ML23195A033
| 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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- MANUAL HARD COPY DISTRIBUTION DOCUMENT TRANSMITTAL 2023-9702
~SER INFORMATION:
GERLACH*ROSEY M EMPL# : O2 8 4 O1 CA# : 03 63 l\ddres~;: NUCSA:~
Phone#: 542-3194 TRANSMITTAL INFORMATION:
TO: 06/30/2023 LOCATION: USNRC FROM: 1\JCLEAR RECORDS DOCUMENT CONTROL CENTER (NUCSA-2)
THE FOLLOWING CHANGES HAVE OCCURRED TO THE HARDCOPY OR ELECTRON:C MANUAL ASSIGNED TO YOU. }Lil..RDCOPY USEES MUST E'.\JSURE THE DCC1J'.VJENTS PRCVIDED MATCH THE INFOR!V:ATION ON THIS TRJ>.::,JSMITTAL. WlIEN REl?LACI:'..\G THIS M.t'\.TERlAL IN YO'.J.?_ Hl\.J.-WCOPY MANUAL, J:<;NSURE THE UPDATE DOCUMENT ID IS THE SAME DOCUMENT ID YOU' RE RE:'IOVING FROM YOUR MANUAL. TOOLS tlllkoM THE HUMAN PERFORMANCE TOOL BAG SHOULD BE UTILIZED TO ELIMI~ATE THE CHANCE OF
-..rRRORS.
A'l"l'ENTlC~(: "REPLACE" directions do not affect the Tal,le of Contents, Therefore no TOC will Le ifJflUed wit:1 the updatPd materi o.l.
TRM2 - TECHNICAL REQUIREMENTS :v'AEUAL UNIT 2 REMOVE f'll\..i.\.TUAL TABLE 0.? CONTENTS DATE: 03/30/2023 ADD l\'L:D..J\'UAL TABLE CF CONTENTS DATE: 06/29/2023 CA'l'EGOEY: DOCUMENTS TYPE: TRM'.<
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- ID: TEXT 2.2 REMOVE: RP.V: 12 ADD: 2EV: 13 CATEGORY: DOCUMENTS ~YPE: TRM2 ID: TEXT 3.3.6 ADD: REV: 6 REMOVE: REV:5 CATEGORY: DOCUMENTS TYPE: TRM2 ID: TEXT H3.3.6 ADD: REV: 7 REMOVE: REV:6 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 CORDANCE WITH DEPARTMENT PROCEDURES. PLEASE MAKE ALL CHANGES F~\D ACKNOWLEDGE MPLETE IN YOUR NI~S INBOX UPON COMPLETION OF UPDATES. FOR ELECTRONIC MMuAL USERS, ELECTRONICALLY REVIEW TEE APPROPRIATE DOCUMENTS AND ACKNOWLEDGE COMPLETE IN YOUR NliV:S INHOX .
