ML23195A033

Technical Requirements Manual

ML23195A033
Person / Time
Site:	Susquehanna
Issue date:	06/29/2023
From:	Susquehanna
To:	Office of Nuclear Reactor Regulation
References
Download: ML23195A033 (1)

Text

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TO: 06/30/2023 LOCATION: USNRC FROM: 1\\JCLEAR RECORDS DOCUMENT CONTROL CENTER (NUCSA-2)

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TRM2 - TECHNICAL REQUIREMENTS :v'AEUAL UNIT 2

REMOVE f'll\\..i.\\.TUAL TABLE 0.? CONTENTS DATE: 03/30/2023

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uu11 *.::>u,.::::...vL...;i

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ANY DISC'fic.:;;A.NCIES WITH 'l'HE MATF.?.IAL PROVIDED, CONTACL' UCS @ X31?1 OR X3194 FOR ASSIST11J'JC.ts. UPDATES FOR HARDCOPY MANUALS WILL BE DISTRIBUTED W:THIN 3 DAYS IN

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SSES MANUAL

Manual Name: TRrvi2 Manual

Title:

TECHNICAL REQUIREMENTS MANUAL UNIT 2

Table Of Contents Issue Date: 06/29/2023 Procedure Name Rev Issue Date Change ID Chancre Number TEXT LOES 99 01/03/2019

Title:

LIST OF EFFF.CTIVE SECTIONS

TEXT TOC 28 12/13/2022,.;...:......._

Title:

TABLE OF CONTENTS I

/,/>_ "*

{.- \\,, /' -,.,.

' *~.,,

TEXT :;_. ~ 0 11 9/2007. '-,..,,,

Title:

USE Al'ilD.l:\\.PPLIC.ATION :JF:FINITIONS *... *?~_-:,

TEXT 2.1 1 02/04/2005 <*_**,. ~:f~;/,>

Title:

PLANT PROGRAMS AND SETPOINTS P:.,AKT PROGRAMS * /~_,

\\. _l TEXT 2 2 13 06/29./.2'

• 1

• Ti t~e: PLANT PROGRAMS AND SETPOINTS _Kf;T~~~T::;_TRi,P SETPOINT TA3LE

/;~'-,.._'*J.,:-~i::/

TEXT 3. Q fl. *. 0:3/J 8/2021

',, "',._ //

Title:

APPLICABILTTY TECHNTC~?~EQ~R:i?,UENT FOR OF:O:?J,_TIQN (TRO) l,PPLICABIL=TY

TEXT 3.1.1 - <~-~;j]J>l~/09/2007 ' *.

Title:

REACTIVITY CONJJiROL'*sy's*.rEMS ANT::CIPATED 'l'Rl',NS:ENT WITHOUT flCRAM ALTERNJ\\.TE ROD INJEC'l'IC.Y (A'l'~S I,~I*) IN!',;f.RDMENTA_'.."ON

TEXT 3.1.2 / \\,.::;~1~-~/ 0 11/19/2002

Title:

REACTIVIT¥ CO OL SYSTEMS CONTROL ROD DRIVE (CRD) HOUSIXG SUPPORT

\\

'J'~:XT 3.1. 3 :::, 12/18/~C:017.

Title:

REACTIVITY CONTROL SYSTEMS CONTROL ROD J3LOCK INSTRUMEKTA'l'ION

\\

TEXT 3.1.4 1 10/1.2/2020

Title:

REACTIVITY CONTROL SYSTEMS CONTROL ROD SCRAM ACCUMULATORS INSTRUMENTATION AND CHECK VALVE

TEXT 3.2.1 20 03/30/2023

Title:

CORE OPERATING LIMITS REPORT {COLR)

• Page 1 of 1.5 Rep,ort Date: 06/30/23 SSES MANUAL

Manual Name: TR!--:2

Manual

Title:

TECHNICAL REQUIREMENTS MA_"\\f:JA7-' UNIT 2

• TEXT 3. 3. 1 0 l] / 19 / 2 0 0 2

Title:

INSTRill~ENTATION RADIATION MONITORING INSTRUMENTATION

TEXT 3. 3. 2 3 03/31/2011

Title:

INSTRU!-!IFJ,;TATION SEISi 1,:r:C MONITOR-NG INSTRUMENTATION

TEXT 3.3.3 2 11/09/2007

Title:

INSTRL1~EN~ATION METEOROLOGICAL MONITORING INSTRUMENTATION

TEXT 3.3.4 11 07/:il/2017'

Title:

INSTRUTv'.ENTATION TRM POST-ACCIDENT MONITORING INSTRUMEKTATION

TEXT 3.3.5 0 11/19/2002

Title:

INSTRUMENTATION THIS ?!I.GE INTENTIONALLY LEFT BLANK

TEXT 3.3.6 6 06/29/2023

Title:

INSTRUME:-JTATION TRM ISOLATION ACTUATION INSTRUMENTATION

• TEXT 3.3.7 1 0° 7 /20?.7.

Title:

INSTRUMENTATION MAIN TURBINE OVERSPEED PROTECTION SYSTEM

TEXT 3.3.8 l 10/22/2003

Title:

INTENTIONAI,J,Y LEFT DLANK

TEXT 3.3.9 3 05/14/2009

Title:

INSTRUMENTATION LPRM UPSCALE ALARM INSTRill~ENTATION

TEXT 3.3.10 1 12 /2004

Title:

INSTRUMENTATION REACTOR RECIRCULATION PUMP MG SET STOPS

TEXT 3.3.11 1 10/22/2003

Title:

INSTRUMENTATION MVP ISOLATION INSTRUMENTATION

TEXT 3.3.12 2 04/02/2019

Title:

WATER MONITORING INSTRUMENTATION

• Page 2 of 15 Report Date: 06/30/23 SSES MANUAL

Manual Name: TRM2

Manual

Title:

TECHNICAL REQUIREMENTS MANUAL UNIT 2

TEXT 3.4.1 1 04/26/2006

Title:

REACTOR COOLANT SYSTEM REACTOR COOLANT SYSTEM CHEMISTRY

TEXT 3.4.2 1 04/16/2009

Title:

INTENTIONALLY LEFT BLANK

TEXT 3.4.3 1 11/09/2007

Title:

REACTOR COOLANT SYSTEM REACTOR COOLANT SYSTEM (RCS)

TEXT 3.4.4 2 05/14/2009

Title:

REACTOR COOLANT SYSTEM REACTOR RECIRCULATION FLOW AND ROD LINE LIMIT

TEXT 3.4.5 1 04/26/2006

Title:

REACTOR COOLANT SYSTEM REACTOR VESSEL MATERIALS

• 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 Page 3 of 15 Report Date: 06/30/23 SSES MANUAL

Manual Name: TR!"J2

Manual

Title:

TECHNICAL REQUIREMENTS MAl\\CA::., ONIT 2

• T~XT 3. G. 11 0 11/19 002

Title:

CONTAINrt'.ENT PRIMARY CONTAINMENT CLOSED SYSTE:*I BOUNDARIES

TEXT 3.7.l 0 J 19/2002

Title:

PLANT SYSTEMS EMP.RGE='lC'{ SP.RVICE KATER SYSTF.M (l!:SW) SHJ'J'DO'iiJN

TEXT 3.7.2 0 11/19/2002

Title:

PLANT SYS-:='EMS ULTI:t-,:..:z'\\.TE HEAT SINK (URS) AND GROUND WATER LEVEL

TEXT 3. 7. 3. l *; 04/~d/2022

Title:

