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Technical Requirements Manual
	ML21105A487
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Site:	North Anna, 05000337
Issue date:	04/01/2021
From:	; Susquehanna
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
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of 2

SSES MANUAL Manual Name:

TRM2

.anual

Title:

TECHNICAL REQUIREMENTS MANUAL UNIT 2 Table Of Contents Issue*Date:

03/31/2021 Procedure Name TEXT LOES Rev 99

Title:

LIST OF EFFECTIVE SECTIONS TEXT TOC 27

Title:

TABLE OF CONTENTS TEXT 1.1 0

Issue Date 01/03/2019 03/05/2019 11/19/2002

Title:

USE AND APPLICATION DEFINITIONS TEXT 2.1 1

TEXT 3.0 TEXT 3.1.1 TEXT 3.1.3 5

12/18/2017 Change ID Change Number

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 19 03/31/2021

Title:

CORE OPERATING LIMITS REPORT (COLR)

Page 1 of 15 Report Date: 04/01/21

SSES MANUAL j)

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. INSTRUME;NTATION.

TEXT 3.3.4 11 07/21/2017

Title:

INSTRUMENTATION TRM POST-ACCIDENT MONITORING INSTRUMENTATION TEXT 3.3.5 0

11/19/2002 Titl'e: INSTRUMENTATION THIS PAGE INTENTIONALLY LEFT BLANK

. -5....,03/05/2019:-

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 INSTRUMENTA1ION TEXT 3.3.12 2

04/02/2019

Title:

WATER MONITORING INSTRUMENTATION Page 2 of 15 Report Date: 04/01/21

SSES MANUAL M~nual Name:

TRM2

.a~ual

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

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TEXT 3.4.5 1

04/26/2006

Title:

REACTOR COOLANT SYSTEM REACTOR VESSEL MATERIALS

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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: 04/01/21

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;. (URS) AND GROUND. WATER* LEVEL*. *

TEXT 3.7.3.1.

6 02/13/2020

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04/16/2009

Title:

PLANT SYSTEMS SPRAY AND SPRINKLER SYSTEMS

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PLANT SYSTEMS CO2 s*YSTEMS TEXT 3.7.3.4 2

04/16/2 o.o9

Title:

PLANT SYSTEMS HALON SYSTEMS T_EXT 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 TEXT 3.7.4 1

04/26/2006

Title:

PLANT SYSTEMS SOLID RADWASTE SYSTEM Page 4 of 15 Report Date: 04/01/21

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

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9

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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

Title:

ELECTRICAL AUTOMATIC 2

12/14/2004 POWER MOTOR OPERATED VALVES (MOV) THERMAL OVERLOAD PROTECTION -

r Page 5 of 15 Report Date: 04/01/21

SSES MANUAL Manual Name:

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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 POWE~. DEGRADEP VOLTAGE I\\RQTECTION TEXT 3.8.6 3

03/05/2019

Title:

ELECTRICAL POWER EMERGENCY SWITCHGEAR ROOM *cobLING

.TEXT 3.8.7 3

02/25/2021

Title:

BATTERY MAINTENANCE AND MONITORING PROGRAM rEXT 3*,.9.1*

Title:

REFUELING OPERATIONS. DECAY.T.IME 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 10/17/2019

Title:

MISCELLANEOUS INDEPENDENT SPENT FUEL STORAGE INSTALLATION (ISFSIJ°-

TEXT 3.10.4 2

04/17/2009

Title:

INTENTIONALLY LEFT BLANK Page 6 of 15 Report Date: 04/01/21

Manual Name:

TRM2 SSES MANUAL

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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 EFFLDENTS, 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 Ti th:!: -RADIO.ACTIVE EFFLUENTS.LIQUID' *RADwASi'E. EFFLUENT -'MONITORING. INSTRUMENTATION

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03/05/2015

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Title:

RADIOACTIVE EFFLUENTS DOSE -

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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. l *l. 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: 0~/01/21

SSES MANUAL j

Manual Name:

TRM2 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 EFF~UENTS 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

.... *.. i'it"le: LOADS CONTROL PROGRAM-CRANE TRAVEL-SPENT FUEL STORAGE POOL

TEXT 3.12.2 4

04/17/2008

Title:

LOADS CONTROL PROGRAM HEAVY LOADS REQUIREMENTS TEXT 3.12.3 0.

Title:

'LOADS CONTROL.PROGRAM LIGHT. LOADS REQUIREMENTS

*ll/19/2Q02 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:

ADMIN~STRATIVE CONTROLS RADIATION PROTECTION PROGRAM Page 8 of 15 Report Date: 04/01/21

SSES MANUAL Manual Name:

TRM2

-~anual

Title:

TECHNICAL REQUIREMENTS MANUAL UNIT 2 TEXT 4.7 0

09/27/2003

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:

-"REACTJ;.VITY-:: CONTROL "-SYSTEM.. B.ASES: ANTICIPATED* TRANSIENT--' WITE;OUT. SCRAM ALTERNATE.

ROD INJECTION (ATWS-ARI) INSTRUMENTATION TEXT B3.l.2 0

n/19/2002

Title:

REACTIVITY CONTROL SYSTEM BAS.ES CONTROL Rob* DRIVE* (CRD) HOUS.ING *sui?J?ORT....

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12/18/2017

Title:

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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: 04/0_1/21

SSES MANUAL Manual Name:

TRM2 tlanual

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

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01/03/2019

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02/22/2012

Title:

INSTRUMENTATION BASES REACTOR RECIRCULATION PUMP MG SET STOPS

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_io/22/2003

Title:

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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 D~te: 04/01/21

SSES MANITAL Manual N.ame:

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.l 2

03/17/2020

Title:

ECCS RPV WATER INVENTORY* CONTROL AND RCIC SYSTEM ADS MANUAL INHIBIT TEXT B3.5.2 2,

03/05/2019

Title:

ECCS RPV* WATER I::NVENTORY CONTROL,A,ND R_CIC SYSTEM ECCS RPV WATER-INVENTORY CONTROL AND RCIC MONITORING INSTRUMENTATION

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03/05/2019

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11/19/2002

Title:

CONTAINMENT BASES VENTING OR PURGING

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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.l 0

11/19/2002

Title:

PLANT SYSTEMS BASES EMERGENCY SERVICE WATER SYSTEM (SHUTDOWN)

TEXT B3.7.2 0

11/19/2002

Title:

PLANT.SYSTEMS BASES ULTIMATE HEAT SINK (UHS) GROUND WATER LEVEL TEXT B3.7.3.l 4

02/16/2017

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: 04/01/21

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 06/19/2019

Title:

PLANT SYSTEMS BASES HALON SYSTEMS TEXT B3.7.3.5 1

04/26/2006

Title:

PLANT SYSTEMS BASES FIRE HOSE STATIONS TEXT B3.7.3.6 1

04/26/2006

'. Title*: **pLAf\\JT, SYSTEMS* BASE8 YARb: FIRE. HYDRANTS AND HYDRANT HOSE HOUSES..

TEXT B3.7.3.7 0

11/19/2002

Title:

PLANT SYSTEMS BASES FIRE RATED ASSEMBLIES rE_~T.*B3_*-.7,3.8 *::: *..

3

.. 09/27/2012-..

* £:i."t:"1e*; **PLANT* s'Y-sTE°r-1is BAsEs FIRE DETECTION INSTRUMENTATION TEXT B3.7.4 0

11/19/2002

Title:

PLANT SYSTEMS BASES SOLID RADWASTE SJ-STEM 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 RADIAT°ION MONITORING INSTRUMENTATION Page 12 of 15 Report Date: 04/01/21

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 C0NTROL 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

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Title:

ELECTR.ICAL POWER BASES. MOTOR OPERATEii"°VALVES***,MoV) THERMAr/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 3

02/25/2021

Title:

BATTERY MAINTENANCE AND MONITORING PROGRAM Page 13 of 15 Report Date: 04/01/21

SSES MANUAL Manual Name:

TRM2 1anual

Title:

TECHNICAL REQUIREMENTS MANUAL UNIT 2 TEXT B3.9.l 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.OPE~TIONS BASES REFUELING PLAT.FORM TEXT B3.10.l 0

11/19/2002

-*_. Ti tlei*:. M:tSCELt,ANEOUS BASES* SEALED SOURCE- *CONTAMINATION TEXT B3.10.2 1

04/10/2007

Title:

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Report Date: 04/01/21

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RADIOACTIVE EFFLUENTS BASES LAND USE CENSUS TEXT B3. 11. 4. 3 0

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10/04/2007

Title:

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12/03/2010

Title:

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ll/19/200i

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LOADS CONTROL PROGRAM BASES LIGHT LOADS REQUIREMENTS Page 15 of 15 Report Date: 04/01/21

Rev. 19 3.2 Core Operating Limits Report (COLR) 3.2.1 Core Operating Limits Report (COLR)

COLR 3.2.1 TRO 3.2.1 The Core Operating Limits specified in the attached COLR shall be met.

APPLICABILITY:

Specified in the referenced Technical Specifications.

ACTIONS CONDITION A.

Core Operating Limits not met.

REQUIRED ACTION A.1 Perform action(s) described in referenced Technical Specification.

TECHNICAL REQUIREMENT SURVEILLANCE SURVEILLANCE COMPLETION TIME Specified in referenced Technical Specifications.

FREQUENCY

---NOTE---------------------

N/A No associated Surveillances. Surveillances are implemented in the applicable Technical Specifications.

SUSQUEHANNA - UNIT 2 TRM / 3.2-1

Rev. 19 Susquehanna SES.

