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{{#Wiki_filter:ACCEREGULATORY NFORMATION DISTRIBUTION SYTEM(RNNBRNB107210416 DOCIDS)FACILE:50'15 DonaldC~CookN'4107/15NOTAR'xcKD)
{{#Wiki_filter:ACCE REGULATORY NFORMATION DISTRIBUTION SY TEM (R N NBRNB107210416 DOC IDS)FACILE:50'15 Donald C~Cook N'4 1 07/15 NOTAR'xcKD)
NO50316DonaldCCk.N,owerPlantiUnitfrIndianaS,p5H.NAME<AUTHORAFFILIATION:
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Indiana L Michi an DENTON O'o N I Of f ice of Nuclear Reactor" R l ti egu a onr Director~SUBJECT':." Forwards info rei enginee'ring, descri ba k o d i fo details for=reactor" vessel e c or" vessel hea ventsrfn response, to NUREG DISTRIBUTIO N CODE~)A046S COPIKS RECElIVED:
SUBJECT':."
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02'1 INPOrJ EST'ARNES NSIC 04 A/D CS S'NG 22'/D GEN PROJ 31 A/D MLQ ENG 23 A/D PLANT SYS25 A/D SAFETY AS17 D.IR'r EM=PREP 33 DIRECTOR'p DHF S2 8 DIRECTOR'g DSI 24 EMERG PREP DEV FKMA<<REP DIV OELD PDR EG F COPIKS LTTR>>ENCL<1 1=1 1 1 1 1 1 1 1 1.1>>l.1~1 1 1 1=0 1 1 f 1 1 1 ,-)ak'g~g gl TOTAL NUMBERS OF COPIES REQUIR ED j-" LiTTR 5 ENCL I"'~<<rtlj4~jW.~'" fbi<<I 0~I I I I lb'I 4~kjbC<<l',',I t'I~<<bI II<<I 41 l b<~It I W gb I~'I I"~'I I"I I<<14 I<<I I~I iW*~<<g~, I<<rt W'$4 N W i'I'1<<<<W q jtW ltt f'W C t<<1 Cq N C,t f I<<'I v p b II INDIANA L MICHIGAN ELECTRIC COMPANY P.O.BOX 18 BOWLING GREEN STATION NEW YORK, N.Y.10004 July 15, 1981 AEP:NRC:0584 Donald C.Cook Nuclear Plant Unit Nos.1 and 2 Docket Nos.50-315 and 50-316 License Nos.DPR-58 and DPR-74 NUREG-0737; ITEM II.B.1-REACTOR COOLANT SYSTEM VENTS Mr.Harold R.Denton, Director Office of Nuclear Reactor Regulation U.S.Nuclear Regulatory Commission Washington, D.C.20555  
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02'1INPOrJEST'ARNES NSIC04A/DCSS'NG22'/DGENPROJ31A/DMLQENG23A/DPLANTSYS25A/DSAFETYAS17D.IR'rEM=PREP33DIRECTOR'p DHFS28DIRECTOR'g DSI24EMERGPREPDEVFKMA<<REPDIVOELDPDREGFCOPIKSLTTR>>ENCL<11=111111111.1>>l.1~1111=011f111,-)ak'g~gglTOTALNUMBERSOFCOPIESREQUIREDj-"LiTTR5ENCL I"'~<<rtlj4~jW.~'"fbi<<I0~IIIIlb'I4~kjbC<<l',',It'I~<<bIII<<I41lb<~ItIWgbI~'II"~'II"II<<14I<<II~IiW*~<<g~,I<<rtW'$4NWi'I'1<<<<WqjtWlttf'WCt<<1CqNC,tfI<<'IvpbII INDIANALMICHIGANELECTRICCOMPANYP.O.BOX18BOWLINGGREENSTATIONNEWYORK,N.Y.10004July15,1981AEP:NRC:0584 DonaldC.CookNuclearPlantUnitNos.1and2DocketNos.50-315and50-316LicenseNos.DPR-58andDPR-74NUREG-0737; ITEMII.B.1-REACTORCOOLANTSYSTEMVENTSMr.HaroldR.Denton,DirectorOfficeofNuclearReactorRegulation U.S.NuclearRegulatory Commission Washington, D.C.20555