PLANT SYSTEMS FIRE SUPPRESSION WATER SUPPLY SYSTEM

TEXT 3.7.3.?. 3 04/::_6/2009

Title:

PLANT E3YS'::'EM:3 SPRAY nm SPRINKLER SYSTEMS

TEXT 3.7.3.3 4 05/16/2016

Title:

PLANT SYSTEMS CO2 SYSTEMS

• TEXT 3.7.3.4 2 C*'.l/16/2009

Title:

PLANT SYSTEMS HALON SYSTEMS

TEXT 3.7.3.5 2 04/:.6/2009

Title:

PLANT SYSTEM/3 FIRE HOSE STI\\TTONS

TEXT 3.7.3.6 2 04/::_6/2009

Title:

PLANT SYSTEMS YARD FIRE HYDRAJ:-JTS AND HYDR1'2-TT HOSE HOUSES

TEXT 3. 7. 3. 7 1 0*1/26/2006

Title:

PLANT SYSTEMS FIRE RATED ASSEMBLIES

TEXT 3.7.3.8 15 08/02/2021

Title:

PLANT SYSTEMS FIRE DETECTION INSTRUMENTATION

TEXT 3.7.4 1 04/.26/2006

Title:

PLANT SYSTEMS SOLID RADWASTE SYSTEM

• Page 4 of 15 Report Date: 06/30/23 SSES MANUAL

Manual Name: TRM2

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

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

• TEXT 3.7.8 9 03/05/2015

Title:

PLANT SYSTEMS SNUBBERS

TEXT 3.7.9 2 03/05/2019

Title:

PLANT SYSTEMS CONTROL STRUCTURE HVAC

TEXT 3.7.10 2 04/29/2014

Title:

PLANT SYSTEMS SPENT FUEL STORAGE POOLS (SFSPS)

TEXT 3.7.11 2 11/01/2018

Title:

PLANT SYSTEMS

TEXT 3.8.1 4 08/02/2021

Title:

ELECTRICAL POWER PRIMARY CONTAINMENT PENETRATION CONDUCTOR OVERCURRENT PROTECTIVE DEVICES

TEXT 3.8.2.1 2 11/09/2007

Title:

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

CONTINUOUS

TEXT 3.8.2.2 3 06/23/2021

Title:

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

AUTOMATIC

• Page 5 of 15 Report Date: 06/30/23 SSES MA.NUAL

Manual Name: TFY:C

Manual

Title:

TECiil\\JICAL REQUIREMENTS MM-JAL UNIT 2

• TEXT 3.8.3 01/28 020

Title:

ELECTRICAL POWER DI':;;SEL GENERJ\\20:?. (DG) MAINTENANCE ACTIVITIES

TEXT 3. 8.1. 1 02/04/2005

Title:

ELECTRIC.' 1 ~- POWJO:R 7.4 V;)C F:T,ECTRJC,*.L SUBSYSTEM

TEXT 3.8.5 1 11/14/2013.

Title:

ELECTRICA~ POWER DEGRl'i.DED VOLTAGE PROTECTION

TEXT 3.S.6 3 03/05/2019

Title:

ELECTRICA:S POWER EMERGENCY SWITCHGEAR ROOM COOLING

TEX'!' 3.8.7 3 02 5/2021

Title:

BATTERY '.f'.!'\\=N'rENi\\NCE JI.ND MONITORING PROGRJ\\t-'.

TEXT 3.9.l 0 ll/19/2002

Title:

REFUELING OPERATIONS DECAY TIME

• TEXT 3.9.2 0 11;* 9/2002

Title:

REFUELING OPERATIONS COMMUNICATIONS

TEXT 3.9.3 J 03/12/2019

Title:

REFUELING OPERJ\\TIONS REFUELING PLATFORM

TEXT 3.10.1 1 04/26/2006

Title:

MISCELLANEOUS SEALED SOURCE COKTAMINATION

TEXT 3. 1 O. 2 1 0 4 0 9 / 2 0 0 7

Title:

MISCELLANEOUS SHUTDOWN MARGIN TEST RPS INSTRUMENTATION

TEXT 3.10.3 4 10/05/2022

Title:

MISCELLANEOUS INDEPENDENT SPENT FUEL STORAGE INSTALLATION (ISFSI)

TEXT 3.10.4 2 04/17/2009

Title:

INTENTIONALLY LEFT BLANK

• Page 6 of 15 Report Date: 06/30/23 SSES MANUAL

Manual Name: TRM2

Manual

Title:

TECHNICAL REQUIREMENTS MANUAL UNIT 2

TEXT 3.11.1.1 1 04/26/2006

Title:

RADIOACTIVE EFFLUENTS LIQUID EFFLUENTS CONCENTRATION

TEXT 3. 11. 1. 2 1 04/26/2006

Title:

RADIOACTIVE EFFLUENTS LIQUID EFFLUENTS DOSE

TEXT 3.11.1.3 1 04/26/2006

Title:

RADIOACTIVE EFFLUENTS LIQUID WASTE TREATMENT SYSTEM

TEXT 3.11,.1. 4 2 10/09/2012

Title:

RADIOACTIVE EFFLUENTS LIQUID RADWASTE EFFLUENT MONITORING INSTRUMENTATION

TEXT 3. 11. 1. 5 3 03/05/2015

Title:

RADIOACTIVE EFFLUENTS RADIOACTIVE LIQUID PROCESS MONITORING INSTRUMENTATION

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 7 of 15 Report Date: 06/30/23 SSES MANUAL

Manual Name: TRM2

Manual

Title:

TECHNICAL REQUIREMENTS MANUAL UNIT 2

• TEXT 3. 11. 4. 1 5 01/03/2022

Title:

RADIOACTIVE EFFLUENTS MONITORING PROGRAM

TEXT 3.11.4.2 2 04/26/2006

Title:

RADIOACTIVE EFFLUENTS LAND USE CENSUS

TEXT 3. 11. 4. 3 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 REQUIREMENTS

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 1 07/01/2021

Title:

ADMINISTRATIVE CONTROLS REPORTING REQUIREMENTS

TEXT 4.6 0 09/27/2003

Title:

ADMINISTRATIVE CONTROLS RADIATION PROTECTION PROGRAM

• Page 8 of 15 Report Date: 06/30/23 SSES MANUAL

,.- Manual Name: TRM2 Manual

Title:

TECHNICAL REQUIREMENTS MANUAL UNIT 2

TEXT 4.7 1 12/13/2022

Title:

ADMINISTRATIVE CONTROLS TRAINING

TEXT B3.0 7 03/18/2021

Title:

APPLICABILITY BASES TECHNICAL REQUIREMENT FOR OPERATION (TRO) APPLICABILITY

TEXT B3.1.1 2 04/29/2014

Title:

REACTIVITY CONTROL SYSTEM BASES ANTICIPATED TRANSIENT WITHOUT SCRAM ALTERNATE ROD INJECTION (ATWS-ARI) INSTRUMENTATION TEXT B3.1.2 0 11/19/2002

Title:

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

TEXT B3.1.3 4 12/18/2017

Title:

REACTIVITY CONTROL SYSTEM BASES CONTROL ROD BLOCK INSTRUMENTATION

TEXT B3.1.4 1 10/12/2020

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 9 of 15 Report Date: 06/30/23 SSES MANUAL