Unit 2 Cycle 21 PL-NF-21-003 Rev. O Page 1 of 103 CORE OPERA TING LIMITS

- REPORT SUSQUEHANNA UNIT 2 TRM / 3.2-2 Nuclear Fuels Engineering

. March 2021

REV AFFECTED NO.

SECTIONS 0

ALL FORM NFP-QA-008-2, Rev. 2 SUSQUEHANNA UNIT 2 Rev. 19 PL-NF-21-003 Rev. O Page 2 of 103 CORE OPERATING LIMITS REPORT REVISION DESCRIPTION INDEX DESCRIPTION / PURPOSE OF REVISION Issuance of this COLR is in support of Unit 2 Cycle 21 operation.

TRM / 3.2-3

1.0 2.0 3.0 4.0 5.0 6.0 7.0 Rev. 19 SUSQUEHANNA STEAM ELECTRIC STATION Unit 2 Cycle 21 CORE OPERA TING LIMITS REPORT Table of Contents PL-NF-21-003 Rev. O Page 3 of 103 INTRODUCTION........................................................................................................... 4 DEFINITIONS............................................................................................................... 5 SHUTDOWN MARGIN.................................................................................................. 6 AVERAGE PLANAR LINEAR HEAT GENERATION RATE (APLHGR)........................ 7 MINIMUM CRITICAL POWER RATIO (MCPR)............................................................ 10 LINEAR HEAT GENERATION RATE (LHGR).............................................................. 38 ROD BLOCK MONITOR (RBM) SETPOINTS AND OPERABILITY

REQUIREMENTS......................................................................................................... 67 8.0 RECIRCULATION LOOPS - SINGLE LOOP OPERATION.......................................... 69 9.0 POWER/ FLOW MAP................................................................................................... 99 10.0 OPRM SETPOINTS...................................................................................................... 101

11.0 REFERENCES

.............................................................................................................. 102 SUSQUEHANNA UNIT 2 TRM / 3.2-4

Rev. 19

1.0 INTRODUCTION

PL-NF-21-003 Rev. 0 Page4 of 103 This CORE OPERATING LIMITS REPORT for Susquehanna Unit 2 Cycle 21 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. 19 PL-NF-21-003 Rev. 0 Page 5 of 103 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 LHGRFACt multiplier protects against both fuel centerline melting and cladding strain during anticipated system transients initiated from core flows less than 108 Mlbm/hr.

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

2.6 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 MAPRAT 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.

SUSQUEHANNA UNIT 2 TRM / 3.2-6

Rev. 19 PL-NF-21-003 Rev. 0 Page 6 of 103 3.0 SHUTDOWN MARGIN 3.1 References 3.2 Technical Specification 3.1.1 Description The_ SHUTDOWN MARGIN shall be equal to or greater than:

a) 0.38% !lk/k with the highest worth rod analytically determined OR b) 0.28% Llk/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. 19 PL-NF-21-003 Rev. O Page 7 of 103 4.0 AVERAGE PLANAR LINEAR HEAT GENERATION RATE (APLHGR) 4.1 References 4.2 Technical Specification 3.2.1 Description The APLHGRs for ATRIUM'-10 fuel shall not exceed the limit shown in Figure 4.2-1A. The APLHGRs for ATRIUM' 11 fuel shall not exceed the limit shown in Figure 4.2-1 B.

The APLHGR limits in Figures 4.2-1A and 4.2-18 are valid in Two Loop operation for Main Turbine Bypass Operable and Inoperable, EOC-RPT Operable and inoperable, Backup Pressure Regulator Operable and Inoperable, and with one Turbine Stop Valve (TSV) or Turbine Control Valve (TCV) closed. The APLHGR limits for Single Loop operation are provided in Section 8.0.

SUSQUEHANNA UNIT 2 TRM / 3.2-8

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a)

Main Turbine Bypass / EOC-RPT / Backup Pressure Regulator Operable Figure 5.2-1A:

Flow-Dependent MCPR value determined from BOC to EOC for ATRIUM'-10 Fuel Figure 5.2-1B:

Flow-Dependent MCPR value determined from BOC to EOC for ATRIUM' 11 Fuel Figure 5.2-2A:

Power-Dependent MCPR value determined from BOC to EOC for ATRIUM'-10 Fuel Figure 5.2-2B:

Power-Dependent MCPR value determined from BOC to EOC for ATRIUM' 11 Fuel b)

Main Turbine Bypass Inoperable Figure 5.2-3A:

Flow-Dependent MCPR value determined from BOC to EOC for ATRIUM'-10 Fuel Figure 5.2-3B:

Flow-Dependent MCPR value determined from BOC to EOC for ATRIUM' 11 Fuel Figure 5.2-4A:

Power-Dependent MCPR value determined from BOC to EOC for ATRIUM'-10 Fuel Figure 5.2-4B:

Power-Dependent MCPR value determined from BOC to EOC for ATRIUM' 11 Fuel c)

EOC-RPT Inoperable Figure 5.2-5A:

Flow-Dependent MCPR value determined from BOC to EOC for ATRIUM'-10 Fuel Figure 5.2-5B:

Flow-Dependent MCPR value determined from BOC to EOC for ATRIUM' 11 Fuel SUSQUEHANNA UNIT 2 TRM / 3.2-11

Rev. 19 PL-NF-21-003 Rev. 0 Page 11 of 103 Figure 5.2-6A:

Power-Dependent MCPR value determined from BOC to EOC for ATRIUM'-10 Fuel Figure 5.2-68:

Power-Dependent MCPR value determined from BOC to EOC for ATRIUM' 11 Fuel d)

Backup Pressure Regulator Inoperable Figure 5.2-7A:

Flow-Dependent MCPR value determined from BOC to EOC for ATRIUM'-10 Fuel Figure 5.2-78:

Flow-Dependent MCPR value determined from BOC to EOC for ATRIUM' 11 Fuel Figure 5.2-8A:

Power Dependent MCPR value determined from BOC to EOC for ATRIUM'-10 Fuel Figure 5.2-88:

Power Dependent MCPR value determined from BOC to EOC for ATRIUM' 11 Fuel e)

One Turbine Stop Valve (TSV) or Turbine Control Valve (TCV) Closed Figure 5.2-9A:

Flow-Dependent MCPR value determined from BOC to EOC for ATRIUM'-10 Fuel Figure 5.2-98:

Flow-Dependent MCPR value determined from BOC to EOCforATRIUM' 11 Fuel Figure 5.2-10A: Power-Dependent MCPR value determined from BOC to EOC for ATRIUM'-10 Fuel Figure 5.2-108: Power-Dependent MCPR value determined from BOC to EOC for ATRIUM' 11 Fuel The MCPR limits in Figures 5.2-1A/5.2-1 B through 5.2-10A/5.2-108 are valid for Two Loop operation.

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. 19 PL-NF-21-003 Rev.a

Page 12 of 103 Main Turbine Bypass/ EOC-RPT /

Backup Pressure Regulator Operable SUSQUEHANNA UNIT 2 TRM / 3.2-13

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USED IN DETERMINING MFLCPR

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40, 2.141 I 26.01' 2.27 I "' ~

150, 2.101 c.o

~............ : so, 1.81:

A I 40, 1.90 I I 5o, 1.84 I I 80, 1.s1 I 160, 1.77 I

---.,..._____ *------........ J B

.., 1--------- 1:1 oo,,1.ss 1 1100, 1.441

REFERENCE:

T.S. 3.2.2 w

I I 80, 1.531 20 30 40

~

60 ro 80 90 Core Power(% RATED)

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

ATRIUM'-10 FUEL FIGURE 5.2-2A 100

CJ)

C CJ)

D C rn I )> z z

)>

C z

--l I\\.)

+-' *e

J 0,

C i...

--l C!)

a C.

0

~

0::

0.

c.v

(.)

N 2

I....,.

-.J SSES UNIT 2 CYCLE 21 40 I

I I

3.8 LEGEND CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME 3.6 CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME 3.4 CURVE C: CORE POWER ::;; 26% AND CORE FLOW ::;; 50 MLBM/HR 3.2 ALL SCRAM INSERTION TIMES 3.0 SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE 2.8 PER SR 3.7.6.1 AND 3.7.6.2 123, 2.651 2.6

... 126, 2.57*1 123, 2.57 c' I 2s, 2.46 I USED IN DETERMINING MFLCPR 2.4 2.2 2.0 1.8 1.6 1.4 1.2 I

26.01, 2.12 :

140, 1.91 50, 1.91,1

--r--,..___..........J ________ J..

i 26.01, 2.02 :

I I --....,.

j60, 1.751 A

80, 1.69:

140, 1.841 I 50, 1.84 I ~------L~--

lso, 1.141

---.L,..,_

B

~

REFERENCE:

T.S. 3.2.2 I I 80, 1.53 I 20 30 40 50 60 70 80 90 Core Power(% RATED)

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

ATRIUM' 11 FUEL FIGURE 5.2-2B

~

co

. I 100,:1.53 I 100, 1.41 I 100

Rev. 19 Main Turbine Bypass Inoperable SUSQUEHANNA UNIT 2 TRM / 3.2-18 PL-NF-21-003 Rev. 0 Page 17 of 103

(J) 2.5 C

(/)

0 C

2.4 m

I

)> z 2.3 z

)>

C 2.2 z

=i N

2.1 "i§ 2.0

i Cl i::

1.9 ell,_

Cl)

a Q.

