less than RA TED THERMAL POWER. The LHGRFACp multiplier protects against both fuel centerline melting and cladding strain during anticipated system transients initiated from partial power conditions.

2.6 MFLCPR is the ratio of the applicable MCPR operating limit for the applicable fuel bundle type divided by the MCPR calculated by the core monitoring system for each fuel bundle.

2. 7 MAPRA T is the ratio of the maximum APLHGR calculated by the core monitoring system for each fuel bundle 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 MCPR 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 Fp is the core flow, in Mlbm / hr, below which the OPRM RPS trip is activated.



3.0 SHUTDOWN MARGIN

3.1 Technical Specification Reference

Technical Specification 3.1 .. 1

3.2 Description

The SHUTDOWN MARGIN shall be equal to or greater than:

a) 0.38% Lik/k with the. highest worth rod analytically determined

OR

b) 0.28% Lik/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 (SDM) tests must also account for changes in core reactivity during the cycle. Therefore, the SDM measured at BOC must be equal to or greater than the applicable requirement from either 3.2.a or 3.2.b plus an adder, "R". The adder, "R", is the difference between the calculated value of maximum core reactivity (that is, minimum SDM) during the operating cycle and the calculated BOC core reactivity. If the value of "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.



4.0 AVERAGE PLANAR LINEAR HEAT GENERATION RA TE (APLHGR)


Technical Specification 3.2.1

4.2 Description

The APLHGRs for ATRIUM™-10 fuel shall not exceed the limit shown in Figure 4.2-1.

The APLHGR limits in Figure 4.2-1 are valid for Main Turbine Bypass Operable and Inoperable, EOC-RPT Operable and Inoperable, and Backup Pressure Regulator Operable a·nd Inoperable in Two Loop operation. The APLHGR limits for Single Loop operation are provided in Section 8.0.


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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™-10 FUEL FIGURE 4.2-1

60000 70000


5.0 MINIMUM CRITICAL POWER RATIO (MCPR)


Technical Specification 3.2.2, 3.3.4.1, 3.7.6, and 3.7.8

5.2 Technical Requirements Manual Reference

Technical Requirements Manual 3.3.7

5.3 Description

The MCPR limit is specified as a function of core power, core flow, average scram insertion time per Section 5.3 and plant equipment operability status. The MCPR limits for all fuel types (ATRI UM™-10) shall be the greater of the FlowDependent or the Power-Dependent MCPR, depending on the applicable equipment operability status.

a) Main Turbine Bypass / EOC-RPT / Backup Pressure Regulator Operable

Figure 5.2-1: Flow-Dependent MCPR value determined from BOC to EOC

Figure 5.2-2: Power-Dependent MCPR value determined from BOC to EOC

b) Main Turbine Bypass Inoperable



c) EOC-RPT Inoperable



d) Backup Pressure Regulator Inoperable


Figure 5.2-8: Power Dependent MCPR value determined from BOC to EOC

e) One Turbine Stop Valve (TSV) or Turbine Control Valve (TCV) Closed


Figure 5.2-10:Power-Dependent MCPR value determined from BOC to EOC



The MCPR limits in Figures 5.2-1 through 5.2-10 are valid for Two Loop operation.

The MCPR limits for Single Loop operation are provided in Section 8.0.

5.4 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.



Main Turbine Bypass/ EOC-RPT / Backup Pressure Regulator

Operable


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1.4

1.3

1.2

SSES UNIT 2 CYCLE 19

LEGEND

CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME

CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME

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

I I

USED IN DETERMINING MFLCPR I

n 30, 1.54 I

r----__

-------- A

-------------B

I REFERENCE: T.S. 3.2.2 ----........ ~

30 40

~ --------------

I 108, 1.21 I

--------50 60 70 80 90 100 110 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) FIGURE 5.2-1

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SSES UNIT 2 CYCLE 19 36 I I I I

3.4 LEGEND

CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME 3.2 ---123, 3.0911--+---------1

t----.-----+-------t----iCURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME 3.0 ~'\L..: 12:.:.6!.,:, 2:.:.:.9::5:...rl------r----i I 23, 3.041\. CURVE C: CORE POWER :s:: 26% AND CORE FLOW :s:: 50 MLBM/HR

' 126, 2.841 2.8

,-

------

~ 2.6 _ C _1-------l1-------+-----1SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE _ c PER SR 3.7.6.1 AND 3.7.6.2

:;::::; -~ Cll 2.4 Q. 0

w 0::: ~. '-----~-------.----~-----,------.----~ 1------11----+----------lUSED IN DETERMINING MFLCPR

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2.0 I 26.01, 1.99 I

1.8 ......... .... ....

.........._ ........ 140, 1.70 126.01, 1.891 ............... -................ A

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B -----1.4 H REFERENCE: T.S. 3.2.2 I I 80, 1.41 L

1.2

I

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20 30 40 ~ 60 ro 80 90 Core Power(% RATED)

MCPR OPERA TING LIMIT VERSUS CORE POWER MAIN TURBINE BYPASS / EOC-RPT / BACKUP PRESSURE REGULATOR OPERABLE


100

Rev. 14

Main Turbine Bypass Inoperable


PL-NF-17-001 Rev. 1 Page 14 of 62

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1.4

1.3

1.2


LEGEND

CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME -CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME

SAFETY ANALYSES ASSUME THAT TWO OR MORE BYPASS VALVES ARE INOPERABLE PER SR 3.7.6.1 OR 3.7.6.2

I USED IN DETERMINING MFLCPR

130, 1.741

~ ~~

~ A

~ B

~

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.,

I REFERENCE: T.S. 3.7.6 and 3.2.2 I

30 40 50

•

60 70 80 90 Total Core Flow (MLB/HR)

MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW MAIN TURBINE BYPASS INOPERABLE


-

1108, 1.36 I

100 110

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23, 3.431 -3.4 \. LEGEND -\ -\ CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM 3.2 INSERTION TIME .....

123, 3.041 I 26, 3.15 I CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME

..... \. 3.0

c\ .....

CURVE C: CORE POWER~ 26% AND CORE FLOW~ 50 MLBM/HR -2.8

' I 26, 2.841 .....

2.6 -SAFETY ANALYSES ASSUME THAT TWO OR MORE BYPASS VALVES ARE INOPERABLE PER SR 3.7.6.1 OR 3.7.6.2 -

2.4

2.2 USED IN DETERMINING MFLCPR i 126.01, 2.03 I

2.0 .... .......... .......