Manual Name: Tm,;:,;

Manual

Title:

TECHNICAL REQUIREMENTS Mk'\\UI-1.cL UNIT 2

• TEXT BJ.3.6 7 06/?. 023

Title:

INSTRUJYi"":NTATION Bl'-.SES TRM ISOLATION ACTUATION INSTRUMENTATION

TEXT B3.l.7 4 0 17/2022

Title:

TNSTRCJiv:BNTATION BA.SES MA TN TUR3::.lF OVERS PEED PROTECTION SYSTEM

TEXT 33.3.8 1 10/22/2003

Title:

INTENTIONALLY BLANK

TEXT B3.3.9 1 0 03/2019

Title:

INSTRUME~,TATION BASES LPRM UPSCP..LE ALARM INSTRU!VIENTA':'ION

TEXT B3.3.10 3 02 22/2012

Title:

INSTRUf/IENTATION BASES RJ*:ACTOR RECIRCULJ\\TTCJN PUMP MG SE'::' STOPS

TEXT B3.3.ll 1 10/22/2003

Title:

INSTRUMEN':ATION BASES MVP ISOLATION INSTRUMENTATION

• TEXT BJ.3.12 1 0'c/Cl2/2019

Title:

WATER MONITORING INSTRUMENTATION

TEXT Bl.4.1 0 11 _9/?.002

Title:

REACTOR COOI,ANT SYSTEM BASES R:.CI',CTOR COOL1'.2H SYSTEM CE( JS'T'RY

TEXT B3. 4. 2 1 04/16/2009

Title:

REACTOR COOLANT SYSTEM BASES STRDCTURAL IN~EGRITY

TEXT B3.4.3 1 Jl/09/2007

Title:

REACTOR COOLANT SYSTEM BASES HIGH/LOW PRESSURE INTERFACE LEAKAGE MONITOR

TEXT B3.4.4 1 01/03/2019

Title:

REACTOR COOLANT SYSTEM BASES REACTOR RECIRCULATION FLOW AND ROD LINE LIMIT

TEXT B3.4.5 0 11/19/2002

Title:

REACTOR COOLANT SYSTEM BASES REACTOR VESSEL MATERIALS

• Page 10 of 15 Report Date: 06/30/23 SSES MANO'AL

Manual Name: TRM2

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.l 2 03/17/2020

Title:

ECCS RPV WATER INVENTORY CONTROL AND RCIC SYSTEM ADS MANUAL INHIBIT

TEXT B3.5.2 2 03/05/2019

Title:

ECCS RPV WATER INVENTORY CONTROL AND RCIC SYSTEM ECCS RPV WATER INVENTORY CONTROL AND RCIC MONITORING INSTRUMENTATION

TEXT B3.5.3 2 03/05/2019

Title:

ECCS RPV WATER INVENTORY CONTROL AND RCIC SYSTEM LONG TERM NITROGEN SUPPLY TO ADS TEXT B3.6.l 0 11/19/2002

Title:

CONTAINMENT BASES VENTING OR PURGING

TEXT B3.6.2 0 11/19/2002

Title:

CONTAINMENT BASES SUPPRESSION CHAMBER-TO-DRYWELL VACUUM BREAKER POSITION INDICATION TEXT B3.6.3 1 04/19/2007

Title:

CONTAINMENT BASES SUPPRESSION POOL ALARM INSTRUMENTATION

TEXT B3.6.4 1 12/14/2004

Title:

CONTAINMENT BASES PRIMARY CONTAINMENT CLOSED SYSTEM BOUNDARIES

TEXT B3.7.1 0 11/19/2002

Title:

PLANT SYSTEMS BASES EMERGENCY SERVICE WATER SYSTEM (SHUTDOWN)

TEXT B3.7.2 0 11/19/2002

Title:

PLANT SYSTEMS BASES ULTIMATE HEAT SINK (UHS) GROUND WATER LEVEL

TEXT B3.7.3.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: 06/30/23 SSES MANUAL

Manual Name: TRI'f7

Manual

Title:

TECL:'HCAL REQUIREMENTS l'/IAKUA::C UNIT 2

TEXT B3. *;. 3. 3 () 11 19/2002

Title:

PLANT SYSTEMS BASES CO2 SYSTEMS

TEXT B3.7.3.4 3 06/19/2019

Title:

PLANT ~iys*:*EMS BASES ':-oj\\LON SYSTEH3

TEXT B3.7.3.5 1 04/26/2006

Title:

PLANT SYSTEMS BASES FIRE HOSE STATIONS

TEXT B3.7.3.6 1 Of 2 /2006

Title:

PLANT SYSTEMS BASES Y..Zill.D FIRE HY~RANTS AND HYDRANT HOSE HOUSES

TEXT 33.7.3.7 0 U/19/200::::

Title:

PLANT SYS'~"EMS BASES l'IRE RATED J\\.SSEJVIB.LIES

TEXT B3.7.3.8 3 09/27/2012

Title:

PLANT SYSTEMS BASES FIRE DETECTION INSTRm,:ENTATION

TEXT ID. 7.4 0 19 002

Title:

PLANT SYSTEMS BASES SOLID RADWASTE SYSTEM

rrgXT B3. 7. 5. 1 0 11/19/2002

Title:

PLANT SYSTEMS fll\\SFS :VJ'.\\.IN CONDF.NS:;'R OFFGAS W:!DROGEN MONITOR

TEXT B3.7.5.2 0 11/19/2002

Title:

PLANT SYSTEMS BASES MAIN CONDENSER OFFGAS EXPLOSIVE GAS MIXTURE

TEXT B3.7.5.3 0 11/19/2002

Title:

PLANT SYSTEMS BASES LIQUID HOLDUP TANKS

TEXT B3.7.6 4 06/04/2013

Title:

PLANT SYSTEMS BASES ESSW PUMPHOUSE VENTILATION

TEXT B3.7.7 2 01/31/2008

Title:

PLANT SYSTEMS BASES MAIN CONDENSER OFFGAS PRETREATMENT LOGARITHMIC RADIATION MONITORING INSTRUMENTATION Page 12 of 15 Report Date: 06/30/23 SSES MANCJAL

Manual Nante; TRr,::.2

Manual

Title:

TECHNICAL REQUIREMENTS MANUAL UNl'l' 2

TEXT B3.7.8 4 o::_/::;::_/2014

Title:

PLANT SYSTEMS BASES SNUBBERS

'l'EXT B3. '/. 9 3 03/05/2019

Title:

l:'I,ANT SYSTF:Ms BASF.S c,)NTROL c~'l'l!.':]1__:TURE HVJ\\C

TEXT B3.7.10 1 12/14 004

Title:

PLANT SYSTEMS BASES SPENT FUEL STORAGE POOLS

TEXT B3.7.11 3 01/2018

Title:

STRUCTUR.~L INTEGRITY

TEXT E3.8.l 7 010

Title:

T<:T,ECTRICJ\\L POWER BAS,:'.S PRIMARY CONTAINMP.NT PENETRATION CONDUCTOR OVERCURREN'i' PROTECTIVE DEVICES

TEXT B3.8.2.l 0 11/19/2002 T:i. tle: ELECTRICJ.I~ POWER BAS3S MOTOR OPE~~TED VALVES (MOV) THERivLZ,,L OVERLOAD PROTECTION -

• CON'J'INUO:JS

TEXT B3.8.2 2 ). 06/23/2021

Title:

ELECTRICAL POWER BASES MOTOR OPE~ATED VALVES (MOV) THERMAL OVERLOA8 PROTECTION AUTOMATIC

TF.XT D3. 8. 3 0 11/19 002

Title:

ELF.:CTRICAT, POWER BASJ*:f, DIESEL (mNERATOR (f~G) MAINTF.NN,CE ACTTVITIES

TEXT B3.8.4 0 ll/19/2002

Title:

ELECTRICP.L POWER BASES 24 VDC ELECTRICAL POWER SUBSYST3M

TEXT B 3. 8. ::i 1 ::.4 013

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 Pag~ 13 of 15 Report Date: 06/30/23 SSES MANUAL

Manual Name: TRI1i7.