0 1.8 s

a::

a.

w

(.)

i\\J

~ 1.7 I _,._

c.o 1.6 1.5 1.4 1.3 1.2 SSES UNIT 2 CYCLE 21 LEGEND J 30, 2.3s I CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME

~35,2.241 I

I

\\

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

\\

~13J

r----_ A B

r----_

i---.___ 110s, 1.41 I 30 I

REFERENCE:

T.S. 3.7.6 and 3.2.2 I 40 50

~

70

~

90 Total Core Flow (MLB/HR)

MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW MAIN TURBINE BYPASS INOPERABLE TWO LOOP OPERATION (BOC TO EOC)

ATRIUM'-10 FUEL FIGURE 5.2-3A 100 110

o

([)

c.o

(/)

2.5 C

(/)

D C

2.4 m

I )> z 2.3 z

)>

C 2.2 z

=i I\\J -

2.1

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i C'l C

1.9 cu...

--l Cl)

C.

a 0

1.8 s:

a:

a.

c,J

()

~

a 1.7 I

I\\J 0

1.6 1.5 1.4 1.3 1.2 SSES UNIT 2 CYCLE 21 LEGEND CURVE A: MPJ<IMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME 130, 2.231 I

I I

~

'\\. 13s,2.081 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

\\

I\\

\\. I 45, 1. 13 I

'------ ------r----_ A B

r---..,.__

r---,..___ 1108, 1.41 I 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 TWO LOOP OPERATION' (BOC TO EOC)

ATRIUM' 11 FUEL FIGURE 5.2-38 100 110 c.o

(J) 4.3 C

(J) 0 4.1 C m I

)>

3.9 z z

)>

3.7 C z

=i 3.5 N

3.3

.... *e 3.1

J Cl C: i 2.9 Cl)

0.

0 0

2.7

~

0:::

a.

(.,)

(.)

2.5 N

a I N 2.3 2.1 1.9 1.7 1.5 1.3 SSES UNIT 2 CYCLE 21 LEGEND CURVE A:

CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM 26, 3.32 INSERTION TIME 23, 3.47 I-CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME CURVE B:

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

-A 26, 3.23

~ '~

MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME 23, 3.38 B '\\... *\\,

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

'\\

REALISTIC AVERAGE SCRAM INSERTION TIME CURVE C:

I I

26, 3.01 D ~',,

SAFETY ANALYSES ASSUME THAT TWO OR MORE BYPASS VALVES ARE 23, 3.18 INOPERABLE PER SR 3.7.6.1 OR 3.7.6.2 CURVED:

26, 2.92 I 26.01, 2.58 H USED IN DETERMINING MFLCPR

~

23, 3.09

(!)

.....,..,_I 40, 2.27 I I SO 2_22 I

I 26.01, 2.30..........

I I 60, 2.00 I A

140, 1.931 80, 1.73 1 I 50, 1.85 I 160, 1.771 ------

8

~

]

REFERENCE:

T.S. 3.7.6 and 3.2.21 I 80, 1.55 I 1'100, 1.731 1100, 1.ss 1 10 20 30 40 50 60 70 Core Power (% RA TED)

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

ATRIUM'-10 FUEL FIGURE 5.2-4A 80 90 100

(/)

4.3 C

(/)

D 4.1 C m

r:

)>

3.9 z z

)>

C 3.7 z

--l 3.5 N

3.3

...,.E 3.1

J Cl C:

i 2.9

--j Cl)

o C. 2.7 0

0:::

ll.

w t) 2.5 j\\.:,

a=

I N

N 2.3 2.1 1.9 1.7 1.5 1.3 CURVE A:

26, 3:17 23, 3.41 CURVE 8:

26, 3.07 23, 3.31

~ CURVE C:

..... 26, 2.56

>- 23, 2.77

.,_CURVED:

26, 2.46

..... 23, 2.67 SSES UNIT 2 CYCLE 21 LEGEND CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME CURVE C: CORE POWER :s; 26% AND CORE FLOW :s; 50 MLBM/HR

-A MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME B _-,

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

\\.\\

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 C

\\

D \\ \\

USED IN DETERMINING MFLCPR

'\\

I 26.01, 2.26 I

... 40, 2.031 I 50, 2.03 l IS0,1.92L_

26.01, 2.os I A

80, 1.79:

~

o

,CD

...lo.

co

40, 1.89 50, 1.891

------- 1*100,,1.73, 11100, :1.531 ISO, 1.791 j

REFERENCE:

T.S. 3.7.6 and 3.2.2

,8 10 20 30 40 50 60 70 Core Power (% RA TED)

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

ATRIUM' 11 FUEL FIGURE 5.2-4B I 80, 1.55 I 80 90 100

~

7J co r

CD Z:

N "Tl I

0 ;o ~

CD I

...lo.< 0 o* o WOW

SUSQUEHANNA UNIT 2 Rev. 19 EOC-RPT Inoperable TRM / 3.2-23 PL-NF-21-003 Rev. 0 Page 22 of 103 - *

(J)

C

(/)

D C m I

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z z

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C z

=i N

'§

i Cl C i...

-I (I)

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0 0

s:

a::

a.

c.v

(.)

N

a I N

.r:,..

SSES UNIT 2 CYCLE 21 2.6 LEGEND 2.5 CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM.

2.4 30, 2.391 INSERTION TIME 2.3 2.2 2.1 2.0 1.9 1.8 1.7 1.6 I~

CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME

\\135,2.241

\\

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

\\

USED IN DETERMINING MFLCPR L

I

\\

, I 4o, 1.611 1.5 A

B 1.4 I

REFERENCE:

T.S. 3.3.4.1 and 3.2.2 I 1.3 1.2 30 40 50 60 70 80 90 Total Core Flow (MLB/HR)

MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW EOC-RPT INOPERABLE TWO LOOP OPERATION (BOC TO EOC)

'.ATRIUM'-10 FUEL*

FIGURE 5.2-SA 100

--1108, 1.251 I

110

~

lJ ca r

CD I

N z

C,,J 71 0 ;;o~

CD I

...>.< 0 o* o vJ OW

(I) 2.6 C

(I)

D C

2.5 m

I )>

2.4 z z

)>

C 2.3 z

N 2.2

.... *e 2.1

i C) 2.0 C: i...

1.9 Cl)

C.

o 0

s:

~

a.

1.8 c,..:,

(.)

N

~

I N 1.7 CJ1 1.6 1.5 1.4 1.3 1.2 SSES UNIT 2 CYCLE 21*

L!.EGEND CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME CURVE 8: REALISTIC AVERAGE SCRAM INSERTION TIME I ~o. 2.231

~

"'-, 35, 2.08 I SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES I

ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2

\\

USED IN DETERMINING MFLCPR

\\

\\ *\\

' 140, 1.s1 I A*

B f

~

REFERENCE:

T.S. 3.3.4.1 and 3.2.2 :

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

MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW EOC-RPT INOPERABLE TWO LOOP OPERATION (BOC TO EOC)

ATRIUM' 11 FUEL FIGURE 5.2-58 100

--L I

CD I 108, 1.25 I I

110

(J)

C (J) 0 C m I

)>

z z

)>

C z

--l N

--l

0 s:: -

u.)

N I N

0)

'§

J C)

C re...

QJ c..

0 a::

0.

(.)

a 4.3 4.1 3.9 3.7 3.5 3.3 3.1 2.9 2.7 2.5 2.3 2.1 1.9 1.7 SSES UNIT 2 CYCLE 21 1------+-----+---~LEGEND 1------1------1-----1CURVE A: M~IMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME i

CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME

+---------

CURVE C: CORE POWER :s; 26% AND CORE FLOW :s; 50 MLBM/HR CURVE C: 1-1------+-----1 MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME 26, 3.04 23, 3.15 t-+--------t-------1CURVE D: CORE POWER :s; 26% AND CORE FLOW :s; 50 MLBM/HR REALISTIC AVERAGE SCRAM INSERTION TIME SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE -

CURVED:

PER SR 3.7.6.1 AND 3.7.6.2 26, 2.92 23, 3.03 F====:=:....1--_,.µ.' 2;;=6=.0F1=, 2=*=61:::::!.H-L~---~'-----=U=S=E=D:.IN'..:...:D.:ET__:_:E:R_:M:.:_:l:N~IN:_:G~M=F~L=C~P.:..:R:_ __ ~

__ _Jt 1-------+-----+--+--...;:-... ~~... -1, 40, 2.2911---.=.+/-===.:::--+------+-----+----tf----------l

50, 2.22 :1-----1-----+----t----+-----1 26.01, 2.21 IH!'o....f---31...,...._--+-----+---... _... _... ~il:-l6

...... o.:.., 2_._05....,I_

-,1-.__

A

a CD co

-...... ;------1--~lr--+------;

80, 1.82 1100, 1.79 I 40, 1.90 l I 50, 1.841 I 60, 1. 771 1-------+------+-------+----+-----,-...._ __ Bl---"=--._ ____

~-+----+------1.-------.