"'-1.8 40, 1.741 ~ A

B I 80, 1.54 I 1100, 1.54 I 1.6

-JREFERENCE: T.S. 3.7.6 and 3.2.21 1.4

1.2 20 30 40 50 60 70 80

Core Power(% RATED)

MCPR OPERATING LIMIT VERSUS CORE POWER MAIN TURBINE BYPASS INOPERABLE TWO LOOP OPERATION (BOC to EOC)

FIGURE 5.2-4

90 100

SUSQUEHANNA UNIT 2

Rev. 14

EOC-RPT Inoperable

3.2-18

PL-NF-17-001 Rev. 1 Page 17 of 62

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1.5

1.4

1.3

1.2


LEGEND

CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM -INSERTION TIME

CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME -SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES -

ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2

I USED IN DETERMINING MFLCPR i

130, 1.541 --..._______

-----------A

~ B

--I REFERENCE: T.S. 3.3.4.1 and 3.2.2 I

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

30 40 50

----- ---~ I 108, 1.21 I ~

60 70 80 90 100 110 Total Core Flow (MLB/HR)

MCPR OPERA TING LIMIT VERSUS TOTAL CORE FLOW EOC-RPT INOPERABLE


l/'l C l/'l 0 C m :c )> z z )>

C z =i N

SSES UNIT 2 CYCLE 19 36

3.4 LEGEND

1-----+------+---CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM ... 3.2 --J 23, 3.0911-------- INSERTION TIME ...

-

CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME 30 ~

L..:j 2:::.3~, 3:..::.0::4:.rl'\....Ji~t'f...l.12_6_, T2._9_5.__ l __ +_--,CURVE C: CORE POWER~ 26% AND CORE FLOW~ 50 MLBM/HR

' I 2.8 - - ~ 26, 2.8411-------l ,..

C '-----..-------.------~---~----~----' ·e -:J 2.6 C,

1----t---+------+----l SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE ,.. PER SR 3.7.6.1 AND 3.7.6.2 C

~ I I I I I

O

(l)c. 2.4 1------1--+------+----r--~---~-----'-----....__--------'----1-1[

2.0

1.8

1.6

1.4

1.2

USED IN DETERMINING MFLCPR

126.01, 1.991

............... 140, 1.701

A Bi-----+----------------1

~REFERENCE: T.S. 3.3.4.1 and 3.2.2! 180, 1.441

20 30 ~ ~ M ro ~ Core Power(% RATED)

MCPR OPERATING LIMIT VERSUS CORE POWER EOC-RPT INOPERABLE

TWO LOOP OPERATION (BOC to EOC) FIGURE 5.2-6

194.46, 1.43 L 1100

, 1

_43

!

90 100


Backup Pressure Regulator Inoperable


l/l C 2.2 l/l 0 C m I :t> 2.1 z z :t> C z 2.0 =i N

1.9

:!:: E

1.8 :J C) C ; ns ...

1.7 Cl) C. 0

OJ ~ N D.

I (.) 1.6 N N :al:

1.5

1.4

1.3

1.2


LEGEND



I I I


I I I I

USED IN DETERMINING MFLCPR r

130, 1.54 I r-----.__

-..........____

-----------A B

-- --............. I REFERENCE: T.S. 3.7.8 and 3.2.21 r--------- ....____

30 40 50

-------------- 1108, 1.211

~ 60 70 80 90

Total Core Flow (MLB/HR)

MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW BACKUP PRESSURE REGULATOR INOPERABLE


100 110

"'O "'O D> r (0 I

CD z N 7' ...... ;a ...... 0 CD -;J .... < 0 0). 0 'I\.)....>.....>.

(./l

C (./l

0 C m I )> z z )>

C z =i

36

3 .4

3 .2 -123, 3.091

N 3 ~ .0 \" 1 26, 2.95 1 123, 3.041 I

' .8 I 26, 2.841 2

-c .6

.4 : 26.01, 2.30 :

.............. ~

140, 2.08 I .2 --........__

2 .0 ~

1 .8

1 .6


... LEGEND ... CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM

INSERTION TIME


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


I I

USED IN DETERMINING MFLCPR [

A

.................. B

--........__ -..... r--,.....__

-.............. I 80, 1.461

~REFERENCE: T.S. 3.7.8 and 3.2.2! --........__

I 94.46, 1.37 L 1 .4

1 .2 20 30

--... -

40 50 60 70 80 Core Power(% RATED)

MCPR OPERA TING LIMIT VERSUS CORE POWER BACKUP PRESSURE REGULATOR INOPERABLE

TWO LOOP OPERATION (BOC to EOC) FIGURE 5.2-8

I 100, 1.351 -

90 100

Rev. 14

One TSV or TCV Closed


PL-NF-17-001 Rev. 1 Page 23 of 62

l/l C l/l 0 C m I )> z z )>

C z =i N

:!:! E :J C) C :;:: n:I .. Cl) Q. 0

(;J a:: N C.

I t.) N 1.11 :E

SSES UNIT 2 CYCLE 19 2.2

LEGEND

2.1 CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM · INSERTION TIME

2.0 CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME

I I I I

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

1.8 . I I I I

130, 1.74 I USED IN DETERMINING MFLCPR r 1.7

1.6

~ -~ ~ A

.............. 8

1.5

1.4

.... ~ ~ ~ I 108, 1.371 ·

1.3 I REFERENCE: T.S. 3.2.2 and TRM 3.3.7 I

1.2 30 40 50 60 70 80 90


MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW ONE TSV OR TCV CLOSED*


100

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

110

(/l

C (/l

0 C m I )> z z )>

C z

3.6

3. 4

3. 2 H23,3.o91

=i N 3. o ~ 126, 2.951

I 23, 3.041 "\.'

:!: E ::::i Cl C: :;:; n:s

2. 8

2. 6

; 2 .4 C. 0

w 0::: N C.. 2

I (.)

~ :l!: .2

'\ ,__ C I 26, 2.841

.2 .o I 26.01, 1.99 I

"' ... ......... ~

...... .........

SSES UNIT 2 CYCLE 19 I I I I

LEGEND



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



1 .8 140, 1.10 I I 26.01, 1.89 I --............. ...... .........

---- A ............... ------

-----..... -.....

--

~

------.6 175, 1.471 I 40, 1.62 I ---------------1

1 .4

1.2 20

B

I REFERENCE: T.S. 3.2.2 and TRM 3.3.7 I

30 40 50 60 Core Power (% RA TED)

MCPR OPERA TING LIMIT VERSUS CORE POWER ONE TSV OR TCV CLOSED*


-----I 75, 1.43 I

70

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

80

Rev. 14

Table 5.3-1

PL-NF-17-001 Rev. 1 Page 26 of 62

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



6.0 LINEAR HEAT GENERATION RATE (LHGR)


Technical Specification 3.2.3, 3.3.4.1, 3.7.6, and 3.7.8



6.3 Descriptio·n

The maximum LHGR for ATRIUM™-10 fuel shall not exceed the LHGR limit determined from Figure 6.2-1. The LHGR limit in Figure 6.2-1 is 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:


Figure 6.2-2: Flow-Dependent LHGR Limit Multiplier

· Figure 6.2-3: Power-Dependent LHGR Limit Multiplier

b) Main Turbine Bypass or EOC-RPT or Backup Pressure Regulator Inoperable

Figure 6.2-4: Flow-Dependent LHGR Limit -Multiplier

Figure 6.2-5: Power-Dependent LHGR Limit Multiplier

c) One Turbine Stop Valve (TSV) or Turbine Control Valve (TCV) Closed

Figure 6.2-6: Flow-Dependent LHGR Limit Multiplier

Figure 6.2-7: Power-Dependent LHGR Limit Multiplier

The LHGR limits and LHGR limit multipliers in Figures 6.2-1 through 6.2-7 are valid for both Two Loop and Single Loop operation.