Manual

Title:

TECEICCAL REQUIREMENTS Ml-\\NUAL UNIT 2

TEXT B3.9.1 0 11/19/2002

Title:

REFUELIKG OPERATIONS 3ASES DECAY TIME

TEXT 33.9.2 0 1]_/'19/200.?.

Title:

RE'.FUELI:\\fG OPERATIOX,~ :SASES COMY'.ffiFCATIONS

TEXT B3.9.3 1 03/12/2019

Title:

REFUELING OPERATIONS BASES REFU3=.iING PLATFORYI

TEXT B3. l O. 1 0 2-9/2002

Title:

MISCELLANEOUS BASES SEALED SOURCS CONTAMINATION

'l'EXT B 3. 10. 2 1 o;; /1 0/2007

Title:

MISCEI,Li\\c'JSUUE, BASE~; SHUTDOWN JY',ARGIN TEST "*"" INSTRUMF7'!TATION

TEXT B3.10.3 3 10/05 022

Title:

MISCELL1'.::~EOUS BASES INDEPENDENT SPENT FUEL STORAGE H-!STALLATION (:;:SFSI)

TEXT B3.ll.l.1 1 05/10/2016

Title:

RADIOACT=VE EFFLUEKTS BASES LIQC:D EFFLUENTS CONCENTFATION

TEXT B3.;1.l.?. 0 11/19/2002

Title:

RADIOI,CTIVE F:FFLUF:K'"~s BASES L TG,:=D EFl*'LUEN'::"S DOSE

TEXT B3.11.1.3 0 11/19/2002

Title:

RADIOACTIVE EFFLUE~TS BASES LIQUID WASTE T~3ATMENT SYST3M

TEXT B3.11.1. 4 0 1 1 /.:.9/2002

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 B3.11.2.1 1 12/14/2004

Title:

RADIOACTIVE EFFLUENTS BASES DOSE RATE

Page 14 of 15 Report Date: 06/30/23

• SSES MANUAL

Manual Name: TRM2

Manual

Title:

TECHNICAL REQUIREMENTS MANUAL UNIT 2

TEXT B3.ll.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 IN FORM TEXT B3.ll.2.4 0 11/19/2002

Title:

RADIOACTIVE EFFLUENTS BASES GASEOUS RADWASTE TREATMENT SYSTEM

TEXT B3. 11. 2. 5 5 07/03/2013

Title:

RADIOACTIVE EFFLUENTS BASES VENTILATION EXHAUST TREATMENT SYSTEM

TEXT B3.11.2.6 2 09/08/2016

Title:

RADIOACTIVE EFFLUENTS BASES RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION TEXT B3.ll.3 0 11/19/2002

Title:

RADIOACTIVE EFFLUENTS BASES TOTAL DOSE

TEXT B3. 11. 4. 1 6 01/03/2022

Title:

RADIOACTIVE EFFLUENTS BASES MONITORING PROGRAM

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

Title:

RADIOACTIVE EFFLUENTS BASES LAND USE CENSUS

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

Title:

RADIOACTIVE EFFLUENTS BASES INTERLABORATORY COMPARISON PROGRAI~

TEXT B3.12.1 1 10/04/2007

Title:

LOADS CONTROL PROGRAM BASES CRANE TRAVEL-SPENT FUEL STORAGE POOL

TEXT B3.12.2 1 12/03/2010

Title:

LOADS CONTROL PROGRAM BASES HEAVY LOADS REQUIREMENTS

TEXT B3.12.3 0. 11/19/2002

Title:

LOADS CONTROL PROGRAM BASES LIGHT LOADS REQUIREMENTS

• Page 15 of 15 Report Date: 06/30/23 Instrument Trip Setpoint Program Rev. 13 2.2

• 2.0 PLANT PROGRAMS AND SETPOINTS

2.2 Instrument Trip Setpoint Table

The Instrument Trip Setpoint Limits in Table 2.2-1 are the Trip Setpoint value limits that were contained in the Instrumentation Setpoint tables for protection systems and other functions important to safety that were included in the scope of the original Standard Technical Specifications. Actual instrument setpoints are established utilizing the Allowable Values specified in the Technical Specifications and Technical Requirements.

Allowable Values are established in the Reference LCOs and TROs identified in this Table. TRO references are enclosed in square brackets.

Instrumentation process setpoints for the listed subsystems and trip functions are set consistent with the Trip Setpoint Limit Column of Table 2.2-1. Actual setpoints are established in accordance with engineering procedures.

Alarm setpoints and other non-protection system trip settings as may be found in the Technical Specifications or in the Technical Requirements are not included in this table.

Reference:

MFP-QA-1220, Engineering Change Process Handbook

-* SUSQUEHANNA - UNIT 2 TRM / 2.0-5 Instrument Trip Setpoint Program Rev. 13 2.2

• TABLE 2.2-1 (Page 1 of 8)

INSTRUMENTATION SETPOINTS

SYSTEM/REFERENCE LCO [TRO TRIP r-UNCTION TRIP SETPOINT

2.2.1 Reactor Protection

2.2.1.1 3.3.1.1 Intermediate Range Monitor, Neutron Flux -~; 120/125 divisions of full scale High 2.2.1.2 3.3.1.1 Average Power Range Monitor, Neutron s; 18% of HA Ti::O THERMAL POWER Flux - High (Setdown) 2.2.1.3 3.3.1.1 Average Power Range Mor:i:or, Simulated 0.55 W + 58.7%

Thermal Powe:- High Two Loop Operation 2.2.1.4 3.3.1.1 Average Power Range Monitor, Simulated 0.55 (W - t:,.W) + 58.7%:b)

Thermal Power - High Single Loop Operation 2.2.1.5 3.3.1.1 Average Powe:- Range Monitor, Simulatod :S 113.5% of f\\P,TED THERlv1J\\L Thermal Power - High Flow Clamp POWER 2.2.1.6 3.3.1.1 Average Power Range Mor,ito:-, Neutron Flux -5 118% of RATED THERMAL High POWER 2.2.1.7 3.3.1.1 Reactor Vessel Steam Dome Pressure High s 1 D87 psig 2.2.1.8 3.3.1.1 Reactor Vessel Water Level - Low, Level 3 2 13. 0 inches(a) 2.2.1.9 3.3.1.1 Main Steam Isolation Valve - Closur-e,,; 1 CJ% closed 2.2.1.10 This section is not used.