1.s 1r-__

_J_ __

___J ___

_J_i--

1

---+-------1-----=+-----=;:::i:=::::;==:t=====1 I 100, :1.s31

REFERENCE:

T.S. 3.3.4.1 and 3.2.2 I 80, 1.531 1.3 10 20 30 40 50 60 70 Core Power (% RA TED)

MCPR OPERATING LIMIT VERSUS CORE POWER EOC-RPT INOPERABLE TWO LOOP OPERATION (BOC TO EOC)

ATRIUM'-10 FUEL FIGURE 5.2-6A 80 90 100

(J) 4.3 C

(J)

D 4.1 C m I )>

3.9 z z

)>

C 3.7 z

-I 3.5 3.3

"§ 3.1

i Cl C:

2.9 Ill...

-I Cl)

u

0. 2.7 0

s:

a::

a.

c.,J t) 2.5

~

I "'

-..J 2.3 2.1 1.9 1.7 1.5 1.3 SSES UNIT 2 CYCLE 21 I

I LEGEND I-

_ CURVE A:

CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME I-

_ 26, 2.77 I-23, 2.85 CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME I-I-

I-

,.. CURVE C:

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

,.. 26, 2.66 M.tl.XIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME 23, 2.77 CURVE D: CORE POWER ~ 26% AND CORE FLOW~ 50 MLBM/HR REALISTIC AVERAGE SCRAM INSERTION TIME

- CURVE B:

I-

- 26, 2.57 A

- 23, 2.65 SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE

""~

PER SR 3.7.6.1 AND 3.7.6.2

~c *,. '1 B....._ -a

_CURVED:

I t

_ 26, 2.46

,..o,"'

USED IN DETERMINING MFLCPR 23, 2.57 26.01, 2.35 I co I 40, 2.12 50, 2.12 60, 2.11 A

180, 2.11 1 I 26.01' 2.04

1100, 1.93 I 40, 1.81 n 50, 1.811

--- i-....

I I 60, 1.77 I

REFERENCE:

T.S. 3.3.4.1 and 3.2.21 B

1100, !1.so 1 10 20 30 I

40 50 60 70 Core Power(% RATED)

MCPR OPERATING LIMIT VERSUS CORE POWER EOC-RPT INOPERABLE TWO LOOP OPERATION (BOC TO EOC) iATRIUM' 11 FUEL FIGURE 5.2-68 I 80, 1.541 80 90 100

Rev. 19 PL-NF-21-003 Rev. 0 Page 27 of 103 Backup Pressure Regulator Inoperable SUSQUEHANNA UNIT 2 TRM / 3.2-28

(/)

2.6 C

(/)

0 C

2.5 m

I )>

2.4 z z

)>

C 2.3 z

-I N

2.2 2.1

e

J C) 2.0 C:

~ 1.9

-I Q)

C.

0 0

s:

0::

a.

1.8

(,.)

(.)

~

a:

I "'

1.7 co 1.6 1.5 1.4 1.3 1.2 SSES UNIT 2 CYCLE 21 I

I I

I LEGEND CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM J 30, 2.391 INSERTION TIME

~

CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME

\\135,2.241 I

I I

I

\\

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

\\

I I

\\

\\ ' I 40, 1.51 I A

B j

REFERENCE:

T.S. 3.7.8 and 3.2.2:

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

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

ATRIUM'-10 FUEL FIGURE 5.2-7 A 108, 1.251 I

100 110

0 CD co

I I

I en C

CJ) 0 C

m I )> z z

)>

C z

=i N

..... E

i Cl C:

+:l cu..

Cl)

C.

0 a:

C.

{.)

2:

2.6 2.5 2.4 2.3 2.2 2.1 2.0 1.9 1.8 1.7 1.6 1.5 1.4 1.3 1.2 SSES UNIT 2 CYCLE 21 I

I LEGEND CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME CURVE 8: REALISTIC AVERAGE SCRAM INSERTION TIME 130, 2.23 I I

I T

\\,.

'\\.~ 35,2.os:

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 40, 1.51 I

~

A B

~

REFERENCE:

T.S. 3.7.8 and 3.2.2:

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

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

'ATRIUM' 11 FUEL FIGURE 5.2-78 100 J

108, 1.25 I I

110

0 CD co

Cl) 4.0 C

Cl) 0 C

3.8 m

I )>

3.6 z z

)>

C 3.4 z

-I 3.2 3.0

e

J Cl 2.8 C:

ns...

2.6

-I Cl)

C.

0 0

~

0::

D.

2.4 vJ 0

N a

I

(.,.)

2.2 2.0 1.8 1.6 1.4 1.2 SSES UNIT 2 CYCLE 21 I

I I

LEGEND CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME CURVE C: CORE POWER ~ 26% AND CORE FLOW~ 50 MLBM/HR

~ 23, 3.03:

ALL SCRAM INSERTION TIMES

._C~H26, 2.92 1 SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE PER SR 3.7.6.1 AND 3.7.5.2 I

I I

I 26.01, 2.491 USED IN DETERMINING MFLCPR

~

26.01, 2.471 ~

.... -"' 140,2.201

~:..._1 r-=:.:::..-_ _ I 50, 2.10 l4o, 2.1s I -.............. -....

I 60, 1.90 I I 50, 1.99 I

""""c:::..--

A

-1 I 60, 1.90 I

............ ----......... __ 80, 1.681 B

H

REFERENCE:

T.S. 3.7.8 and 3.2.2:

I 80, 1.541 20 30 40 50 60 70 80 Core Power(% RATED)

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

ATRIUM'-10 FUEL FIGURE 5.2-BA I

90 t

0 CD cc 1.100, :1.551 lr100, :1.44 I 100

~

"U cc r

CD z

~

71 0 ;a~

CD I

....>.< 0 o* o vJ OvJ

(f)

C (f) 0 C m I )>

z z

)>

C z

-I

..... E

J Cl C: i...

-I Cl)

Q.

0 0

~

0:::

a.

w

(.)

i-v

a:

I w "'

SSES UNIT 2 CYCLE 21 40 I

3.8 LEGEND CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM 3.6 INSERTION TIME 3.4 CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME CURVE C: c'ORE POWER s 26% AND CORE FLOW s 50 MLBM/HR 3.2 ALL SCRAM INSERTION TIMES 3.0 SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES -

2.8 ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 I 23, 2.6s:

I I

2.6

.., I 26, 2.57 :

USED IN DETERMINING MFLCPR t

I 23, 2.57 I "-.....

I 2_4 _

C I 26, 2.46 I 2.2 26.01, 2.25 I r--....._

140, 2.00 2.0

~--,

I so, 1.92 c.o 140, 1.98 I I

~160, 1.791 A

1.8

,so, 1.921.

~----

I 80, 1.69 I I 60, 1.78 I 1.6 i

REFERENCE:

T.S. 3.7.8 and 3.2.21 B

------. 1100, ;1.s3I 1100,1.411 1.4

1. 2 20 30 40 I 80, 1.53 I

~

60 ro Core Power(% RATED)

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

ATRIUM' 11 FUEL FIGURE 5.2-88 80 90 100 r

Rev. 19 One TSV or TCV Closed SUSQUEHANNA UNIT 2 TRM / 3.2-33 PL-NF-21-003 Rev. 0 Page 32 of 103

2.6

(/)

C 2.5 Cl) 0 C m 2.4 I )> z z 2.3

)>

C z 2.2 I\\.)

2.1

.... *e 2.0

J C)

C:

1.9 ca...

C1l Q.

a 0

1.8 s::

c:::

a.

w

(.)

1.7 j\\.,

lE I w

.t,.

1.6 1.5 1.4 1.3 1.2 SSES *uN.2 CYCLE 21 LEGEND CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM I 30, 2.39 I INSERTION TIME CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES 140, 2.09 1 ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2

\\

USED IN DETERMINING MFLCPR I

\\

I

\\

145, 1.10 I r---...._

A B

co r----....

- - i----_ I108, 1.431 H

REFERENCE:

T.S. 3.2.2 and TRM 3.3.71 30 40 50 60 70 80 90 Total Core Flow (MLB/HR)

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

TWO LOOP OPERATION (BOC TO EOC)

ATRIUM'-10 FUEL FIGURE 5.2-9A 100

Operation with one TSV or TCV closed is only supported at power levels S 75% rated power 110

~

"'O cc r;--

(D z

w "Tl W

I 0 ::a~

CD I

..,. < 0 o* o wow

2.6 (J)

C 2.5 (J)

D C m 2.4 I )> z z 2.3

)>

C z 2.2

-l N

2.1

'§ 2.0

i C)

C 1.9 Cll...

0)

-l c..

a 0

1.8 s::

et::

o.

(.,,)

u 1.7 i--,

a I

(.,,)

c.n 1.6 1.5 1.4 1.3 1.2 SSES uNlt2 CYCLE 21 LEGEND CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME 130, 2.231 CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME

~

I I

I SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES

~

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

TWO LOOP OPERATION (BOC TO EOC)

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Operation with one TSV or TCV closed is only supported at power levels S 75% rated power 110 co

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

ATRIUM' 11 FUEL FIGURE 5.2-1 OB 70 80 co

Rev. 19 Table 5.3-1 PL-NF-21-003 Rev. O Page 37 of 103 -

A verage Scram Time Fraction Table For Use With Scram Time Dependent C ontrol Rod Position 45 0.470 39 0.630 25 1.500 5

2.700 Av erage Scram Realistic sertion Time In SU SQUEHANNA UNIT 2 MCPR Operating Limits Average Scram Time to Position (seconds)

TRM / 3.2-38 0.520 0.860 1.910 3.440 Maximum Allowable

Rev. 19 PL-NF-21-003 Rev. 0 Page 38 of 103

s.o LINEAR HEAT GENERATION RATE (LHGR) 6.1 References 6.2 Technical Specification 3.2.3, 3.3.4.1, 3.7.6, and 3.7.8 Technical Requirements Manual 3.3.7 Description The maximum LHGR for ATRIUM'-10 and ATRIUM' 11 fuel shall not exceed

. the LHGR limits determined from Figure 6.2-1A and Figure 6.2-1 B, respectively.