==DearMr.Denton:==
==Dear Mr.Denton:==
Thisletteranditsattachments documenttheengineering description, testprocedures, background information, genericoperating guidelines andsupporting detailsforthereactorvesselheadventsbeinginstalled inbothUnitsoftheDonaldC.CookNuclearPlant.Morespecifically, theattachments tothislettercontainthefollowing information:
This letter and its attachments document the engineering description, test procedures, background information, generic operating guidelines and supporting details for the reactor vessel head vents being installed in both Units of the Donald C.Cook Nuclear Plant.More specifically, the attachments to this letter contain the following information:
Attachment 1:Abriefdescription ofthedesign,operation andtestingrequirements Attachment 2:Attachment 3:Background Information forPressurizer VentingOperation-Rev.0,datedMarch1981.sPressurizer VentingOperation
Attachment 1: A brief description of the design, operation and testing requirements Attachment 2: Attachment 3: Background Information for Pressurizer Venting Operation-Rev.0, dated March 1981.s Pressurizer Venting Operation-Rev.0, dated March 1981.Attachment 4: Background Information for Reactor Head Vent Operation-Rev.0,, dated February 1981.Attachment 5: Reactor Vessel Head Vent Operation-Rev.0, dated February 1981.810721 0416 810715 I PDR ADQCK 05000315 P PDR (/(  
-Rev.0,datedMarch1981.Attachment 4:Background Information forReactorHeadVentOperation-Rev.0,,datedFebruary1981.Attachment 5:ReactorVesselHeadVentOperation
-'T I J V>I I)J' Mr.'arold R.Denton AEP:NRC:0584 Attachment 6: The following Supporting Information is attached: a)Suggested Technical Specifications.
-Rev.0,datedFebruary1981.8107210416810715IPDRADQCK05000315PPDR(/(  
b)Flow Diagram of the Reactor Head Vent System (Figure 1).c)d)Flow Diagram of the Pressurizer Vent System (Figure 2).Logic Diagram (Figure 3).e)Elementary Wiring Diagram 6.Formal submittal of Technical, Specifications'will take place once, the sys-tem design is finalized.
-'TIJV>II)J' Mr.'arold R.DentonAEP:NRC:0584 Attachment 6:Thefollowing Supporting Information isattached:
Westinghouse report WCAP-9600,"Report on Small Break Accidents for Westinghouse NSSS System", June 1979, Section 3.9 has been used as.a reference in developing the design of the vent system.This information is provided as requested in Item II.B.l of NUREG-0737.The Reactor Coolant System Venting Systems at the Cook Plant will be implemented by the required date of July 1, 1982.Very truly yours,.S.unter Vice President cc: John E.Dolan-Columbus R.C.Callen G.Charnoff R.W.Jurgensen D.V.Shaller-Bridgman Joe Williams, Jr.Region III Resident Inspector-Bridgman f I l'I ATTACHMENT 1 TO AEP:NRC:05 Descr i tion of Desi n The reactor Coolant Vent System is comprised of the Reactor Head Vent System and the Pressurizer Vent System.It has been designed to vent a volume of Hydrogen approximately equal to one-half of the re-actor coolant system volume in one hour at system design pressure and temperature, Each of these subsystems consists of two parallel flow paths.'." one inch in size, with redundant isolation valves in each flow path.A 3/8" orifice has been installed upstream of the isolation valves to limit the flow in the case of a break downstream of the orifices to within the capacity of;-one centrifugal charging pump.A break of an RCS Vent Line upstream of, the orifices would result in a small LOCA not greater than.one inch in diameter.This type of break has been analyzed in WCAP-9600 (Reference 1)and would behave similarly to the hot leg break presented.in this report.Therefore a break in the vent line would not result in.a calculated core uncover.A locked open hand valve will be installed upstream of the 3/8" orifices.The isolation valves are D.C.powered, fail closed, solenoid valves with stem position switches.These valves can be operated from.'he control.room..They will be no@nally closed during plant operation.
a)Suggested Technical Specifications.
b)FlowDiagramoftheReactorHeadVentSystem(Figure1).c)d)FlowDiagramofthePressurizer VentSystem(Figure2).LogicDiagram(Figure3).e)Elementary WiringDiagram6.Formalsubmittal ofTechnical, Specifications'will takeplaceonce,thesys-temdesignisfinalized.
Westinghouse reportWCAP-9600, "ReportonSmallBreakAccidents forWestinghouse NSSSSystem",June1979,Section3.9hasbeenusedas.areference indeveloping thedesignoftheventsystem.Thisinformation isprovidedasrequested inItemII.B.lofNUREG-0737.TheReactorCoolantSystemVentingSystemsattheCookPlantwillbeimplemented bytherequireddateofJuly1,1982.Verytrulyyours,.S.unterVicePresident cc:JohnE.Dolan-ColumbusR.C.CallenG.CharnoffR.W.Jurgensen D.V.Shaller-BridgmanJoeWilliams, Jr.RegionIIIResidentInspector
-Bridgman fIl'I ATTACHMENT 1TOAEP:NRC:05 DescritionofDesinThereactorCoolantVentSystemiscomprised oftheReactorHeadVentSystemandthePressurizer VentSystem.IthasbeendesignedtoventavolumeofHydrogenapproximately equaltoone-halfofthere-actorcoolantsystemvolumeinonehouratsystemdesignpressureandtemperature, Eachofthesesubsystems consistsoftwoparallelflowpaths.'."oneinchinsize,withredundant isolation valvesineachflowpath.A3/8"orificehasbeeninstalled upstreamoftheisolation valvestolimittheflowinthecaseofabreakdownstream oftheorificestowithinthecapacityof;-onecentrifugal chargingpump.AbreakofanRCSVentLineupstreamof,theorificeswouldresultinasmallLOCAnotgreaterthan.oneinchindiameter.