en C en 0 C m :c )> z 2 )>

C 2 =i N

lJJ N

I N lC

16.0

14.0

I ~ 12.0 :J m -I}_ C 0 ~ 10.0 m C m

(!) -ns m

:::c ~ 8.0 m C :J

6.0

4.0 0

I I I I I


I I I I I I I I I I I I I I I I I I I I I I I' I 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---,---r--,---r--T---,---r--,---r--T--"'T'"--r--,---r--T--.,..--r--,---r--T---,---r--,---r--,---r--r--,---r--,--..,..--r--,---r--,--..,..--T--,---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 I I I I I I I I I I I I I I I I I . I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I

I o~o, :13.:4 H--+--f--+--t--il 1~90:0, ~3.~ H--+--f--+--t--i--+--f--i REFERENCE: T.s. 3.2.3 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

--l---f---~--~---l.--l--...:..--~--~---:..-- -.:..--i--~---l.--J--..:..--~--~---l.--~--..:...--i--~---l.--J-- USED IN DET·ERMINING FDLRX I I I I I I I I I I 1 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 ·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 I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I' I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I --~---'---L--J---~--~---'---L--J---~--~---'---L--J---~--~---'---L--J-- --~---'---~--J---~--~--..L.--~--J---~--J--..L.--~--J---~--J--..&..--~--J---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 I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I 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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--t--~---t--t---r--+---1---t--t---r--t---1---t--t---r--t---1---t--t---r--+---1---t--t---r--+---1---t- ---r--t---1---t--t---r--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 I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I 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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I I I I I I I I I I ; I I I I 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 74400 7 1

--~---:---~--~---~--~---:---~--~---~--~--4---~--~---~--~---1----~--~---~--~--4---~--~---~--~---l----~--~---~--~--4---~--~---~--~--..,. ' . I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I 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---,---~--,---r--T--..,..--r--~---r--T--..,..--r--~---r--T--..,..--r--~---r--T--..,..--r--~---r--T--..,..--r--~---r--T--..,..--r--~---r--,--..,..--T--~---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 I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I 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 I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I 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 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

10000 20000 30000 40000 50000 60000 Pellet Exposure (MWD/MTU)

LINEAR HEAT GENERATION RATE LIMIT VERSUS PELLET EXPOSURE ATRIUM™-10 FUEL

FIGURE 6.2-1

70000 80000


Main Turbine Bypass/ EOC-RPT / Backup Pressure Regulator

Operable


(/) C (/)

0 C m I )> z z )>

C z -I N

w N I w .......

1.10

1.00

0.90

0.80

0.70

0.60

0.50

0.40

0.30

I I I


I I I I I I I I I I I I I I I I I I I I I I I I I I I -------r--------r-------r-------r-------r-------,--------,--------,--------,---180 1 00 1--1--------1--------1--------y-----. --y--------l l l l l l l l l J I • l l l l l I I I I I I I I I I I I I I I --------;---o----1---------t-------1--------1--------1--------1--------1--------1------~-:;a,11--------'l--------+--------l'------~.1--------'I---~' I I I I I I I I I I I 1 I I I I I I I I I : l : : : l l l I l I l l l 108, 1.00

------- ~------- ~-------4--------4---------:--------~--------~------- -------~--------~--------~--------~--------~--------~--------y--------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 --------~--------~--------1---------+---------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--------~--------1--------1--------1--------t--------t--------l I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I

------- ~------- -------:--------...;..--------:--------~--------~ -------~--------~--------~--------~--------~--------~--------+--------+--------• I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I 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--------~--------+--------+--------I I I I I I I I I I I I I I I I

30 0 75 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--------1--------1--------1--------t--------t--------l I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I --------r--------r--------r--------r--------,--------,--------.,--------,--------,--------,--------,--------,--------,--------T--------T--------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 lb I I I I I I 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--------~--------+--------•--------I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I

--------r--------~-------t--------t--------t--------;--------;--------i--------1--------1--------1--------1--------1--------t--------+--------: l l l l l l l l l l ·~ ·~ ·: ·~ --------!.--------~--------i---------i---------i--------~---------l--------~--------~--------~--------4--- REFERENCE: T.S. 3.2.3 -I I I I I I I 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

1

1-·-----':,__ ___ ..,, ___ __,,,__ ___ .... __ ....,~ --------r-------r-------r-------r-------r-------1--------1--------1--------1--------,-------- USED IN DETERMINING FDLRX -

I I 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---------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 --------,---------~--------r--------r--------r-------..------

SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE PER SR 3. 7.6.1 AND 3. 7.6.2

30

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 . l

40 50 60 70 80 90 100

Total Core Flow (MLB/hr)

FLOW DEPENDENT LHGR LIMIT MULTIPLIER MAIN TURBINE BYPASS/ EOC-RPT / BACKUP PRESSURE REGULATOR OPERABLE

A TRIUM™-1 O FUEL FIGURE 6.2-2

110

(/) C (/)

0 C m I >z z >c z -I N

(..v

N I

(..v N

1.10

1.00

0.90 I.,

.!=! :e-= :,

0.80 :li: c:: (!) :c ..J .... C

0.70 Q) "t, C Q) Q. Q)

C I., Q) 0.60 ~ 0 C.

0.50

OAO

0.30

SSES UNIT 2 CYCLE 19 I I I I

I I I I I I I I I P -----r-------r-------r-------n 94.46, 1.00 I I I I I . .

LEGEND

I I I I I I I I I I CURVE A: BASE CURVE -----1--------1--------1--------t-----~-~~.~~~-1 I I I I I ,---....... ---,

CURVE 8: CORE POWER:5:26% AND CORE FLOW:5:50 MLBM/HR I ! I l ! 100, 1.00 L---...... ---...... ---...... ---...... ---...... ---...... ---...... ---...... ---...... ---...... --'-----+--------+------ -------+--------+--------• I I I I

I I : : I I I 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 I I I I I I I I I I I I I I I I I I I I I

; I : ; : : : : A : I I : : : I I I I I I I I I I I I I I I --------~--------~-------;---------:--------;--------;--------;--------i------- ------i--------i--------i--------1--------+--------t--------l I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I 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--------4--------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 I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I --------~--------~-------~-------~------- -----~--------~--------~--------~--------~--------~--------~--------~--------+--------+--------• I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I --------r--------~------- ------:---------:--------;--------;--------i--------i--------i--------t--------t--------t--------+--------+--------, 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 I I I I I I I I I I I I I I : I I I I I I I" I I I I I I I --------r 126.-01, o.651------t-------t-------1--------1-------t-------,--------,--------1--------1--------1--------t--------t--------• . ~ ; . I I I I I I I I I I I I

--------~ ------r--------!--------~-------~-------~--------~--------t--------t--------t--------t----1 ~E:FE:~E:I\IC:E:: 1".~. 3.2.3 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

~-----=-=-----~~ ~ t t t 1 126, ~.50 1 _1 _______ 1 _______ 1 _______ j___

-----~--------;--------;--------i--- USED IN DETERMINING FDLRX I I I I I I I I I I I I I I I I

I I I I I I I I I I I I I I I I I I I I SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES I I I I I

s1 :- r r r 1 ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2

: I 26, 0.431 ! ! ! ! I I I I I I I I I ---- --~--------F-------;--------;--------;--------;--------;--------;--------;--------;--------t--------t--------t--------t--------t--------' 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 23, 0.40 l---~--------1---------i---------l--------~--------~--------~--------~--------~--------4--------4--------4--------!--------!--------I I I I I I I I I I I I I I

20

I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I

30 40 50 60 70 80 90

Core Power (% RA TED)

POWER DEPENDENT LHGR LIMIT MULTIPLIER MAIN TURBINE BYPASS/ EOC-RPT / BACKUP PRESSURE REGULATOR OPERABLE

A TRIUM™-10 FUEL FIGURE 6.2-3

100

:;a CD :<

"U :;a "U !l> CD r

(Cl < I CD • Z w....,. 71 ....>. ....>.