The LHGR limits in Figures 6.2-1A and 6.2-1B are valid for Main Turbine Bypass Operable and Inoperable, EOC-RPT Operable and Inoperable, Backup Pressure Regulator Operable and Inoperable, and with one Turbine Stop Valve (TSV) or Turbine Control Valve (TCV) closed.

To protect against both fuel centerline melting and cladding strain during anticipated system transients initiated from reduced power and flow conditions, power and flow dependent LHGR limit multipliers are provided in the following figures:

a)

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Flow-Dependent LHGR Limit Multiplier for ATRI UM'-10 Fuel Figure 6.2-2B:

Flow-Dependent LHGR Limit Multiplier for ATRIUM' 11 Fuel Figure 6.2-3A:

Power-Dependent LHGR Limit Multiplier for ATRIUM'-10 Fuel Figure 6.2-3B:

Power-Dependent LHGR Limit Multiplier for ATRIUM' 11 Fuel b)

Main Turbine Bypass Inoperable Figure 6.2-4A:

Flow-Dependent LHGR Limit Multiplier for ATRIUM'-10 Fuel Figure 6.2-4B:

Flow-Dependent LHGR Limit Multiplier for ATRIUM' 11 Fuel Figure 6.2-5A:

Power-Dependent LHGR Limit Multiplier for ATRIUM'-10 Fuel Figure 6.2-5B:

Power-Dependent LHGR Limit Multiplier for ATRIUM' 11 Fuel SUSQUEHANNA UNIT 2 TRM / 3.2-39

Rev. 19 c)

EOC-RPT lrfoperable PL-NF-21-003 Rev.a Page 39 of 103 Figure 6.2-6A:

Flow-Dependent LHGR Limit Multiplier for ATRIUM'-10 Fuel Figure 6.2-6B:

Flow-Dependent LHGR Limit Multiplier for ATRIUM' 11 Fuel Figure 6.2-7A:

Power-Dependent LHGR Limit Multiplier for ATRIUM'-10 Fuel Figure 6.2-7B:

Power-Dependent LHGR Limit Multiplier for ATRIUM' 11 Fuel d)

Backup Pressure Regulator Inoperable Figure 6.2-SA:

Flow-Dependent LHGR Limit Multiplier for ATRIUM'-10 Fuel Figure 6.2-8B:

Flow-Dependent LHGR Limit Multiplier for ATRIUM' 11 Fuel Figure 6.2-9A:

Power-Dependent LHGR Limit Multiplier for ATRIUM'-10 Fuel Figure 6.2-9B:

Power-Dependent LHGR Limit Multiplier for ATRIUM' 11 Fuel e)

One Turbine Stop Valve (TSV) or Turbine Control Valve (TCV) Closed Figure 6.2-10A: Flow-Dependent LHGR Limit Multiplier for ATRIUM'-10 Fuel Figure 6.2-10B: Flow-Dependent LHGR Limit Multiplier for ATRIUM' 11 Fuel Figure 6.2-11A: Power-Dependent LHGR Limit Multiplier for ATRIUM'-10 Fuel Figure 6.2-11 B: Power-Dependent LHGR Limit Multiplier for ATRIUM' 11 Fuel The LHGR limits and LHGR limit multipliers in Figures 6.2-1A/6.2-1 B through 6.2-11A/6.2-11 Bare valid for both Two Loop and Single Loop operation.

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- Page 67 of 103 7.0 ROD BLOCK MONITOR (RBM) SETPOINTS AND OPERABILITY REQUIREMENTS 7.1 References 7.2 Technical Specification 3.3.2.1 Description The RBM Allowable Value and Trip Setpoints for; a)

Low Power Range Setpoint, b)

Intermediate Power Range Setpoint, c)

High Power Range Setpoint, d)

Low Power Range - Upscale, e)

Intermediate Power Range - Upscale, and f)

High Power Range - Upscale shall be established as specified in Table 7.2-1. The RBM setpoints are valid for Two Loop and Single Loop Operation, Main Turbine Bypass Operable and Inoperable, EOC-RPT Operable and Inoperable, Backup Pressure Regulator Operable and Inoperable, and with one Turbine Stop Valve (TSV) or Turbine Control Valve (TCV) closed.

The RBM system design objective is to block erroneous control rod withdrawal initiated by the operator before fuel design limits are violated. If the full wffhdrawal of any *control rod wouid riot vioiate a fuel des1gri limit, then the RBM system is not required to be operable. Table 7.2-2 provides RBM system operability requirements to ensure that fuel design limits are not violated.

SUSQUEHANNA UNIT 2 TRM / 3.2-68

Function Low Power Range Setpoint Rev. 19 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 ValueC1l 28.0 63.0 83.0 123.4 117.4 107.6 PL-NF-21-003 Rev. 0 Page 68 of 1 03 Nominal Trip Setpoint 24.9 61.0 81.0 123.0 117.0 107.2 (1)

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

(2)

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Applicable to both Two Loop and Single Loop Operation.

C4l Applicable to both ATRIUM-10 and ATRIUM 11 Fuel.

SUSQUEHANNA UNIT 2 TRM / 3.2-69

Rev. 19 PL-NF-21-003 Rev.a Page 69 of 103

8.0 RECIRCULATION LOOPS A SINGLE LOOP OPERATION 8.1 References 8.2 Technical Specification 3.2.1, 3.2.2, 3.3.4.1, 3.4.1, 3.7.6, and 3.7.8 Technical Requirements Manual 3.3.7 Description APLHGR The APLHGR limit for ATRIUM'-10 fuel shall be equal to the APLHGR Limit from Figure 8.2-1A. The APLHGR limit for ATRIUM' 11 fuel shall be equal to the APLHGR Limit from Figure 8.2-1 B.

The APLHGR limits in Figures 8.2-1A and 8.2-1 Bare valid in Single Loop operation for Main Turbine Bypass Operable and Inoperable, EOC-RPT Operable and Inoperable, Backup Pressure Regulator Operable and Inoperable, and with one Turbine Stop Valve (TSV) or Turbine Control Valve (TCV) closed.

Minimum Critical Power Ratio Limit The MCPR limit is specified as a function of core power, core flow, and plant equipment operability status. The MCPR limits for all fuel types (ATRIUM'-10 and ATRI UMTM 11) shall be the greater of the Flow-Dependent or the Power-Dependent MCPR, depending on the applicable equipment operability status.

a)

Main Turbine Bypass / EOC-RPT / Backup Pressure Regulator Operable Figure 8.2-2A:

Flow-Dependent MCPR value determined from BOC to EOG for ATRIUM'-10 Fuel Figure 8.2-2B:

Flow-Dependent MCPR value determined from BOC to EOG for ATRIUM' 11 Fuel Figure 8.2-3A:

Power-Dependent MCPR value determined from BOC to EOG for ATRIUM'-10 Fuel Figure 8.2-3B:

Power-Dependent MCPR value determined from BOC to EOG for ATRIUM' 11 Fuel b)

Main Turbine Bypass Inoperable Figure 8.2-4A:

Flow-Dependent MCPR value determined from BOC to EOG for ATRIUM'-10 Fuel Figure 8.2-4B:

Flow-Dependent MCPR value determined from BOC to EOG for ATRIUM' 11 Fuel SUSQUEHANNA UNIT 2 TRM / 3.2-70

Rev. 19 PL-NF-21-003 Rev. 0 Page 70 of 103 Figure 8.2-5A:

Power-Dependent MCPR *value determined from BOC to EOC for ATRIUM'-10 Fuel Figure 8.2-58:

Power-Dependent MCPR value determined from BOC to EOC for ATRIUM' 11 Fuel c)

EOC.:.RPT Inoperable Figure 8.2-6A:

Flow-Dependent MCPR value determined from BOC to EOC for ATRIUM'-10 Fuel Figure 8.2-68:

Flow-Dependent MCPR value determined from BOG to EOC for ATRIUM' 11 Fuel Figure 8.2-7 A:

Power-Dependent MCPR value determined from BOC to EOC for ATRIUM'-10 Fuel Figure 8.2-78:

Power-Dependent MCPR value determined from BOC to EOC for ATRIUM' 11 Fuel ct)

Backup Pressure Regulator Inoperable Figure 8.2-8A:

Flow-Dependent MCPR value determined from BOC to EOC for ATRIUM'-10 Fuel Figure 8.2-88:

Flow-Dependent MCPR value determined from BOC to EOC for ATRIUM' 11 Fuel Figure 8.2-9A:

Power-Dependent MCPR value determined from BOC to EOC for ATRIUM'-10 Fuel Figure 8.2-98:

Power-Dependent MCPR value determined from BOC to EOC for ATRIUM' 11 Fuel e)

One Turbine Stop Valve (TSV) or Turbine Control Valve (TCV) Closed Figure 8.2-10A: Flow-Dependent MCPR value determined from BOC to EOC for ATRIUM'-10 Fuel Figure 8.2-108: Flow-Dependent MCPR value determined from BOC to EOC for ATRIUM' 11 Fuel Figure 8.2-11A: Power-Dependent MCPR value determined from BOC to EOC for ATRIUM'-10 Fuel Figure 8.2-11 B: Power-Dependent MCPR value determined from BOC to EOC for ATRIUM' 11 Fuel The MCPR limits in Figures 8.2-2A/8.2-2B through 8.2-11A/8.2-11 Bare valid only for Single Loop operation and support power levels up to 67.2% RATED THERMAL POWER and core flows up to 52 Mlbm/hr. These conditions SUSQUEHANNA UNIT 2 TRM / 3.2-71

Rev. 19 PL-NF-21-003 Rev. O Page 71 of 103 conservatively bound Single Loop Operation in accordance with Technical Specification 3.4.1.