2.2.1.11 3.3.1.1 Drywell Pressure - High s 1.72 psig 2.2.1.12 3.3.1.1 Scram Discharge Volume Water Level s 65 gallons High - Level Transmitter

• 2.2.1.13 3,3.1.1 Scram Discharge Volume Water Level - :s: 61 gallons High Heat Switch 2.2.1.14 3.3.1.1 Turbine Stop Valve - Closure 5.5% closed 2.2.1.15 3.3.1.1 Turbine Control Valve Fast Closure, Trip ? 500 psig Oil Pressure - Low

M See Figure 2.2-1 (b) For singlG loop operation, !:le value of 6.W 8 7

• • SUSQUEHANNA - UNIT 2 TRM / 2.0-6 Instrument Trip Setpoint Program Rev. 13 2.2

• TABLE 2.2-1 (Page 2 of 8)

INSTRUMENTATION SETPOINTS

SYSTEM/REFERENCE LCO [TRO] TRIP FUNCTION TRIP SETPOINT

2.2.1.16 OPRM Instrumentation

2.2.1.16.1 3.3.1.1 Sp PBA Amplitude Trip See COLR - TRO 3.2 2.2.1.16.2 3.3.1.1 Np PBA Successive Confirmation Count Trip See COLR - TRO 3.2 2.2.1.16.3 [3.3.9] TOL (E) Period Tolerance 0.10 sec 2.2.1.16.4 [3.3.9] fc Conditioning Filter Cutoff Frequency 1.50 Hz 2.2.1.16.5 [3.3.9] Tmin Oscillation Period Lower Time Limit 1.00 sec 2.2.1.16.6 [3.3.9] Tmax Oscillation Period Upper Time Limit 3.50 sec 2.2.1.16.7 [3.3.9] LPRMmin Minimum LRPMs/Cell Required for 2 Cell Operability 2.2.1.16.8 [3.3.9] S1 Peak Threshold Setpoint/ABA.& GRBA 1.20 2.2.1.16.9 {3.3.9] S2 Valley Threshold Setpoint/ABA & GRBA 0.85 2.2.1.16.10 [3.3.9] Smax Amplitude Trip Setpoint/ABA 1.50 2.2.1.16.11 [3.3.9] DR3 Growth Rate Factor Setpoint/GRBA 1.60

2.2.2 Isolation Actuation Instrumentation

2.2.2.1 Primary Containment Isolation

2.2.2.1.1 3.3.6.1 Reactor Vessel Water Level Low, Level 3 ~ 13.0 inches(aJ 2.2.2.1.2 3.3.6.1 Reactor Vessel Water Level Low Low, Level 2 ~ -38.0 fnches<a) 2.2.2.1.3 3.3.6.1 Reactor Vessel Water Level Low Low Low, ~ -129 inches(aJ Level 1 2.2.2.1.4 3.3.6.1 Drywell Pressure - High s 1.72 psig 2.2.2.1.5 3.3.6.1 SGTS Exhaust Radiation - High s 23.0 mR/hr 2.2.2.1.6 [3.3.6] Main Steam Line Radiation - High High s 15 x full power background without hydrogen injection

(a) See Figure 2.2-1.

• SUSQUEHANNA - UNIT 2 TRM /2.0-7 Instrument Trip Setpoint Program Rev. 13 2.2

TABLE 2.2-1 (Page 3 of 8)

INSTRUMENTATION SETPOINTS

SYSTEM/REFERENCE LCO [TRO] TRIP FUNCTION TRIP SETPOINT

2.2.2.2 Secondary Containment Isolation

2.2.2.2.1 3.3.6.2 Reactor Vessel Water Level - Low Low, 2 -38.0 inches<aJ Level2 2.2.2.2.2 3.3.6.2 Drywell Pressure - High :::;; 1.72 psig 2.2.2.2.3 3.3.6.2 Refuel Floor High Exhaust Duct Radiation - :::;; 18 mR/hr High 2.2.2.2.4 3.3.6.2 Railroad Access Shaft Exhaust Duct Radiation - :::;; 5 mR/hr High 2.2.2.2.5 3.3.6.2 Refuel Floor Wall Exhaust Duct Radiation - :::;; 21 mR/hr High

2.2.2.3 Main Steam Line Isolation

2.2.2.3.1 3.3.6.1 Reactor Vessel Water Level - Low Low Low, 2 -129 inches(a)

Level 1 2.2.2.3.2 3.3.6.1 Main Steam Line Pressure - Low 2 861 psig 2.2.2.3.3 3.3.6.1 Main Steam Line Flow - High :::;; 173 psid 2.2.2.3.4 3.3.6.1 Condenser Vacuum - Low 2 9.0 inches Hg vacuum 2.2.2.3.5 3.3.6.1 Reactor Building Main Steam Line Tunnel :::;; 177°F Temperature - High

• 2.2.2.3.6 This section is not used.

2.2.2.3.7 This section is not used.

2.2.2.3.8 This section is not used.

2.2.2.4 Reactor Water Cleanup System Isolation

2.2.2.4.1 3.3.6.1 Reactor Vessel Water Level - Low Low, ~ -38 inches(a)

Level2 2.2.2.4.2 3.3.6.1 RWCU.6. Flow - High :::;; 59 gpm 2.2.2.4.3 3.3.6.1 RWCU Flow - High :::;; 462 gpm 2.2.2.4.4 3.3.q.1 RWCU Penetration Area Temperature - High :::;; 131°F 2.2.2.4.5 This section is not used.

2.2.2.4.6 3.3.6.1 RWCU Pump Area Temperature - High :::;; 147°F 2.2.2.4.7 This section is not used.

2.2.2.4.8 3.3.6.1 RWCU Heat Exchanger Area Temperature - :::;; 147°F High 2.2.2.4.9 This section is not used.

(a) See Figure 2.2-1.

SUSQUEHANNA - UNIT 2 TRM / 2.0-8 Instrument Trip Setpoint Program Rev. 13 2.2

TABLE 2.2-1 (Page 4 of 8)

INSTRUMENTATION SETPOINTS

SYSTEM/REFERENCE LCO [TRO] TRIP FUNCTION TRIP SETPOINT

2.2.2.5 Reactor Core Isolation Cooling System Isolation

2.2.2.5.1 3.3.6.1 RCIC Steam Line t. Pressure - High s 138 inches H20 2.2.2.5.2 3.3.6.1 RCIC Steam Supply Line Pressure - Low 2 60 psig 2.2.2.5.3 3.3.6.1 RCIC Turbine Exhaust Diaphragm Pressure -s 10.0 psig High 2.2.2.5.4 3.3.6.1 RCIC Equipment Room Temperature - High s 167°F 2.2.2.5.5 3.3.6.1 RCIC Pipe Routing Area Temperature - High s 167°F 2.2.2.5.6 3.3.6.1 RCIC Emergency Area Cooler Temperature -s 167°F High 2.2.2.5.7 3.3.6.1 Drywell Pressure - High s 1.72 psig 2.2.2.5.8 This section is not used.

2.2.2.5.9 This section is not used.

2.2.2.6 High Pressure Coolant Injection System Isolation

2.2.2.6.1 3.3.6.1 HPCI Steam Linet. Pressure - High s 370 inches H20 2.2.2.6.2 3.3.6.1 HPCI Steam Supply Line Pressure - Low 2 104 psig 2.2.2.6.3 3.3.6.1 HPCI Turbine Exhaust Diaphragm Pressure -s 10 psig High

• 2.2.2.6.4 3.3.6.1 HPCI Equipment Room Temperature - High s 167°F 2.2.2.6.5 3.3.6.1 HPCI Emergency Area Cooler Temperature -s 167°F High 2.2.2.6.6 3.3.6.1 HPCI Pipe Routing Area Temperature - High s 167°F 2.2.2.6.7 3.3.6.1 Drywell Pressure - High s 1.72 psig 2.2.2.6.8 This section is not used.