0 -(j) N

""1 I

0 0 ....>.


Main Turbine Bypass or EOC-RPT or Backup Pressure Regulator

Inoperable


(/)

C (/)

0 C rn I )> z z )>

C z -i N

w N I w

.i::,.

1.10

1.00

0.90

0.80

0.70

0.60

0.50

0.40

0.30

SSES UNIT 2 CYCLE 19 I I I

I I I I I I I I I I I I I I I I I I I I I I I I I

--------~--------~--------+------------------~--------~--------~--------~--------~--------~--------~--------•--------+--------•--------~--------• I I I I I 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 100 1 00 I I ________ L ________ L _______ _i_ _______ l_ _______ J ________ J ________ J ________ J ________ J ________ J ________ J ________ l ________ x_~--~--: ; 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 1108, 1.00 I I I I I I I I I I I I I I I I I I I 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--------1--------~--------~--------~--------~-------- 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 I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I

--------r--------r--------+---------+--------;--------;--------;--------i----- .--------1--------i--------1--------t--------t--------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 I I I I I I I I I I I I I I I I I I

--------~--------~--------:---------:--------~--------~------- -------~--------~--------4--------~--------4--------+--------+--------~--------I • I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I 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 I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I· I I I I I I I I I I I I I I I I --------r--------~-------~-- --~-------;--.-----;--------;--------~--------i--------1--------1--------i--------t--------t--------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 I I I I I I I I I I I I I I I I I I

--------~----- -r--------{---------:--------~--------~--------~--------~--------~--------~--------{--------{--------+--------~--------~--------1 I I I I I I