Linear Heat Generation Rate Limit The LHGR limits for Single Loop Operation are defined in Section 6.0.

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

SUSQUEHANNA UNIT 2 TRM / 3.2-72

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-..J 1.6 1.4 1.2 1.0 SSES_UNIT 2 CYCLE_,21 LEGEND CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME 130, 2.231

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

~

I3s, 2.08 I

\\

I USED IN DETERMINING MFLCPR I

\\

I I

\\

A B

I 40, 1.51 I I 52, 1.461

REFERENCE:

T.S. 3.4.1 and 3.2.21 30 35 40 45 50 55 60 65 Total Core Flow (MLB/HR)

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

. ATRIUM' 11 FUEL FIGURE 8.2-2B 70

o CD CD

Cl) 4.0 C

(/)

0 C

3.8 m

I )> z 3.6 z

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C 3.4 z

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3.2

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a 0

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a::

a.

c,J

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-.J 00 2.2 2.0 1.8 1.6 1.4 SSES UNIT 2 CYCLE 21 I

LEGEND CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME CURVE C: CORE POWER~ 26% AND CORE FLOW ~ 50 MLBM/HR ALL SCRAM INSERTION TIMES

_j23, 3.06 I I

I SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES

,.. ""' I 26, 2.95 I ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 USED* IN DETERMINING MFLCPR

26.01, 2.52 :

140, 2.171

~

.A I 50, 2.131 H 26.01, 2.30 1

60, 1.90: :

I 40, 1.93 I C

I 50, 1.87 I

.

.:: 1 67.2, 1.81 I

, 160, 1.801 I 67.2, 1.721

~

REFERENCE:

T.S. 3.4.1 and 3.2.2 I

20 30 40 50 60 Core Power(% RATED) :.

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

ATRIUM'-10 FUEL FIGURE 8.2-3A 80 c.o

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SSES UNIT 2 CYCLE 21 LEGEND i--------+---------iCURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME i--------+---------iCURVE C: CORE POWER~ 26% AND CORE FLOW~ 50 MLBM/HR ALL SCRAM INSERTION TIMES 123, 2.68 I I

I I

SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 USED IN DETERMINING MFLCPR g 26

............_ 126,2.601 8:

, 23, 2.60 ~

i 26, 2.49 11----------+---------+--------+--------+---------1 LJ I

~ 2.4 2.2 126.01, 2.15L A I 67.2, 2.06 I 2.0 1126.01, 2.06 I B

140, 2.061 1.8 1.6 I

REFERENCE:

T.S. 3.4.1 and 3.2.21 1.4..__ _____

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

MCPR OPERATING LIMIT VERSUS CORE POWER MAIN TURBINE BYPASS/ EOC-RPT / BACKUP PRESSURE REGULATOR OPERABLE SINGLE LO,OP OPERATION (BOC TO EOC)

ATRIUM' 11 FUEL FIGURE 8.2-3B 80 co

Rev. 19 PL-NF-21-003 Rev. 0 Page 79 of 1 03 Main Turbine Bypass Inoperable SUSQUEHANNA UNIT 2 TRM / 3.2-80

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a I 00 1.6 1.4 1.2 1.0 SSES UNIT 2 CYCLE:21 LEGEND i

CURVE _A: MAXIMUM A(LOWABLE.AVERAGE SCRAM I

INSERTION TIME a*

CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME 130, 2.391

~

I

.I I

SAFETY ANALYSES ASSUME THAT TWO OR MORE BYPASS 135, 2.241 r,,,.,_

VALVES ARE INOPERABLE PER SR 3.7.6.1 OR 3.7.6.2

~

I I

USED IN DETERMINING MFLCPR

~

A B

I 45, 1.73 I 52, 1.69 I I

REFERENCE:

T.S. 3.4.1, 3.7.6, and 3.2.2 I 30 35 40 45 50 55 60 Total Core Flow (MLB/HR)

MCPR OPERA TING LIMIT VERSUS TOT AL CORE FLOW

MAIN TURBINE BYPASS INOPERABLE SINGLE LOOP OPERATION (BOC TO EOC)

ATRIUM'-10 FUEL FIGURE 8.2-4A 65 70

a CD C.D

-0 Q)

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1.6 1.4 1.2 1.0 SSES UNIT 2 CYCLE 21 LEGEND CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM I

INSERTION TIME l

CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME I

J I

I 130, 2.231

SAFETY ANALYSES ASSUME THAT TWO OR MORE BYPASS VALVES ARE INOPERABLE PER SR 3.7.6.1 OR 3.7.6.2 30

~

13s, 2.osl I~

I l:J~ED IN DETERMINING MFLCPR

~

A B

J45, 1.73 J J 52, 1.s~ I I

REFERENCE:

T.S. 3.4.1, 3.7.6, and 3.2.2 I 35 40

~

-~

Total Core Flow (MLB/HR) : :

MCPR OPERATING LIMIT VERSUS TOTAL/CORE FLOW

MAIN TURBINE BYPASS INOPERABLE SINGLE LOOP OPERATION (BOC TO EOC)

ATRIUM' 11 FUEL FIGURE 8.2-48 65 co 70

(J) 4.4 C

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4.0 z z

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(,J 2.4 2.2 2.0 1.8 1.6 1.4 SSES UNIT 2 CYCLE,21 I

LEGEND CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM CURVE A:

INSERTION TIME 26, 3.35 23, 3.50 CURVE B: REALISTIC AVERAGf: SCRAM INSERTION TIME CURVE C: CORE POWER s; 26%.AND CORE FLOW s; 50 MLBM/HR CURVE B:

A MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME 26, 3.26 --

~,

-8 23, 3.41 -

CURVE D: CORE POWER s; 26°/o;AND CORE FLOW s; 50 MLBM/HR REALISTIC AVERAGJ= SCRAM INSERTION TIME C

I I

CURVE C:

D, ',

26, 3.04 SAFETY ANALYSES.ASSUME THAT TWO OR MORE BYPASS 23, 3.21 VALVES ARE INOPERABLE PER SR 3.7.6.1 OR 3.7.6.2 CURVED:

1 26.01, 2.61 I USED IN DETERMINING MFLCPR 26, 2.95 23, 3.12 l40 2.301 I 5o, 2.25 r I...........

A 26.01, 2.33 I I 60, 2.031

I 67.2, 1.94 I I 40, 1.96 I i 50, 1.88 a

~

REFERENCE:

T.S. 3.4.1, 3.7.6, and 3.2.2:

60, 1.80 I -- ;61.2, 1.12:

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

MCPR OPERA TING LIMIT VERSUS CORE POWER MAIN TURBINE BYPASS INOPERABLE SINGLE LOOP OPERATION (BOC ro EOC) 1ATRIUM'-10 FUEL FIGURE 8.2-5A 70

~

80 co

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4.4 4.2 4.0 3.8 3.6 3.4 3.2 3.0 2.8 2.6 2.4 2.2 2.0 1.8 SSES UNIT 2 CYCLE_21 I

I I

I LEGEND 1-----------------;

CURVE~: MAXIMUM ALLOWASLE AVERAGE SCRAM

'====---+-----+----1,

INSERTION TIME CURVE A:

26, 3.20 23, 3.44 1----+------+----+CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME 1------------+-----1CURVE C: CORE POWER :s; 26% AND CORE FLOW :s; 50 MLBM/HR

=-:::-,..---l-A----+-----1 CURVE B:

MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME 26, 3.10 23, 3.34 CURVE C:

26, 2.59 23, 2.80 CURVED:

26, 2.49 23, 2.70 CURVED: CORE POWER :s; 26%_ AND CORE FLOW :s; 50 MLBM/HR REALISTIC AVERAGE SCRAM INSERTION TIME i----- C ---+----l------+I 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 I

I 26.01, 2.29 I A

1------------------F'--._,.=--

--+-----.+--.:..:' *---+--------1.--,..-------1 I 67.2, 2.06 I

26.01, 2.11 ~- B 140, 2.061 1.6 H

REFERENCE:

T.S. 3.4.1, 3. 7.6, and 3.2.2 11---1---------1--_,*_* -----<~------1-------1 1.4 L_ ____

_j_ _____

.i...__ ____

...J..._ ____

10 20 30 40 so*

60 Core Power(% RATED)

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

ATRIUM' 11 FUEL FIGURE 8.2-5B 70 80 (0

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SSES UNIT 2 CYCLE 21 3.0 LEGEND 2.8 CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME 2.6 CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME 2.4 2.2 2.0 1.8 1.6 130, 2.39 I

~

1 I

I 135, 2.241 j SAFETY ANALYSES AS:SUME THAT FOUR BYPASS VALVES ARE OPERABlE PER SR 3.7.6.1 AND 3.7.6.2

\\

I USED IN DETERMINING MFLCPR

\\

A B

1.4 I 40, 1.51 I 152, 1-461 1.2

REFERENCE:

T.S. 3.4.1, 3.3.4.1, and 3.2.2 I 1.0 30 35 40 45 50 55 60 Total Core Flow (MLB/HR) :

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

~TRIUM'-10 FUEL FIGURE 8.2-6A 65 i---

70 co "U

"U tl.l r

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--..J 1.6 1.4 1.2 1.0 SSES UNIT 2 CYCLE '*21 LEGEND i

CURVE A: MAXIMUM A~LOWABLE AVERAGE SCRAM INSERTION TIME

_CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME

. \\,

,1*

I

SAFETY ANALYSES A$pUME THAT FOUR BYPASS VALVES 130, 2.231 i,..._

ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2

~

135, 2.081

~

I USED IN DETERMINING MFLCPR

\\

A B

I 40, 1.51 I I 52, 1.4t> I

REFERENCE:

T.S. 3.4.1, 3.3.4.1, and 3.2.2 I 30 35

~

Total Core Flow (MLB/HR)..