2.2.2.6.9 This section is not used.

2.2.2.7 Shutdown Cooling/System Isolation

2.2.2.7.1 3.3.6.1 Reactor Vessel Water Level - Low, Level 3 2 13.0 inches<0 )

2.2.2.7.2 3.3.6.1 Reactor Vessel Steam Dome Pressure - High s 98 psig 2.2.2.7.3 [3.3.6] RHR Flow - High s 25,000 gpm

2.2.3 ECCS Actuation

2.2.3.1 Core Spray System

2.2.3.1.1 3.3.5.1 Reactor Vessel Water Level - Low Low Low, 2 -129 inches<a)

Level 1 2.2.3.1.2 3.3.5.1 Drywell Pressure - High s 1.72 psig 2.2.3.1.3 3.3.5.1 Reactor Vessel Steam Dome Pressure - Low 2 396.5, s; 428.5 psig injection permissive

(a) See Figure 2.2-1.

SUSQUEHANNA - UNIT 2 TRM / 2.0-9 Instrument Trip Setpoint Program Rev. 13 2.2

• TABLE 2.2-1 (Page 5 of 8)

INSTRUMENTATION SETPOINTS

SYSTEM/REFERENCE LCO [TRO] TRIP FUNCTION TRIP SETPOINT

2.2.3.2 LPCI Mode of RHR System

2.2.3.2.1 3.3.5.1 Reactor Vessel Water Level - Low Low Low, 2':: -129 inches(a)

Level 1 2.2.3.2.2 3.3.5.1 Drywell Pressure - High.s; 1.72 psig 2.2.3.2.3 3.3.5.1 Reactor Vessel Steam Dome Pressure - Low, :2: 396.5,.s; 428.5 psig injection permissive 2.2.3.2.4 3.3.5.1 Reactor Vessel Steam Dome Pressure - Low, :2: 236 psig, decreasing Recirculation Discharge Valve permissive

2.2.3.3 HPCI System

2.2.3.3.1 3.3.5.1 Reactor Vessel Water Level - Low Low, ::::: -38 inches(a)

Level2 2.2.3.3.2 3.3.5.1 Drywell Pressure - High s 1.72 psig 2.2.3.3.3 3.3.5.1 Condensate Storage Tank Level - Low 2':: 40.5 inches above tank bottom 2.2.3.3.4 3.3.5.1 Reactor Vessel Water Level - High, Level 8 s 54 inches

2.2.3.4 Automatic Depressurization System (ADS)

2.2.3.4.1 3.3.5.1 Reactor Vessel Water Level - Low Low Low, 2':: -129 inches

• Level 1 2.2.3.4.2 3.3.5.1 Drywell Pressure - High.s; 1.72 psig 2.2.3.4.3 3.3.5.1 ADS Timer :,;; 102 seconds 2.2.3.4.4 3.3.5.1 Core Spray Pump Discharge Pressure - High 2':: 135,.s; 155 psig 2.2.3.4.5 3.3.5.1 Low Pressure Coolant Injection Pump :2: 121,:,;; 129 psig Discharge Pressure - High 2.2.3.4.6 3.3.5.1 Reactor Vessel Water Level - Low, Level 3 13inches Confirmatory 2.2.3.4.7 3.3.5.1 ADS Drywell Pressure Bypass Timer s 420 seconds

2.2.3.5 Loss of Power - ECCS Actuation

2.2.3.5.1 4.16kv ESS Bus Undervoltage (Loss of Voltage< 20%)

2.2.3.5.1.1 3.3.8.1 Bus Undervoltage ~ 823.2,.s; 856.8 Volts 2.2.3.5.1.2 3.3.8.1 Time delay ::::: 0.4, s 0.6 seconds

(aJ See Figure 2.2-1.

SUSQUEHANNA - UNIT 2 TRM / 2.0-10 Instrument Trip Setpoint Program Rev. 13 2.2

• TABLE 2.2-1 (Page 6 of 8)

INSTRUMENTATION SETPOINTS

SYSTEM/REFERENCE LCO [TRO] TRIP FUNCTION Tf~IP SETPOINT

2.2.3.5.2 4 '.6kV ESS Bus Ur:dervoltage (Degraded Voltage< 65%)

2.2.3.5.2.1 3.3.8.1 Bus U11dervoltage 2641.1, s; 27 48.9 Volts 2.2.3.5.2.2 3.3.8.1 Time delay ~, 2.7, s; 3.3 seconds

2.2.3.5.3 4.16kV ESS Bus Undervoltage (Degraded Voltage, < 93%)

2.2.3.5.3.1 3.3.8.1 Bus Undervoltage ;:: 3829.3, s 3906.7 Vc!ts 2.2.3.5.3.2 3.3.8.1 Time Delay (Non-LOCA) ?: 4 minute, 30 seconds s 5 mir:ute. 30 seconds 2.2.3.5.3.4 3.3.8.1 Time Delay (LOCA) ;,: 9, s 11 seconds

2.2.3.5.4 480V ESS Bus 0B565 Undervoltage (Degraded Voltage, < 65%)

2.2.3.5.4.1 [3.8.5] 480V Basis ;:: 308 9 < 315.1 Vol:s 2.2.3.5.4.2 [3.8.5] Time Delay > 4.5, s; 5.5 seconds

2.2.3.5.5 480V ESS Bus 0B565 Undervoltage (Degraded Voltage,< 92%)

2.2.3.5.5.1 [3.8.5] 480V Basis ;:: 437.6. s; 446.4 Voits

• 2.2.3.5.5.2 [3.8.5] Time Delay 2 9. <: 11 seconds

2.2.4 ATV' S Alternate Rod Injection and Recirculation Pump Trip

2.2.4.1 3.3.4.2/[3.1.1] Reactor Vessel. Water Level - low Low, ;:,, -38 inches(a)

Level2 2.2.4.1 3. 3.4.2/[3.1.1] Reactor Vessel Steam Dome Pressure - High s 1135 psig

2.2.5 Er:d of Cycle Recirculation Pump Trip

2.2.5.1 3.3.4.1 Turbine Stop Valve-Closure s; 5.5% closed 2.2.5.2 3,3.4.1 Turbine Cor:tml Valve - Fast Closure 2c 500 psig

?..?..6 Reactor Core lso!atio:1 Cooling Sys:em Actuation

2.2.6.1 3.3.5.2 Reactor Vessel Wator Levo: - Low Low, ?: -38 inches(a)

Leve!2 2.2.6.2 3.3.5.2 Reactor Vessel Water Level - High, Level 8 ~ 54 inches(a) 2.2.6.3 3.3.5.2 Condensate Storage Tank Level - Low ~ 36.0 inches above tank bottom

(a) See Figure 2.2-1.