I I I I I I I I ______ _L_ _____ J _______ 1 _______ 1 _______ j_ _______ J__ _____ _J_______ REFERENCE: T.S. 3.2.3, 3.3.4.1, 3. 7 .6 and 3. 7.8 __ : I I I I I I . . I : I I I I I I I I I I ...... ___ _. ____ ._ ___ _._ ___ ......__~

~~~:-~~+~~------~-------t-------t-------~--------~--------~--------~--------~--------J-------~ USED IN DETERMINING FDLRX ~--' I I I I I I I I I I I I I I I I I I I

I : I : : : ,....,., ___ _,,._ ___ ~•---......:'----~•----'----'-----=-----'----, I I I I I I --------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

--------~--------~--------+--------...... -------~--------~-------' I I I I I I I I I I I I I I I I I

FOR MAIN TURBINE BYPASS INOPERABLE, SAFETY ANALYSES ASSUME THAT TWO OR MORE BYPASS VALVES

ARE INOPERABLE PER SR3.7.6.1 OR 3.7.6.2 I I I I 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--------:-------1--------1--------1--------1--------1--------1--------1-- ------1--------t--------t-----. --t--------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 --------r--------r--------,---------,--------~--------~--------~--------,--------,--------~--------~--------~--------T--------T--------r--------

30

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

40 50 60 70 80 90 100 Total Core Flow (MLB/HR)

FLOW DEPENDENT LHGR LIMIT MULTIPLIER MAIN TURBINE BYPASS OR EOC-RPT OR BACKUP PRESSURE REGULATOR INOPERABLE


110

(j) C (j)

D C m I ~ z z ~ C z -; N

w N I w

01

1.10

1.00

0.90

o:ao

0.70

0.60

OAO

0.30

SSES UNIT 2 CYCLE 19 I I I

I I I I I I I -----1--------1--------1--------r

1

--------r 1 oo, 1.00 ____ J _______ J _______ J 94.46, 1.00 L_~! ___ ..

I I I I

LEGEND

CURVE A: BASE CURVE I I I I I I I I I I I I I I I I I I I I CURVE B: CORE POWER~ 26% AND CORE FLOW~ 50 MLBM/HR

-----~--------~--------~--------+- -----+-----------....,...----,-----,,-------,-----,-----,-----,-----,,----......,.-----,--1 I f f f f I I I I

I I I I I I I I I I I I I I I I I I I I I I I --------~--------~-------..... --------+---------+--------~--------~--------~--------~--------~--------~--------~--------~----- -+--------+--------' I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I 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--------t-------~--------~--------i--------i--------i--------i--------i--------i ------t--------t--------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

--------~-. ------~--------{---------{---------}-------~--------~--------~--------~--------~----- ·~---- --~--------+--------+--------l 1 1 1 1 1 1 1 1 1 I ao, o.75 ll 1 1 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

--------r--------r--------r-------~-------.+--------~--------1--------1---- ~ ·1--------~------- ~----- -------1--------t--------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 I I I I I I I I I I I --------~--------~-------;---------t--------t------- -- ,--------i--------i--------i--------1--------1--------1--------t--------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 I I I I I I I I I I I I ------- r l26.0c1, 0.6~-------~-------~-------1--------1--------1--------1--------1--------1--------1--------1--------t--------t--------l . ~ I I I I I I I I I I I I I I I I I I I I I I I I I I I --------r ------r--------t---------t---------t--------~--------~--------~--------~--------~--------~--------~--------~--------+--------•--------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 Ir-__ ......_ ___ _._ ___ ....._ __ _..__ __ __. ___ ......_ ___ _.__......,

-------+ ----- r--------r-------r-------r-------r-------r------11 REFERENCE: T.S. 3.2.3, 3.3.4.1, 3.7.6, and 3.7.8

! 26, ~.50 L!-------!-------!-------1-------i-------~_ .. _-_-_-_-__ -_-.,r,_-_-__ -_-_-_-_=~------_-_-;:::::::c:===::c:===:::c:===c:==:::1==~ I I I I I I I I I

B I f f 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--------...i--------~-------~--------~--------~--------~--------~-----..... ....,...----:----.,..-----,----,--___, ! 1

26, ?·43 I I I I I FOR ~AIN ,,,;RBINE

1

BYPA~S INOPERABLE, SAFETY ANALYSES

USED IN DETERMINING FDLRX

--i---------i--------t-------t-------t---- ASSUME THAT TWO OR MORE BYPASS VALVES ARE INOPERABLE

-123, o'.40 L __ J ______ j _______ L------1--------,---------,--------,------- ~ER SR., 3.7.6.1 .. 0R 3.7:6.2 ____ -r--------T--------r-------1 I I I I I I I I I I I I I I

20

I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I

30 40 50 60 70 80 90


POWER DEPENDENT LHGR LIMIT MULTIPLIER MAIN TURBINE BYPASS OR EOC-RPT OR BACKUP PRESSURE REGULA TOR INOPERABLE


100

:::a CD <

Rev. 14



PL-NF-17-001 Rev. 1 Page 35 of 62

l/')

C l/') 1.10 0 C m :::r:: )> z z 1.00 )>

C z =l N 0.90

... .2! C. E :s :!!:

0.80

0::: (!) :c ..J -C 0.70 Cl) ~

LU C N

Cl)

I Q. LU Cl)

-..J C

== 0.60

0 u::

0.50

0.40

0.30

SSES UNIT 2 CYCLE 19 I h I 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--------~-------~--------~--------:..-------I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I 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--------~-------~--------~-------~--------T-------"'T"-------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 108 0 94 I I I I 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--------~-------~--------•------- ~-------1--------~-------~--------·--------t--------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 I I I

I I I

I I I I I I I I I I I I I I I I I I I I I I I I I I I I I -------~--------~-------~--------·--------~-------~--------~-------~--------•--------~-------~------- ------~--------·-------...,..·------' I I I' I I I I I I I ' I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I

I I I I I I I I I -------~--------L••••---~--------~------- ~-------~--------~-------~--------~------ ------J--------~-------~--------~-------~-------1 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 -------J--------L••••---J--------~--------~-------J--------L---••• -------~--------'--------J--------L-------J--------~--------'--------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 -------1--------~-------;--------t------- r------ -------~-------;--------t--------r-------1--------~-------;--------t--------t-------

• I I I I I I I I I I I I

I I I

I I I I I I

l I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I

-------i--------~-------~------- -------r-------i-------....-~~~~~~~~~~~~~~~~~~~~~~~~----.~ 1 I I I I I I I I I I I I I I I I I I

-------~------- ------~ -------+--------r-------~-------' • I I I

I I I I I I I I I

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

I I I I I I I I I I I I I I I

------~--------~-------~ -------+--------~-------~--------~-------~--------+-------~-------~--------~-------~--------+--------:--------!30, o .. 551 i i i i i i l I · REFERENCE: T.S. 3.2.3 °and TRM 3.3.7 I

I I I I I I I I . . -------,--------r-------,--------T--------r-------,--------r-------,--------y--------r-------~--------r-------~--------y--------.-------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 -------,--------r-------,--------T·-------r-------,--------r-------,--------T·-------,..------1 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 I I I I I I I I I I I I I I I I I I I I -------~--------r-------~--------T·-------~-------~--------r-------~--------T--------,.-------~--------r-------~--------T·------..... -------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 -------~--------~-------~--------+--------~-------~--------~-------~--------+--------~-------1--------~-------~--------+--------+--------