MCPR OPERATING LIMIT VERSUS TOTAi;.; CORE FLOW EOC-RPT INOPERABLE SINGLE LOOP OPERATION (BOC T'O EOC)

ATRIUM' 11 FUEL FIGURE 8.2-68 65 co 70

CJ) 4.4 C

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0 4.2 C m I )>

4.0 z z

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CXl CXl 2.4 2.2 2.0 1.8 1.6 1.4 SSES IUNIT 2 CYCLE.*21 LEGEND CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME CURVE B: REALISTIC AVERAGE.SCRAM INSERTION TIME CURVE C: CORE POWER::;; 26% AND CORE FLOW::;; 50 MLBM/HR MAXIMUM ALLOWASLE AVERAGE SCRAM INSERTION TIME

_ CURVE C:

CURVE D: CORE POWER::;; 26%,AND CORE FLOW::;; 50 MLBM/HR 26, 3.07

- 23, 3.18 REALISTIC AVERAGE SCRAM INSERTION TIME C...,_

D...........

SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES I

- CURVED:,-

ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2

'""26, 2.95

.- 23, 3.06 I

I I

I 26.01, 2.64 I

USEO IN DETERMINl,NG MFLCPR I

......... _ 140, 2.321

,so, 2.251, A

I._,

26.01, 2.30 1

--:---...... _ 60, 2.08 I

67.2, 2.00 :

140, 11.93 I j 50, 1.87 8

167.2, 1.721 I

60, 1.801 I

REFERENCE:

T.S. 3.4.1, 3.3.4.1, and 3.2.2 I 10 20 30 40

50 60 Core Power (% RA TED).

MCPR OPERATING LIMIT VERSUS CORE POWER EOC-RPT INOPERABLE*;*

SINGLE LOOP OPERATION (BOC :to EOC)

ATRIUM'-10 FUEL FIGURE 8.2-7 A 70

~

c.c 80

(/)

4.4 C

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0 4.2 C m I )>

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a I

00 co 2.4 2.2 2.0 1.8 1.6 1.4 SSES UNIT 2 CYCLE.21

, I I

I I

LEGEND' CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME CURVE A:

CURVE 8: REALISTIC AVERAGE SCRAM INSERTION TIME 26, 2.80 23, 2.88 CURVE C: CORE POWER ::; 26% AND CORE FLOW ::; 50 MLBM/HR

MAXIMUM ALLOWABLi: AVERAGE SCRAM INSERTION TIME CURVE C:

26, 2.69 CURVE D: CORE POWER ::; 26% AND CORE FLOW ::; 50 MLBM/HR 23, 2.80 REALISTIC AVERAGE SCRAM INS_ERTION TIME CURVE B:

26, 2.60 A

SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 23, 2.68

-C......

B.:::::.:

I USEq {N DETERMINi°NG MFLCPR CURVED:

I D""---

26, 2.49 23, 2.60 126.01, 2.381 140, 2.151 150,2.151,. A J60,2.14I *

1--------- ---~----- --*.----- 167.2, 2.141 I

26.01, 2.071 140, 2.061 I so, 2.06 [.

B 160, 2.06 I.

I 67.2, 2.06 I 7

REFERENCE:

T.S. 3.4.1, 3.3.4.1, and 3.2.2: I 10 20 I

30 40 50 60 Core Power(% RATED)..

MCPR OPERA TING LIMIT VERSUS CO~E POWER EOC-RPT INOPERABLE

SINGLE LOOP OPERATION (BOC TO EOC)

'ATRIUM' 11 FUEL FIGURE 8.2-78 70

~

co 80

Rev. 19 PL-NF-21-003 Rev.a Page 89 of 103 Backup Pressure Regulator Inoperable SUSQUEHANNA UNIT 2 TRM / 3.2-90

(/)

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a I c.o 1.6 1.4 1.2 1.0 SSES UNIT 2 CYCLE:21 LEGEND CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME 130, 2.391

~

SAFETY ANALYSES AS~UME THAT FOUR BYPASS VALVES 135, 2.241 ARE OPERABLE; PER SR 3.7.6.1 AND 3.7.6.2 II. \\

USED IN DETERMINING MFLCPR

\\

A 8

I 40, 1.51 I I 52, 1.461 H

REFERENCE:

T.S. 3.4.1, 3.7.8, and 3.2.2 1

30 35 40 j'

45 50 55 60 Total Core Flow (MLB/HR)..

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

ATRIUM'-10 FUEL FIGURE 8.2-8A 65

~

70 c.o

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1.6 1.4 1.2 1.0 SSES UNIT 2 CYCLE:_21 LEGEND CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIM.E CURVE B: REALISTIC AVE;RAGE SCRAM INSERTION TIME SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES 130, 2.231 ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2

"""-- ~

135, 2.osl USED IN DETERMINING MFLCPR

~

\\

A 8

140, 1.51 I 152, 1.461

~

REFERENCE:

T.S. 3.4.1, 3.7.8, and 3.2.2 1 30 35 40 45 50 5,5 60 Total Core Flow {MLB/HR),.

MCPR OPERA TING LIMIT VERSUS TOTAL-CORE FLOW BACKUP PRESSURE REGULATOR INOPERABLE SINGLE LOOP OPERATION {BOC TO EOC)

!ATRIUM' 11 FUEL FIGURE 8.2-88 65 CD 70

Cf) 4.0 C

Cf) 0 C

3.8 m

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3.2 3.0 2.8

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cc Cl) w C.

0 2.2 0:::

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2E 2.0 1.8 1.6 1.4 SSES UNIT 2 CYCLE 21 LEGEND CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME CURVE C: CORE POWER:;;; 26% AND CORE FLOW :;;; 50 MLBM/HR ALL SCRAM INSERTION TIMES 23, 3.06 I C """ 126, 2.95j S~FETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 I

I

26.01, 2.52 :

USED IN DETERMINING MFLCPR

~

H 26.01, 2.50 1

!"... ~

140, 2.231

~~

I 50, 2.131 I --.

140 2 21 1 ---......

A I

I 60, 1.93 I I 50, 2.02

--.--~

B

---:__ ____ I 67.2, 1.86 I

]

REFERENCE:

T.S. 3.4.1, 3.7.8, and 3.2.2

so,1.93: :"---

1 1

67.2, 1.80 20 30 40 50 0/

Core Power (,o RATED) 60 MCPR OPERATING LIMIT VERSUS CO.RE POWER BACKUP PRESSURE REGULATOR INOPERABLE SINGLE LOOP OPERATION (BOC fo EOC)

ATRIUM'-10 FUEL FIGURE 8.2-9A 70

'° 80

(/)

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2.

6 4

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8 6

23, 2.68 I

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126,2.60 1 123, 2.60 I

C 26, 2.49 I

2. 4

2. 2

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H 26.01, 2.28 1

2. 0

1. 8 SSE$ UNIT 2 CYCLE 21 LEGEND CURVE A~ MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME CURVE B: REALISTIC AVERA~E SCRAM INSERTION TIME CURVE C: CORE POWERS 26% AND CORE FLOWS 50 MLBM/HR ALL SCRAM INSERTION TIMES SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES

, ARE OPERABLE PER SR 3.7.6.1.AND *3.7.6.2 I

I I

USED IN DETERMINING MFLCPR 140, 2.06 I I 67.2, 2.06 I A-B

1. 6 ]

REFERENCE:

T.S. 3.4.1, 3. 7.8, and 3.2.2 J 1.4 20 30 40 50 Core Power(% RATED) 60 MCPR OPERATING LIMIT VERSUS CORE POWER BACKUP PRESSURE REGULATOR INOPERABLE SINGLE LOOP OPERATION (BOC TO EOC)

ATRIUM' 11 FUEL FIGURE 8.2-9B.

70 80

a CD co

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1CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM I

INSERTION TIME CURVE 8: REALISTIC AVERAGE SCRAM INSERTION TIME 130, 2.391

~

SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES i--.....

ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 I

~

140, 2.091 I

I USED IN DETERMINING MFLCPR I

I I

~

A B

145, 1.701 I 52, 1.67 I

REFERENCE:

T.S. 3.4.1, 3.2.2, and TRM 3.3.7 I 30 35

~

Total Core Flow (MLBJHR)

MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW

ONE TSV OR TCV CLOSED SINGLE LOOP OPERATION (aoc TO EOC)

ATRIUM'-10 FUEi,.

FIGURE 8.2-1 0A 65 70 c.o

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(f) 3.0 C

(f)

D C m 2.8 I

z z 2.6 C z

=i N

2.4

"§ 2.2

J C)

C:

ltS...

2.0

-l Cl)

o C.

0 s:

0:::

0..

w

(.)