ThistypeofbreakhasbeenanalyzedinWCAP-9600 (Reference 1)andwouldbehavesimilarly tothehotlegbreakpresented
.inthisreport.Therefore abreakintheventlinewouldnotresultin.acalculated coreuncover.Alockedopenhandvalvewillbeinstalled upstreamofthe3/8"orifices.
Theisolation valvesareD.C.powered,failclosed,solenoidvalveswithstempositionswitches.
Thesevalvescanbeoperatedfrom.'hecontrol.room..Theywillbeno@nallyclosedduringplantoperation.
Indicating
Indicating
'hghtswillbeinstalled inthecontrolroomsotheoperators willknowtnevalveposition.
'hghts will be installed in the control room so the operators will know tne valve position.These valves will be qualified to IEEE-323-1974, IEEE-344-1975 an'd IEEE-383-1972.
Thesevalveswillbequalified toIEEE-323-1974,IEEE-344-1975 an'dIEEE-383-1972.
RTD assemblies have been added downstream of the solenoid valves to detect leakage through these valves..These RTD"ssemblies will set off an alarm in the control room if leakage through the valves should occur..The reactor vessel head vent connects to a part-length control rod drive mechanism housing located near the center of the reactor head.The pressurizer vent is connected to the pressurizer relief line.The possibility of reactor coolant pressure boundary leakage is minimized because of the two isolation valves in series.Isolation valves in one flow path are powered by Train A and the valves in the second flow path are powered by Train B.Both the reactor head vent and the pressurizer vent discharge into the upper volume of the.containment at approx.elevation 673'-0", in an area which will provide adequate dilution of any combustible gas. All piping and equipment used in the reactor head vent from the part-length rod housing to the orifices and all piping and equipment used in the pressurizer vent from the pressurizer relief piping to the orifices are designed in accordance with ASME, Section III Class 1 requirements.
RTDassemblies havebeenaddeddownstream ofthesolenoidvalvestodetectleakagethroughthesevalves..TheseRTD"ssemblies willsetoffanalarminthecontrolroomifleakagethroughthevalvesshouldoccur..Thereactorvesselheadventconnectstoapart-length controlroddrivemechanism housinglocatednearthecenterofthereactorhead.Thepressurizer ventisconnected tothepressurizer reliefline.Thepossibility ofreactorcoolantpressureboundaryleakageisminimized becauseofthetwoisolation valvesinseries.Isolation valvesinoneflowpatharepoweredbyTrainAandthevalvesinthesecondflowpatharepoweredbyTrainB.Boththereactorheadventandthepressurizer ventdischarge intotheuppervolumeofthe.containment atapprox.elevation 673'-0",inanareawhichwillprovideadequatedilutionofanycombustible gas. Allpipingandequipment usedinthereactorheadventfromthepart-length rodhousingtotheorificesandallpipingandequipment usedinthepressurizer ventfromthepressurizer reliefpipingtotheorificesaredesignedinaccordance withASME,SectionIIIClass1requirements.
From the orifices up to the first anchor downstream of the second isolation valve the piping and equipment has been designed in accordance with ASME Section III Class 2 requirements.
Fromtheorificesuptothefirstanchordownstream ofthesecondisolation valvethepipingandequipment hasbeendesignedinaccordance withASMESectionIIIClass2requirements.
The remainder of the piping is designed to AEP Seismic Class 1 Level 4.~Testin The isolation valves used on the reactor head vent and pressurizer-vent will be tested in accordance with subsection IWV-3000 of ASME Section XI for Category B valves during refueling outages.~Otal P d The following procedures are attached and aregenerically applicable to the D.C.Cook Plant.1.Background Information for'Pressurizer Venting Operation-Rev.0 dated March 1981.2.Pressurizer Venting Oper ation-Rev.0 dated March 1981.3.Background Information for Reactor Head Vent Operation-Rev.0 dated February 1981.4.Reactor Vessel Head Vent Operation-Rev.0 dated February 1981.References 1.WCAP-9600,"Report on Small Break Accidents for Westinghouse NSSS System," June 1979, (specifically Case.F Section 3.2).
Theremainder ofthepipingisdesignedtoAEPSeismicClass1Level4.~TestinTheisolation valvesusedonthereactorheadventandpressurizer-ventwillbetestedinaccordance withsubsection IWV-3000ofASMESectionXIforCategoryBvalvesduringrefueling outages.~OtalPdThefollowing procedures areattachedandaregenerically applicable totheD.C.CookPlant.1.Background Information for'Pressurizer VentingOperation
ATTACHMENT E T0 AEP:NRC:0584}}
-Rev.0datedMarch1981.2.Pressurizer VentingOperation-Rev.0datedMarch1981.3.Background Information forReactorHeadVentOperation
-Rev.0datedFebruary1981.4.ReactorVesselHeadVentOperation
-Rev.0datedFebruary1981.References 1.WCAP-9600, "ReportonSmallBreakAccidents forWestinghouse NSSSSystem,"June1979,(specifically Case.FSection3.2).
ATTACHMENT ET0AEP:NRC:0584}}