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 ,.;...:......._
I
Title:
TABLE OF CONTENTS
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' *~.,,
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
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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 SEISi1,: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 TEXT 3.3.7 6
1 06/29/2023
Title:
INSTRUME:-JTATION TRM ISOLATION ACTUATION INSTRUMENTATION 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
Title:
PLANT SYSTEMS CO2 SYSTEMS TEXT 3.7.3.4
Title:
PLANT SYSTEMS HALON SYSTEMS 4
2 05/16/2016 C*'.l/16/2009 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
Title:
REFUELING OPERATIONS DECAY TIME TEXT 3.9.2 0
0
Title:
REFUELING OPERATIONS COMMUNICATIONS ll/19/2002 11;* 9/2002 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 04 0 9 / 2 0 07
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 TEXT B3.2.1 AND CHECK VALVE 1
0 10/12/2020
Title:
REACTIVITY CONTROL SYSTEM BASES CONTROL ROD SCRAM ACCUMULATORS INSTRUMENTATION 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
Title:
WATER MONITORING INSTRUMENTATION 0'c/Cl2/2019 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
- 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 TEXT B3.6.3 INDICATION 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 B3 . 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:
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RADIOACTIVE EFFLUENTS BASES LIQUID RADWASTE EFFLUENT MONITORING INSTRUMENTATION TEXT B3 . 11. 1. 5 0 11/19/2002
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RADIOACTIVE EFFLUENTS BASES RADIOACTIVE LIQUID PROCESS MONITORING INSTRUMENTATION TEXT B3.11.2.1 1 12/14/2004
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RADIOACTIVE EFFLUENTS BASES DOSE RATE Page 14 of 15 Report Date: 06/30/23
SSES MANUAL
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TECHNICAL REQUIREMENTS MANUAL UNIT 2 TEXT B3.ll.2.2 0 11/19/2002
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RADIOACTIVE EFFLUENTS BASES DOSE - NOBLE GASES TEXT B3 . 11. 2 . 3 0 11/19/2002
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TEXT B3.12.1 1 10/04/2007
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LOADS CONTROL PROGRAM BASES CRANE TRAVEL-SPENT FUEL STORAGE POOL TEXT B3.12.2 1 12/03/2010
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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 2.2 PLANT PROGRAMS AND SETPOINTS 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 HATi::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 1D87 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 ,,; 1CJ% 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 87
- 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 2.2.3.4.1 2.2.3.4.2 2.2.3.4.3 2.2.3.4.4 Automatic Depressurization System (ADS) 3.3.5.1 3.3.5.1 3.3.5.1 3.3.5.1 Reactor Vessel Water Level - Low Low Low, Level 1 Drywell Pressure - High ADS Timer Core Spray Pump Discharge Pressure - High 2':: -129 inches
.s; 1.72 psig
- ,;; 102 seconds 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 2.2.3.5.5.1 2.2.3.5.5.2 2.2.4 480V ESS Bus 0B565 Undervoltage (Degraded Voltage,< 92%)
ATV'S
[3.8.5]
[3.8.5]
480V Basis Time Delay Alternate Rod Injection and Recirculation Pump Trip
- 437.6. s; 446.4 Voits 2 9. <
- 11 seconds 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 RATED 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 NMENCLATIJRE HEIGHT ABVE 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 r--NARRU RANGE--,
WIDE 581.5 (8) +60 +60-+60-;:r.:+601 566, 5 (7) C9> 54 <7) 39 HI ALARM 557. 5 (4)
HPCI &(4:r30 Lil ALARM BTTIJM IJF STEAM 540. 5 <3) INSTRUMEN O-O TRIPS RCIC <i ~ 13 DRYER SKIRT 527.5 ZERO REACT FEED 498. 5 -38 SCRAM WATER CIJNTRIBUTE (2) INITIATE RCIC, T ADS 450 HPCI, ARI TRIP RECIRC PUMPS
- 400 350 300 366. 7 398. 5 C1)
ACTIVE FUEL
-150
-129 (1) INITIATE RHR, CS START DIESEL CNTRIBUTE TO ADS CLSE MSIV'S 250
.,~J RECIRC 161, 5 UTLET NOZZLE 100 NOTE* SCALE IN INCHES 50 ABVE VESSEL ZER FIGURE 2, 2-1 REACTOR VESSEL WATER LEVEL 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.
0 w
1.6 '\
~
a:::: 1.4 Acceptable
\,
I-z 1.2
.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 3.3.6 Instrumentation 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.
- A CONDITION One or more required channels inoperable A.1 REQUIRED ACTION Place channel in trip.
COMPLETION TIME 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> for 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 3.3.6 Rev. 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 OTHER REQUIRED SPECIFIED CHANNELS PER SURVEILLANCE 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 1(cl)
- a. RHR Flow - High 3,4(c),5(c) 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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TRM Isolation Actuation Instrumentation Rev.6 3.3.6
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TRM Isolation Actuation Instrumentation Rev. 7 B 3.3.6
- *B 3.3.6 BASES TRM Isolation Actuation Instrumentation 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)
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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)
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TRM Isolation Actuation Instrumentation Rev. 7 B3.3.6
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.
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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