30

I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I

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

FLOW DEPENDENT LHGR LIMIT MULTIPLIER ONE TSV OR TCV CLOSED*


90 100

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

110

(/)

C (/)

0 C m I )> z z )>

C z =i N

... -~ C. E :I :!!: 0:: (!) ::c ...J ..... C: Cl)

"C C:

w Cl) C.

N Cl) I C w ...

00 Cl)

3:: 0 ll.

1.10

1.00

0.90

0.80

0.70

0.60

0.50


LEGEND

CURVE A: BASE CURVE

I I I I

I I I I ---r----------,-----------r----------~-----------1 I I I I I I I I I I I I I I I I I I I ---r----------~-----------r----------~-----------1 I I I I I I I

CURVE B: CORE POWER~ 26% AND CORE FLOW~ 50 MLBM/HR : : : : ~---~---~----~----~---~----~---~--~---r----------,-----------r-----.-11-s-.o ... ,o_, -o-.9-0.,1--• 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 : ; ; ; ; ; A ; I I I I

I I I I I I I I I I I ----------~-----------~----------J-----------~----------~-----------~---------- --------~----------~-----------~----------~-----------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 ----------~-----------~----------J-----------~----------1 I I I I I I I I I I I I I I I I I ----------~-----------L----------J I I I I I I

I

-------L--------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 --------~----------J-----------~----------~-----------~----------~-----------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

J25·0t O.GS '---~-----------~----------~---------1 REFERENCE: T.S. 3.2.3 and TRM 3.3.7 ~----' I I I L-r-.----~------,------,-----~------,--~ I

I

----------~-' B ! I ----------'T-

I I I I I I I I I I

-------t----------i-----------r----------1-----------r----------f------- USED IN DETERMINING FDLRX

l l I I I I I

~~!-~:~0

-------i-----------~----------i-----------~----------~-----------r----------,-----------r----------,-----------1 I I I I I I I I I I I I I I I I I I I

23, 0.47 I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I

0.40

0.30

--------r----------,-----------r----------,-----------r----------~-----------r----------~-----------r----------~-----------~--~•~ I I I I I I I I I

I I I I I I I I I I I 26, 0.43 : : : : : : : : : I . . I I I I I I I I I ---~-----------~----------~-----------~----------1-----------~----------~-----------~----------1-----------~----------1-----------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

--,23, 0.40--------~----------~-----------~----------~-----------~----------~-----------~----------~-----------~----------~-----------. . . I I I I I I I I I I

20

I I I I I I I I I I I I I 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

30 40 50 60


POWER DEPENDENT LHGR LIMIT MULTIPLIER ONE TSV OR TCV CLOSED"


70

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

80


7.0 ROD BLOCK MONITOR {RBM) SETPOINTS AND OPERABILITY REQUIREMENTS


Technical Specification 3.3.2.1

7.2 Description

The RBM Allowable Value and Trip Setpoints for;

a) Low Power Range Setpoint, b) Intermediate Power Range Setpoint, c) High Power Range Setpoint, d) Low Power Range - Upscale, e) 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, and Backup Pressure Regulator Operable and Inoperable.

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.


Rev. 14

Function

Low Power Range Setpoint

Table 7.2-1 RBM Setpoints

Intermediate Power Range Setpoint

High Power Range Setpoint

Low Power Range - Upscale

Intermediate Power Range - Upscale

High Power Range - Upscale

Allowable Value<1l

28.0

63.0

83.0

123.4

117.4

107.6

PL-NF-17-001 Rev. 1 Page 39 of 62

Nominal Trip Setpoint

24.9

61.0

81.0

'

123.0

117.0

107.2

<1J Power setpoint function (Low, Intermediate, and High Power Range Setpoints) determined in percent of RATED THERMAL POWER. Upscale trip setpoint function (Low, Intermediate, and High Power Range - Upscale) determined in percent of reference level.

Table 7.2-2 RBM System Operability Requirements

Thermal Power MCPR <2,3l (% of Rated)

2: 28 and< 90 < 1.76

2: 90 and< 95 < 1.47

~95 < 1.68

<2l Applicable to Main Turbine Bypass Operable and Inoperable, EOC-RPT Operable and Inoperable, and Backup Pressure Regulator Operable and Inoperable.

<3l Applicable to both Two Loop and Single Loop Operation.



8.0 RECIRCULATION LOOPS - SINGLE LOOP OPERATION


Technical Specification 3.2.1, 3.2.2, 32.3, 3.3.4.1, 3.4.1, 3.7.6, and 3.7.8



8.3 Description

APLHGR

The APLHGR limit for ATRIUM™-10 fuel shall be equal to the APLHGR Limit from Figure 8.2-1.

The APLHGR limits in Figure 8.2-1 are valid for Main Turbine Bypass Operable and Inoperable, EOC-RPT Operable and Inoperable, and Backup Pressure Regulator Operable and Inoperable in Single Loop operation.

Minimum Critical Power Ratio Limit

The MCPR limit is specified as a function of core power, core flow, and plant equipment operability status. The MCPR limits for all fuel types (ATRIUM™-10) shall be the greater of the Flow-Dependent or the Power-Dependent MCPR, depending on the applicable equipment operability status.




b) Main Turbine Bypass Inoperable



c) EOC-RPT Inoperable




Rev. 14

d) Backup Pressure Regulator Inoperable

PL-NF-17-001 Rev. 1 Page 41 of 62

Figure 8.2-8: Flow-Dependent MCPR value determined from BOC to EOG

Figure 8.2-9: Power-Dependent MCPR value determined from BOC to EOG

e) One Turbine Stop Valve (TSV) or Turbine Control Valve (TCV) Closed

Figure 8.2-10:Flow-Dependent MCPR value determined from BOC to EOG

Figure 8.2-11 :Power-Dependent MCPR value determined from BOC to EOG

The MCPR limits in Figures 8.2-2 through 8.2-11 are valid only for Single Loop operation.

Linear Heat Generation Rate Limit

The LHGR limits for Single Loop Operation are defined in Section 6.0.

RBM Setpoints and Operability Requirements

The RBM setpoints and operability requirements for Single Loop Operation are defined in Section 7.0.


(/l

C (/l

0 C rn :c )> z z )>

C z =i N

tu N

I .i:,. tu


I I I I I I

I

I I I. I

I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I 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---T---r---~---,---~---,---T---T---r---~---.---~---,---,---T---r---~---.---~---,---,---T---r---~---r---~---,---,---T---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 I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I

__ l __ j_ __ j ___ l__J __ J __ J __ l __ j_ __ j__j __ J __ J __ J __ l __ j_ __ j_ __ j__[ : R~F~R~N:c~ T.~. ~-4~ 1 ~n~ 3>. ~ : Ii_ __ I I I I I I I I I I 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 __ J ___ j __ J __ j __ J __ _l __ 1 __ j_ _ _j __ _! __ j __ J __ _l __ 1 __ j_ __ j __ _! __ J: : :us:ED :IN ~E~E~M1~1N~ ~A~RA~ : : J 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 I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I

14.0

~ 12.0 I I I I I I I I I I 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---~---~---·---~---~---~---1---~---~---~---~---~---~---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 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 :J

... Cl) ra., C ra ra 0::: ii: C

Cl) .2 c, .. ra e! ... Cl) Cl) C

~~ .. ra Cl)