• -* SUSQUEHANNA - UNIT 2 TRM / 2.0-11 Instrument Trip Setpoint Program Rev. 13 2.2

• TABLE 2.2-1 (Page 7 of 8)

INSTRUMENTATION SETPOINTS

SYSTEM/REP[RENCE LCO [TRO] TRIP FUNCTION TRIP SETPOINT

2.2.7 Control Rod Block

2.2.7.1 Rod Block Monitor

2.2.7.1."l 3.3.2 Low Power Range - Upscale See COLR - TRO 3.2 3.3.2 Intermediate Power Range - Upscale See COLR - TRO 3.2 3.3.2 High Power Range - Upscale See COLR - TRO 3.2 2.2.7.1.2 3.3.2 Low Power Range Setpoint See COLR - TRO 3.2 3.3.2 Intermediate Power Range Setpoint See COLR - TRO 3.2 3.3.2 High Power Range Setpoint See COLR TRO 3.2

2.2.7.2 APRM

2.2.7.2.1 [3.1.3] Simulated Thermal Power-H'.gh - Two Loop 0.55 VV + 54.2%

Operation 22.7.2.2 [3.1.3] Simulated Thermal Power-High - Single Loop 0.55 (W - tiW) + 54.2%i 0l Operation 2.2.7.2.3 [3.1.3] Simulated Thermal Power-High Clamp 108% of RAI l::D THERM/\\L POWER 2.2.7.2.4 I3.1.3J Downscale 2:: 5% of RA TED THERMAL POWER 2.2.7.2.5 [3.1.3] Neutron Flux - High {Setdown) ~ 12% of RA.TE') THERMAL POWER

• 2.2. 7.3 Source Range Monitors

2.2.7.3.1 [3.1.3] Upscale s; 2E5 cps 2.2.7.3.2 [3.1.3] Downscale 2 3.0 cps(bl

2.2.7.4 Intermediate Range Monitors

2.2.7.4.1 [3. i.3] s; 108/125 divisions of full scale 2.2.7.4.2 (3.1.3] Downscale 2 5/125 divisions of full scale

2.2.7.5 Scram Discharge Volu:-ne

2.2.7.5.1 [3.1.3] Water Level - High ~; 35 9 gallons

2.2.7.6 Reactor Coolant System Recirculation Flow

2.2.7.6.1 [3.1.3] Upscale 114%

(bl With a signal-to-noise ratio 2 2, or within the limits of Figure 2.2-2.

(cJ For single loop operation, the valve of l:lW = 8.7.

• SUSQUEHANNA - UNIT 2 TRM / 2.0-12 Instrument Trip Setpoint Program Rev. 13 2.2

• TABLE 2.2-1 (Page 8 of 8)

INSTRUMENTATION SETPOINTS

SYSTEM/REFERENCE LCO [TRO] TRIP FUNCTION TRIP SETPOINT

2.2.8 CREOASS

2.2.8.1 3.3.7.1 Main Control Room Outside /\\'r Intake ::.: 5 mR/hr Radiation Monitor

?..?..8.1.1 3.3.7.1 Reactor Vessel Water Level - Low Low, ? -38.0 inches(a)

Level2 2.2.8.1.2 3.3.7.1 Drywell Pressure - High <:, 1.72 psig 2.2.8.1.3 3.3.7.1 Refuel Floor High Exhaust Duct <:,1SmR/hr Radiation - High 2.2.8.1.4 3.3.7.1 Railroad Access Shaft Exhaust Duct Radiation :c, 5 mR/hr

-High 2.2.8.1.5 3.3.7.1 Refuel Floor Wall Exhaust Duct <:, 21 mR/hr Radiation - High

2.2.9 Feedwater/Main Turbine Trip System Actuation

2.2.9.1 3.3.2.2 Reactor Vessel Level - High <::, 54.0 inches(a)

2.2.10 MVP Isolation

2.2.10.1 [3.3.11] Main Steam Line Radiation - High High ~ 15 x full power background without hydrogen injection

(a) Seo Figure 2.7.-1

• • • SUSQUEHANNA UNIT 2 TRM / 2.0-13 Instrument Trip Setpoint Program Rev. 13 2.2

WATER LEVEL N MENCLATIJRE HEIGHT AB VE 800 N. VESSEL ZER READING (IN.)

(8) 581. 5 +54 (7) 566,5 +39 (4) 557. 5 +30 (3) 540.5 +13 (2) 489,5 -38

( 1) 398.5 -129

658,5-MAIN STEAM LINE RANGE WIDE r--NARR U RANGE--,

581.5 (8) +60 +60-+60-;:r.:+601 566, 5 (7) C 9> 54 < 7) 39 HI ALARM 557. 5 (4) HPCI &(4:r30 Lil ALARM B TTIJM IJF STEAM 540. 5 < 3) INSTRUMEN O-O TRIPS <i 13 RCIC ~

DRYER SKIRT 527.5 ZERO FEED 498. 5 -38 SCRAM REACT WATER CIJNTRIBUTE (2) INITIATE RCIC, T ADS 450 HPCI, ARI TRIP RECIRC PUMPS

400 398. 5 C 1) -129 (1) INITIATE RHR, CS 366. 7 START DIESEL

• 350 -150 C NTRIBUTE TO ADS CL SE MSIV'S

300 ACTIVE FUEL

250.,~J

RECIRC 161, 5 UTLET NOZZLE

100

50 NOTE* SCALE IN INCHES AB VE VESSEL ZER

REACTOR VESSEL WATER LEVEL FIGURE 2, 2-1

SUSQUEHANNA - UNIT 2 TRM / 2.0-14 Instrument Trip Setpoint Program Rev.13 2.2

Instrument Trip Setpoint Table 2.2

3 2.8

2.6

2.4 2.2 \\

2 \\

{/) \\

-- 1.8 Q.

..._,, 1.6 0 '

w \\

~ Acceptable a:::: 1.4 I-1.2 \\,

z

.0 :::,

' (.) 1 "' ~ -. ~ r---__

• *~ 0.8

{/)

0.6 Not Acceptable 0.4 0.2

0 2 6 10 14 18 22 26 30

Signal-to-Noise Ratio

Figure 2.2-2 Minimum SRM Trip Setpoint Versus Signal-to-Noise Ratio

SUSQUEHANNA - UNIT 2 TRM / 2.0-15 TRM Isolation Actuation Instrumentation Rev. 6 3.3.6

• 3.3 Instrumentation

3.3.6 TRM Isolation Actuation Instrumentation

TRO 3.3.6 The TRM containment isolation instrumentation for each Function in Table 3.3.6-1 shall be OPERABLE.

APPLICABILITY: As specified in Table 3.3.6-1

ACTIONS

---

NOTES-------------

1. Penetration flow paths isolated to comply with Action C may be unisolated intermittently under administrative controls.

2. Separate Condition entry is allowed for each channel.

CONDITION REQUIRED ACTION COMPLETION TIME A One or more required A.1 Place channel in trip. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> for channels inoperable Function 2.a

AND.

24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> for Functions other than Function 2.a

B. One or more Functions with B.1 Restore isolation capability. 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> isolation capability not maintained.

C. Required Action and C.1 Initiate appropriate 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> associated Completion compensatory measures for Time of Condition A or B the degraded condition.

not met.

(continued)

SUSQUEHANNA - UNIT 2 TRM /3.3-13 TRM Isolation Actuation Instrumentation Rev. 6 3.3.6 TECHNICAL REQUIREMENT SURVEILLANCE

---

NOTES-----------------------

1. Refer to Table 3.3.6-1 to determine \\Alhich TRSs apply for each TRM Isolation Actuation Instrumentation Function.

2. When a channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated Conditions and Required Actions may be delayed for up to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> provided the associated function maintains isolation capability.