1.8 is.:,

a:

I c.o

---i 1.6 1.4 1.2 1.0 SSES UNIT 2 CYC.LE*21 LEGEND CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTiON TIME

cuRVE B: REALl$TIC AVERAGE SCRAM INSERTION TIME I

130, 2.231

'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

-.............. 140, 1.931 I

I

~

~ A B

I s2, 1.61 I l4s.-:1.10 I

REFERENCE:

T.S. 3.4.1, 3.2.2, and TRM 3.3.7 I 30 35 40 45 50 55

.. Total Core Flow (MLB/HR)

J

MCPR OPERATING LIMIT VERSUS tOTAL CORE FLOW

; ONE TSV OR TCV CLOSED SINGLE LOOP OPERATION (BOC TO EOC)

ATRIUM' 11 FUEL

1 FIGURE 8.2-108'.;

so 65 co 70

Cl) 4.0 C

Cl) 0 C

3.8 m

c

)> z 3.6 z

)>

C 3.4 z

N 3.2

'§ 3.0

i Cl)

C:

2.8 IIS..

Q)

u C.

0 2.6

~

0::

0.

w

()

N a 2.4 I co co 2.2 2.0 1.8 1.6 1.4 SSES UNIT 2 CYCLE 21 I

I LEGEND

; ~

CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME CURVE,B: REALISTIC AVERAGE SCRAM INSERTION TIME CURVE C: CORE POWER~ 26% AND CORE FLOW~ 50 MLBM/HR ALL SCRAM INSE~TION TIMES I 23, 3.061 I

I I

SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES c'

126, 2.951 ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 USED IN DETERMINING MFLCPR 1 26.01, 2.52 I

i 140, 2.t7I

~ 26.01, 2.30 I ----......._

I 50, 2.131

*ta--

A

~...

160, 1.90 I 140, 1.931

_------ 167.2, 1.81 1 150, 1.871 B 60, 1.80 1

~

I

REFERENCE:

T.S. 3.4.1, 3.2.2, and TRM 3.3.7 1 I

20 30 I

40 50 60 Core Power(% RATED)

MCPR OPERATING LIMIT VERSUS CORE POWER

. ONETSV OR TCV CLOSED SINGLE LOOP OPERATION (BOC TO EOC)

ATRIUM'-10 FUEU

FIGURE 8.2-11A'

167.2, 1.721 70 co 80

Cl)

C Cl) 0 C

m I

)>

z z

)>

C z

-j I\\.)

-j

a

s:;: -

c.v i\\J I co co

'§

J Cl C:

~

Cl!...

Cl)

C.

0 0::

fl.

(.)

~

ss*es UNIT 2 CYCLE 21 4.0 LEGEND 3.8 CURVE' A: MAXIMUM ALLOWABLE AVERAGE SCRAM

3.

INSERTION TIME 6

CURV~* B: REALISTIC AVERA~E SCRAM INSERTION TIME 3.4 CURVE:C: CORE POWER~ 26% AND CORE FLOW~ 50 MLBM/HR

3. 2 ALL SCRAM INSERTION TIMES I

I I

3. 0 SAFETY ANA~ YSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2

2. 8 23, 2.681

USED IN DETERMINING MFLCPR

2.

............ 26, 2.60 I 6

123,2.60~

I H 26, 2.491

2. 4

2. 2 I 26.01, 2.15 A

2.

, 67.2, 2.06 I 0

n 26.01, 2.061 8

140, 2;061 8

1.

1. 6 H

REFERENCE:

T.S. 3.4.1, 3.2.2, and TR_M 3.3.7:

I 1.4 20 30 I

40 50 60 Core Power(% RATED)

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

ATRIUM' 11 FUEL*

FIGURE 8.2-118*

70 co 80

Rev. 19 PL-NF-21-003 Rev. O Page 99 of 1 03 9.0 POWER/ FLOW MAP 9.1 9.2 References Technical Specification 3.3.1.1 Description Monitor reactor conditions to maintain THERMAL POWER/ core flow outside of Stability Regions I and 11 of the Power I Flow map, Figure 9.1..

If the OPRM Instrumentation is OPERABLE per TS 3.3.1.1, Region I of the Power/ 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 I Flow map is considered an immediate scram region.

Region II of the Power /Flow map is**considered an immediate exit region

.. r.~~ar_~l~~~.. o! ~he __ c:>perc:1_bil_ity of. t~e OP.RM. lnstr~mentation.

SUSQUEHANNA UNIT 2 TRM / 3.2-100

120 110 100 90 80 c

w

!¢ 70

~

40 30 20 10 0

0 Rev. 19

Purpose:

I I

-f- --r-1--r-1-- +-1 UNIT 2

~ ::~tr_;:i_c:_:.;J:;--:;:~::.-i!:'==:r,nn,,,~

Initial/ Date:

I STABILITV*REGION I IF OPRM INOPERABLE IMMEDIAlELY SCRAM IAW APPLICABLE PROCEDURE.

IF OPRM OPERABLE IMMEDIAlELY EXIT IAW APPLICABLE PROCEDURE.

STABILITY REGION II IMMEDIA lEL Y EXITIAW APPLICABLE PROCEDURE.

RES1RIC1ED REGION IF ABOVE MELLLABOUNDARY, IMMEDIAlEL YEXITIAW APPLICABLE PROCEDURE.

=~--~~-----i~ -l-~~-~-~- -~-1-+- -+-1-+-t-

1--:-:

-.l--L-.J-.... ~~~'--, --1-r-:

PL-NF-21-003 Rev.a Page 100 of 103 120 110 100 90 80 60 50 40 20 10 10 20 30 40 50 60 70 80 90 Total Core Flow (Mlbm/hr) 100 0

110 Figure 9.1 SSES Unit 2 Cycle 21 Power/ Flow Map SUSQUEHANNA UNIT 2 TRM / 3.2-101

Rev. 19 10.0. OPRM SETPOINTS 10.1 References Technical Specification 3.3.1.1 10.2 Description PL-NF-21-003 Rev. O

Page 101 of 103 **

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 TRM / 3.2-102

Rev. 19 11.0. REFERENCES PL-NF-21-003 Rev. 0

- Page 102 of 103 11.1 The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC, specifically those described in the following documents:

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

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

Framatome ANP, May 2001.

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

4. XN-NF-80-19(P)(A), Volume 1 and Supplements 1 and 2, "Exxon.Nuclear Methodology for Boiling Water Reactors: Neutronic Methods for Design and Analysis," Exxon Nuclear Company, March 1983.

5. XN-NF-80-19(P)(A), Volume 3 Revision 2 "Exxon Nuclear Methodology for Boiling Water Reactors Thermex: Thermal Limits Methodology Summary Description," Exxon Nuclear Company, January 1987.

6. XN-NF-80-19(P)(A), Volume 4, Revision 1; "Exxon.Nuciear Methodology for Boiling Water Reactors: Application of the ENC Methodology to BWR Reloads," Exxon Nuclea*r Comp~friy, June 1986.

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

September 1986.

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

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

10. EMF-85-74(P)(A), Revision 0, Supplement 1(P)(A) and Supplement 2(P)(A),

"RODEX2A (BWR) Fuel Rod Thermal-Mechanical Evaluation Model,"

Siemens Power Corporation, February 1998.

11. EMF-2158(P)(A), Revision 0, "Siemens Power Corporation Methodology for Boiling Water Reactors: Evaluation and Validation of CASMO-4/Microburn-B2," Siemens Power Corporation, October 1999.

12. EMF-CC-074(P)(A), Volume 4, Revision 0, "BWR Stability Analysis -

Assessment of STAIF with Input from MICROBURN-B2," Siemens Power Corporation, August 2000.

SUSQUEHANNA UNIT 2 TRM / 3.2-103

Rev. 19 PL-NF-21-003 Rev. O.

Page103 of 103

13. NEDO-32465-A, "BWROG Reactor core stability Detect aria suppress Solutions Licensing Basis Methodology for Reload Applications," August 1996.

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

15. BAW-10247PA, Revision 0, "Realistic Thermal-Mechanical Fuel Rod Methodology for Boiling Water Reactors," AREVA, Inc., April 2008.

16. ANP-10340P-A, Revision 0, "Incorporation of Chromia-Doped Fuel Properties in AREVA Approved Methods," Framatome Inc., May 2018.

17. ANP-10335P-A, Revision 0, "ACE/ATRIUM-11 Critical Power Correlation,"

Framatome Inc., May 2018.

18. ANP-10300P-A, Revision 1, "AURORA-8: An Evaluation Model for Boiling Water Reactors; Application to Transient and Accident Scenarios,"

Framatome Inc., January 2018.

19. ANP-10332P-A, Revision 0, "AURORA-8: An Evaluation Model for Boiling Water Reactors; Application to Loss of Coolant Accident Scenarios,"

Framatome Inc., March 2019.

. 20. ANP-10333P-A; Revision 0, "AURORA-B: An Evaluation Model for Boilirig.

Water Reactors; Application to Control Rod Drop Accident (CRDA),"

Framatome Inc:; March 2018.

21. ANP-10307PA, Revision 0, "AREVA MCPR Safety Limit Methodology for Boiling Water Reactors," AREVA, Inc., June 2011.

22. BAW-10247P-A Supplement 1P-A, Revision 0, "Realistic Thermal-Mechanical Fuel Rod Methodology for Boiling Water Reactors, Supplement 1:

Qualification of RODEX4 for Recrystallized Zircaloy-2 Cladding," AREVA Inc.,

April 2017.

23. BAW-10247P-A Supplement 2P-A, Revision 0, "Realistic Thermal-Mechanical Fuel Rod Methodology for Boiling Water Reactors, Supplement 2:

Mechanical Methods," Framatome Inc., August 2018.

SUSQUEHANNA UNIT 2 TRM / 3.2-104

ML21105A487

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