:c ... ra Cl) C :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 --""'---J---J---~---~---L---L--...1...--J---J---~---~---L---L--...L.--J---J---J---~---L---L---1---J---J---J---~---L---L---~--J---J---J---~---L---I I I I I I I I I I I I I I I I I I I I I I I I I I I I I 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 0 0 10 0 I I I 15000 10 0 I I I I I I I I I I I I I I I I I I I I I I I I . ' . : : : ' . : : : : : : : : : : : : : : : : : : : : : : : : I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I 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---t---t---t---~---:---1---~---i---t---t---~--~--1---i---t---t---t---~---:---1---i---1---t---t---l I I I I I I I I I I I I I I I I I I I I I I I I

10.0 I I I I I I I I I I I I I I I I I I I I I I I I I

I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I

I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I 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---t---t---t---r---t--i---i---t---t--- - ---t--i---i---t---t---t---t---t--i---i---t---t---t---t---r--i---i---t---t---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 I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I 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---f---+---~---~---1---i---t---f---+---~---~---l---i---t---f--- - ---~---l---i---i---f---+---~---~---1---i---t---f---+---~---I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I 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 --,---,---,---T---T---r---r.---r--~---,---~---T---r---r--"'T"--~---,---~---T---r---r---r--~---,--- -T---r---r---r--~---,---~---T---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 I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I 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---,---~---,---~---T---~---r---,---~---,---~---T---r---r---,---~---~---~---T---r---r---r---~--- -,---T---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 I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I : ! : I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I II ~ 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 67000 5 6 ---r--,---1---r---r---r---r---r--,---1---r---r---r---r---r--,---1---r---r---r---r---r--,---1---r---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 I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I

8.0

6.0

4.0 0.0

I I I 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

10000.0 20000.0 30000.0 40000.0 50000.0 60000.0 70000.0 Average Planar Exposure (MWD/MTU)

AVERAGE PLANAR LINEAR HEAT GENERATION RATE LIMIT VERSUS AVERAGE PLANAR EXPOSURE -SINGLE LOOP OPERATION



Main Turbine Bypass / EOC-RPT / Backup Pressure Regulator

Operable


Vl C 3.6 Vl

0 C m I

3.4 )> z z )>

C z 3.2

=i N

3.0

.... 2.8 ·e ::i C) C: 2.6 :;:; ns ... Cl) C. 0 2.4 c..u 0:::

N a. I (.) .j:::,,

(J1 a: 2.2

2.0

1.8

1.6

1.4


LEGEND ~


>---CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME

~

SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES >---


I USED IN DETERMINING MFLCPR I

130, 1.871 - A B

I

I REFERENCE: T.S. 3.4.1 and 3.2.21 I 108, 1.48 ~

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

SINGLE LOOP OPERATION (BOC to EOC) FIGURE 8.2-2

-110

l/l C l/l

0 C m I )> z z )>

C z =i N

w N

I .j:::,, Cl'l

:!: E :J Cl C:

:;:::: Ill ... Cl) C. 0 0:: a.. ()

~

46

4.4

4.2

4.0

1-------+---------l



CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME 3.8 I 23, 3.711

----,...---+--------1---1

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

"" 3.6 , .._ I I 123, 3.65 F\ 26, 3.55 I I I

3.4 126, 3.42 11--------1-----~---I ,__ C --l-==:::::::::i:=:!..._-----l--------1----l

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

3 .2

3 .0 USED IN DETERMINING MFLCPR

2 .8

2 .6 I 26.01, 2.40 I

2 .4 .............

2 .2 -............._

I 61 140, 2.0 I

A - 8 160, 1.901 .... -2 .0

1.8

1.6 ]REFERENCE: T.S. 3.4.1 and 3.2.21

1.4 20 30 40 50 60 70

Core Power(% RATED) 80 90

MCPR OPERA TING LIMIT VERSUS CORE POWER MAIN TURBINE BYPASS/ EOC-RPT / BACKUP PRESSURE REGULATOR OPERABLE


100, 1.90 I

100

Rev. 14

Main Turbine Bypass Inoperable

SUSQUEHANNA UNIT 2 · 3.2-47

PL-NF-17-001 Rev. 1 Page 46 of 62

Vl C V,

0 C m :::r: )> z z )>

C z =i N

~

E :J

. C) C:

:;:l ns ... Q) C. 0

w 0:: N ll.

I () ~ 00 :e


4.0 LEGEND . -CUR.VE A: MAXIMUM ALLOWABLE AVERAGE SCRAM

3.8 INSERTION TIME -3.6 CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME -~-4.

3.2 SAFETY ANALYSES ASSUME THAT TWO OR MORE BYPASS -VALVES ARE INOPERABLE PER SR 3.7.6.1 OR 3.7.6.2

3.0 I I I

2.8 I USED IN DETERMINING MFLCPR

2.6

2.4

2.2 130, 2.111

...... 2.0 A B

1.8 H REFERENCE: T.S. 3.4.1, 3.7.6, and 3.2.2 I I 108, 1.65 I-

1.6

1 .. 4 30 40 50 60 70 80 90


MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW MAIN TURBINE BYPASS INOPERABLE


-

100 110

V'l

~ 44 o· C m I )> z z )>

C z ~ f',..J

:t:: E

::::i C) C ;:; ra .. Cl) C. 0

w ~ f',..J Cl.

I 0 .i::,. lO :!E

4.2 W23, 4.121 . \ 4.0 \

3.8 ' " - C - 126, 3.78 I

I 23, 3.651 \ 3.6 \

\ '26, 3.42' 3.4

3.2

3.0

2.8

2.6 I 26.01, 2.45 I

2.4 ......

"' ...... "'--. : 40, 2.11 : 2.2

..............

SSES UNIT 2 CYCLE 19 I I I I I

LEGEND



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

SAFETY ANALYSES ASSUME THAT TWO OR MORE BYPASS VALVES ARE INOPERABLE PER SR 3.7.6.1 OR 3.7.6.2


160, 1.961 A B 2.0 I REFERENCE: T •. s. 3.4.1, 3.7.6, and 3.2.21

1.8 20 30 40 50 60 70 80

Core Power(% RATED)

MCPR OPERATING LIMIT VERSUS CORE POWER MAIN TURBINE BYPASS INOPERABLE


90

--

----C

100, 1.96 I

100

"U "U ru r

(C I

CD z .:,.. 71 CX) ::a ...>.

0 CD -;-J -<o 0). 0 N...>....>.

SUSQUEHANNA UNIT 2

Rev. 14

EOC-RPT Inoperable

3.2-50

PL-NF-17-001 Rev. 1 Page 49 of 62

(./l

C 4.0 (./l

0 C m :I: )>

3.8 z z )> 3.6 C z =l N

3.4

3.2

:!:: E 3.0 :J Cl C

2.8 :.:: n:s ... Cl) C. 0 2.6 w 0::

N a. I (.) u,

I-' :a: 2.4

2.2

2.0

1.8

1.6

1.4


LEGEND -

CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME -

CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME -

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

I I

I USED IN DETERMINING MFLCPR I

· l 30, 1.871

-A

B

REFERENCE: T.S. 3.4.1, 3.3.4.1, and 3.2.2 ! : 108, 1.48 I

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

MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW EOC-RPT INOPERABLE


-100 110

CJ')

C CJ')

§ m I )> z z )>

C z =i N

4.6

4.4

4.2

4.0

SSES UNIT 2 CYCLE 19 ,,

t-------1,------+---1CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME

r;:::==:::;---t-------t---1CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME 3.8 ...j 23, 3.71 li----------t

CURVE C: CORE POWER~. 26% AND CORE FLOW~ 50 MLBM/HR

3.6 "-..,_ I I - I 23, 3.65 l\.t""t"'t""l-\-2.....:6,_3_.5_5...J-----;----;.___----r_~-----r-----~----~----~--.E 3.4 1 1 1 1

:J _ C _ .JL..:2:.:::6!....:, 3~.4:::!2:..Jlr----r-----11 g> 3.2 -

~ a, 3.0 Q. 0 I


I I I I I I I

----------

-----w 0::: 2.8 N C..

USED IN DETERMINING MFLCPR t= I (.)

~ :;E 2.6

2.4

2.2

2.0

1.8

i------+---1126.01, 2.40 :------------------+----------------

,............._ 1------+-.;;:,o,,,,i:::---1: 40, 2.06 11------------------+----------

I I A B 11 oo, 1.90 I 60, 1.90 ----- -- ---+-------!:===,---'

...... ___

HREFERENCE: T.S. 3.4.1, 3.3.4.1, and 3.2.21------------------+-----1.6

1.4 20 30 40 50 60 70 80

Core Power (%.RATED)

MCPR OPERATING LIMIT VERSUS CORE POWER EOC-RPT INOPERABLE