SURVEILLANCE FREQUENCY

TRS 3.3.6.1 Perform CHANNEL CHECK 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />

TRS 3.3.6.2 Perform CHANNEL FUNCTIONAL TEST 92 days

TRS 3.3.6.3 Perform CHANNEL CALIBRATION 92 days

TRS 3.3.6.4 Peliorm CHANNEL CALIBRATION 24 months

TRS 3.3.6.5 Perform LOGIC SYSTEM FUNCTIONAL TEST 24 months

TRS 3.3.6.6 Perform RESPONSE TIME TEST 24 months on a

• staggered test basis

( continued)

• • SUSQUEHANNA - UNIT 2 TRM / 3.3-14 TRM Isolation Actuation Instrumentation Rev.6 3.3.6 TABLE 3.3.6-1 PRIMARY CONTAINMENT ISOLAT!ON INSTRUMENTATION

APPLICABLE MODES OR REQUIRED OTHER CHANNELS PER SURVEILLANCE SPECIFIED FUNCTION CONDITIONS TRIP SYSTEM REQUIREMENTS ALLOWABLE VALUE

1. Dele:ed

2. Primary Containment Isolation

a. Main Steam Line 1,2,3 2 TRS 3.3.6.1,,; 21 x full power Radiation High TRS 3.3.6.2 background without High TRS 3.3.6.4 hydrogen injection TRS 3.3.6.5 TRS 3.3.6.6(a)

3. Shutdown Cooling System Isolation (hl

a. RHR Flow - High 3,4(c),5(c) 1 (cl) TRS 3.3.6.1 s: 26,000 gpm TRS 3.3.6.2 TRS 3.3.6.4 TRS 3.3.6.5

(a) Radiation detectors are exempt from response time testing.

(b) Not req:.iired when the penetration is isolated from the reactor vessel via manual isolation valve, blind flange, or deactivated auto isolation valve.

(c) ReqLli,ed in Modes 4 and 5 when automatic isolation of the associated penetration flow path is credited in calculating DRAIN THv1E per LCO 3.5.2..

(d) Wnen required in Modes 4 and 5, only one trip system is required.

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e

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SUSQUEHANNA - UNIT 2 TRM / 3.3-16 TRM Isolation Actuation Instrumentation Rev. 7 B 3.3.6

• *B 3.3.6 TRM Isolation Actuation Instrumentation

BASES

TRO The TRM Actuation instrumentation automatically initiates closure of appropriate primary containment isolation valves (PCIVs). The function of the PCIVs, in combination with other accident mitigation systems, is to limit fission product release during and following postulated Design Basis Accidents (DBAs) (Reference 1). The TRM Isolation Actuation Instrument has been relocated from the Technical Specifications because the identified Function is not credited in the plant design basis to mitigate any plant event, but does provide a diverse means to initiate an Isolation Actuation.

The isolation instrumentation includes the sensors, relays, and instruments that are necessary to cause initiation of primary containment and Reactor Coolant Pressure Boundary (RCPB) isolation. When the setpoint is reached, the sensor actuates, which*then outputs an isolation signal to the isolation logic. Monitoring a wide range of independent parameters provides functional diversity. The input parameters to the isolation logic are:

(a) Main steam line radiation, and

(b) RHR Flow - High.

The RHR high flow isolation is only applicable to the RHR suction side piping; it will not detect smaller branch size breaks or breaks on the discharge side of the RHR pump.

The valves associated with these trip channels are identified in Table B 3.3.6-

1. Each of these valves is also associated with other trip channels as identified in LCO ~ases B 3.6.1.3.

The trips occur after a one second delay. See Tech Spec Basis B 3.3.6-1.

(continued)

SUSQUEHANNA - UNIT 2 TRM / B 3.3-10 TRM Isolation Actuation Instrumentation Rev. 7 B 3.3.6

• BASES

ACTIONS The Actions are defined to ensure proper corrective measures are taken in response to the inoperable components. The ACTIONS are modified by hNo Notes. Note 1 allows penetration flow path(s) to be unisolated intermittently under administrative controls. These controls consist of stationing a dedicated operator at the controls of the valve, who is in continuous communication with the control room. In this way, the penetration can be rapidly isolated when a need for primary containment isolation is indicated.

Note 2 is provided to modify the ACTIONS for separate Condition entry, consistent with similar Note in the TS 3.3.6.1 Actions.

Condition C applies if the channel is not restored to OPERABLE status or placed in trip, or isolation capability is not restored, within the allowed Completion Time. If inoperable channels should not be placed in trip (e.g., might result in a undesirable transient) Action C may be intentionally entered as a result of not meeting Required Action A.1 in its required Completion Time. Required Action C.1 requires appropriate compensatory measures be in place within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. Examples of appropriate compensatory measures may consist of verifying that diverse isolation functions remain OPERABLE. Furthermore, isolating the penetration (e.g.,

as may be required by TS Actions for an inoperability affecting both the TRM Function and a required TS Function) also provides adequate compensatory actions since isolating the affected penetration flow path(s) accomplishes the

• safety function of the inoperable channels. If it is not desired to isolate the affected penetration flow path(s) (e.g., as in the case where isolating the penetration flow path(s) could result in a reactor scram or disabling RHR SDC), alternate compensatory measures should be pursued. The 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> Completion Time is acceptable due to the fact that these Functions are not assumed in any accident or transient analysis in the FSAR.

TRS The TRSs are defined to be performed at the specified Frequency to ensure that the TRM. Isolation Actuation Instrumentation Functions are maintained OPERABLE. TRM Isolation Actuation Instrumentation Surveillances are performed consistent with the Bases for LCO 3.3.6.1 "Isolation Activation Instrumentation."

(continued)

SUSQUEHANNA - UNIT 2 TRM / B 3.3-11 TRM Isolation Actuation Instrumentation Rev. 7 B3.3.6

• BASES

TRS TRS 3.3.6.5 (continued)

The LOGIC SYSTEM FUNCTIONAL TEST demonstrates the OPERABILITY of the required isolation logic for a specific channel. The system functional testing performed on PCIVs in LCO 3.6.1.3 overlaps this surveillance to provide complete testing of the assumed safety function. The 24 month Frequency is based on the need to perform portions of this surveillance under the conditions that apply during a plant outage and the potential for an unplanned transient if the surveillance were performed with the reactor at power. Operating experience has shown these components usually pass the surveillance when performed at the 24 month Frequency.

TRS 3.3.6.6

The response time testing of Function 2.a is per FSAR Table 7.3-29.

REFERENCES 1. FSAR Section 7.3.1

2. NRG Inspection and Enforcement Manual, Part 9900: Technical Guidance, standard Technical Specification Section 1.0 Definitions, Issue dated 12/8/96.

SUSQUEHANNA - UNIT 2 TRM / 8 3.3-12 TRM Isolation Actuation Instrumentation Rev. 7 B 3.3.6

• Tabie B 3.3.6~1

Primary Containment Isolation Valves (Page 1 of 1)

Plant systems Valve Number Valve Description Isolation Signal Function No.

(Table 3.3.6-1)

Reactor HV-243F019 Reactor Coolant Sample Valve 2.a Recirculation HV-243F020 Reactor Coolant Sample Valve 2.a RHR HV-251F022 RHR - Reactor Vessel Head Spray Valve 3.a HV-251F023 RHR - Reactor Vessel Head Spray Valve 3.a HV-251F008 RHR - Shutdown Cooling Valve 3.a HV-251F009 RHR - Shutdown Cooling Valve 3.a

SUSQUEHANNA - UNIT 2 TRM / B 3.3-13