90 100

:;a CD :=::: ...... ~


Backup Pressure Regulator. Inoperable


<.n C 4.0 <.n 0 C m :c 3.8 )> 2 z )> 3.6 C z =i N

3.4

3.2

~

E 3.0 :::i C) C

2.8 ;:; cu ... Cl) C. 0 2.6 w Cr!

N C. I u u,

.j:::,, :al: 2.4

2.2

2.0

1.8

1.6

1.4

. SSES UNIT 2 CYCLE 19

LEGEND ,..__

CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME -

CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME -

-SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES



---j 30, 1.87 I

-A

8

I REFERENCE: T.s~ 3.4.1, 3.7.8, and 3.2.2

30 40 50 60 70 80 90

Total C~re Flow (MLB/HR)

MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW BACKUP PRESSURE REGULATOR INOPERABLE


100

-

I 108, 1.48 I

-110

(./l

C (./l

0 C m I )> z z )>

C z =i

46

4

4

4

.4

.2

.o

N 3 .8 I 23, 3.711

w N

I u, u,

:!:: E :J en C: :;:: ns ... (I) C. 0 0:: ll. (.)

~

3

3

3

3

2

2

2

2

2

6 " I I • , '""' I 26, 3.55 I I 23, 3.65 : '\

·4 - c -n2s, 3.421 ...,.

.2

.0 : 26.01, 2.77:

.8 ....__

.6 -..............

.4

.2

.0


LEGEND



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


I I I I

I USED IN DETERMINING MFLCPR

140, 2.51 \ A

---- --........_ B

---.... , so, 2.141 --........_

~

1 .8 ~ REFERENCE: T.S. 3.4.1, 3.7.8, and 3.2.21

.6 1

1.4 20 30 40 50 60 70 80


MCPR OPERA TING LIMIT VERSUS CORE POWER BACKUP PRESSURE REGULATOR INOPERABLE


90

----------

I

100, 2.141

100

"U "U tu r

(Q I

CD z CJ1 71 .j:>. ::0 ....>.

0 CD -;-J --h < 0 O'). 0 N->-->-

Rev. 14



PL-NF-17-001 Rev. 1 Page 55 of 62

l/l C 4.0 l/l 0 C m I 3.8 )> z z )> 3.6 C z =i N

3.4

3.2

:!:: E 3.0 :J C) C:

2.8 :;:; cu ... Cl) C. 0 2.6 w 0:::

N ll.. I (.) lJ1

'-I :!E 2.4

2.2

2.0

1.8

1.6

1.4


LEGEND -CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM

INSERTION TIME -

CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME - -

-SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES



LJ 30, 2.11 I

-A 8

J REFERENCE: T.S. 3.4.1, 3.2.2, and TRM 3.3.7 I

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

MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW ONE TSV OR TCV CLOSED*


90 100

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

-

1108, 1.67 I

-

110

Vl C 4.6 Vl 0 C m 4.4 I )> z 4.2 z )>

C 4.0 z =i N 3.8

3.6

:!:: 3.4 E :J C) 3.2 C: :;::

C'CI ... 3.0 Q)

C. 0

c..u a: 2.8 N 0..

I (.) u, CX) a=: 2.6

2.4

2.2

2.0

1.8

1.6

1.4

SSES UNIT 2 CYCLE 19 I

LEGEND



: 23, 3.71: CURVE C: CORE POWER~ 26% AND CORE FLOW~ 50 MLBM/HR ~

'' I I I 23, 3_65'"p--~ I 26, 3.55 I

SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES 126, 3.421 -c ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2


I 26.01, 2.40 I

--........... --..........

: 40, 2.06 I --.......... A B ~

: 60, 1.90:

J REFERENCE: T.S. 3.4.1, 3.2.2, and TRM 3.3.7 I

20 30 40 50 60 Core Power(% RATED)

MCPR OPERATING LIMIT VERSUS CORE POWER ONE TSV OR TCV CLOSED*


70

*Operation with one TSV or TCV closed is only supported at power levels :,; 75% rated power

: 75, 1.90

80

Rev. 14 PL-NF-17-001 Rev. 1 Page 58 of 62 ·

9.0 POWER/ FLOW MAP


Technic~I Specification 3.3.1.1

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


";F. -.... ~ a. iii E .... Q)

..c: I-

110

100

90

80

70

60

50

40

30

20

10

Rev. 14

Purpose: -------------------

Initial/ Date: I

STABILITY REGION II IMMEDIAlELY EXITIAW APPLICABLE T . .:: PROCEDURE. ~

RESJRICTED REGION IF ABOVE MELLLA BOUNDARY, IMMEDIA lEL Y EXITIAW APPLICABLE PROCEDURE .

I I I I I I I I I I I I

IHJJ:: J(<-..J.J=:=:=: =: =-==,=,=, =, ==,=.=.=,==: =: =:=:4-1., _L_' -r-r-r-r- ·t-rt·t -r-t·;--1-- --i--tl·r- --:·r-r·r·r- --1-·rT·r ·r-T·rr· ·r-r-T·r- -

:~::~:r:~: :+:r:~:~: :i, :+. :+, :~.:: :1,.·:i, :1·r I I I I I I t I

I : : : : : : : I I

-1--:-:4-:- --:-·t·-~-t- I I I I -:-

-r-r·t·r- ·t·rt·r -~.~::: _~-~-1

!r. __ -:':1: _~,-~.11-___ : --· ·r·r·-:-·r- -T-rT·r- ·

-~--~-~--~- -+-~--:..-~-' I I I I I I I I I I I I I I I

I I I l I I I I I I I I I I I I _., __ .__,. __ '"_ .............. .a. I I I I I I I I I I I I I I I I

--t--~-1--r- --:-:--:-1-:~ttt +Hf

I I I 1 I I I I - --'--•--'--"'-

' I I I I I I I I I I

- -'---'--'-- --l..-4---'--l.-l I I I I I I

I I I I t I I I

--t--:--1-+- -+-t-+-t-1 I I I I I I I

-1--r-1--r- --1-·t·-r·t-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 : l : : : l -:--:-:--r- --:-t--i--t--tt-tt- -t-r-t-t

I I I I

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PL-NF-17-001 Rev. 1 Page 59 of 62

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Total Core Flow (Mlbm/hr) (for SLO <75% Pump Speed Use Form G0-200-009-2)

Figure 9.1 SSES Unit 2 Cycle 19 Power I Flow Map

100


Rev. 14

10.0 OPRM SETPOINTS


Technical Specification 3.3.1.1

10.2 Description

PL-NF-17-001 Rev. 1 Page 60 of 62

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 MCPR 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

3.2-61

Rev. 14

11.0 REFERENCES

PL-NF-17-001 Rev. 1 Page 61 of 62

11.1 The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRG, 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-84-105(P)(A), Volume 1 and Volume 1 Supplements 1 and 2, "XCOBRA-T: A Computer Code for BWR Transient Thermal-Hydraulic Core Analysis," Exxon Nuclear Company, February 1987.

5. 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.

6. XN-NF-80-19(P)(A), Volumes 2, 2A, 28, and 2C "Exxon Nuclear Methodology for Boiling Water Reactors: EXEM BWR ECCS Evaluation Model," Exxon Nuclear Company, September 1982.

7. 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.

8. 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. ·

9. XN-NF-85-67(P)(A), Revision 1, "Generic Mechanical Design for Exxon Nuclear Jet Pump BWR Reload Fuel," Exxon Nuclear Company, Inc., September 1986.

1 O. ANF-524(P)(A), Revision 2 and Supplements 1 and 2, "Advanced Nuclear Fuels Corporation Critical Power Methodology for Boiling Water Reactors," November 1990.

11. NE-092-001A, Revision 1, "Licensing Topical Report for Power Uprate With Increased Core Flow," Pennsylvania Power & Light Company, December 1992 and NRG SER (November 30, 1993).



12. ANF-89-98(P)(A) Revision 1 and Supplement 1, "Generic Mechanical Design Criteria for BWR Fuel Designs," Advanced Nuclear Fuels Corporation, May 1995. . .

13. EMF-2209(P)(A), Revision 3, "SPCB Critical Power Correlation," AREVA NP, September 2009.

14. 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.

15. EMF-2158(P)(A), Revision 0, "Siemens Power Corporation Methodology for Boiling Water Reactors: Evaluation and Validation of CASM0-4/MicroburnB2," Siemens Power Corporation, October 1999.

16. EMF-CC-074(P)(A), Volume 4, Revision 0, "BWR Stability Analysis -Assessment of STAIF with Input from MICROBURN-B2," Siemens Power Corporation, August 2000.

17. NED0-32465-A, "BWROG Reactor Core Stability Detect and Suppress Solutions Licensing Basis Methodology for Reload Applications," August 1996.

18. ANF-913(P)(A), Volume 1 Revision 1 and Volume 1 Supplements 2, 3, and 4, "COTRANSA2: A Computer Program for Boiling Water Reactor Transient Analyses," Advanced Nuclear Fuels Corporation, August 1990.

19. ANF-1358(P)(A), Revision 3, ''The Loss of Feedwater Heating Transient in Boiling Water Reactors," Framatome ANP, September 2005.


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