Revision as of 08:27, 6 July 2018

Forwards Info Re Engineering Description,Test Procedures, Background Info,Generic Operating Guidelines & Supporting Details for Reactor Vessel Head Vents,In Response to NUREG- 0737,Item II.B.1
ML17331A772
Person / Time
Site: Cook  American Electric Power icon.png
Issue date: 07/15/1981
From: HUNTER R S
INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To: DENTON H R
Office of Nuclear Reactor Regulation
Shared Package
ML17319A959 List:
References
RTR-NUREG-0737, RTR-NUREG-737, TASK-2.B.1, TASK-TM AEP:NRC:0584, AEP:NRC:584, NUDOCS 8107210416
Download: ML17331A772 (9)
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Text

ACCE REGULATORY NFORMATION DISTRIBUTION SY TEM (R N NBRNB107210416 DOC IDS)FACILE:50'15 Donald C~Cook N'4 1 07/15 NOTAR'xcKD)

NO 50 316 Donald C C k.N ,ower Planti Unit fr Indiana S, p5 H.NAME<AUTHOR AF FILIATION:

'g Uni t 2'z Indi ane L 05p0031 6 HUNTERrR>>.S<

Indiana L Michi an DENTON O'o N I Of f ice of Nuclear Reactor" R l ti egu a onr Director~SUBJECT':." Forwards info rei enginee'ring, descri ba k o d i fo details for=reactor" vessel e c or" vessel hea ventsrfn response, to NUREG DISTRIBUTIO N CODE~)A046S COPIKS RECElIVED:

TITLES=Response>>to NURKG<<0737 N:LiTR ENCL]'IZE: '~'NUREG<<0660 TMI Acti'P on'an Rgmts'OL's)

NOTESt-ILE'.3 copies" al 1 mat er el~en copies of all matet'ial to ILK', 05000315 05000316" RECIPIENT ID>>CODE'/NAMEI ACTION$: ORB 0 f BC05>>INTERNAL>A/D CS C;SYS 27 A/D>>FOR<TECH 32'.A/D LICENS>>16'/0 OP REACT 15>>A/D>>RAD PROT 26'EP'IRr DHFS 29.DIRECTORS'EE 2'1<DIRECTORS'Lt 14 DIRECTOR,DST 30.EMRG PRP LIC I LEI 12!OR ASSESS BR 18 RAD'SMT'R EXTERNALS ACRS LPDR 03>>>>VT'I S" COPIES I>>TTR ENCL(7 7 16 16 1-1 1 1.RECIPIENT ID CODE/NAME'.

02'1 INPOrJ EST'ARNES NSIC 04 A/D CS S'NG 22'/D GEN PROJ 31 A/D MLQ ENG 23 A/D PLANT SYS25 A/D SAFETY AS17 D.IR'r EM=PREP 33 DIRECTOR'p DHF S2 8 DIRECTOR'g DSI 24 EMERG PREP DEV FKMA<<REP DIV OELD PDR EG F COPIKS LTTR>>ENCL<1 1=1 1 1 1 1 1 1 1 1.1>>l.1~1 1 1 1=0 1 1 f 1 1 1 ,-)ak'g~g gl TOTAL NUMBERS OF COPIES REQUIR ED j-" LiTTR 5 ENCL I"'~<<rtlj4~jW.~'" fbi<<I 0~I I I I lb'I 4~kjbC<<l',',I t'I~<<bI II<<I 41 l b<~It I W gb I~'I I"~'I I"I I<<14 I<<I I~I iW*~<<g~, I<<rt W'$4 N W i'I'1<<<<W q jtW ltt f'W C t<<1 Cq N C,t f I<<'I v p b II INDIANA L MICHIGAN ELECTRIC COMPANY P.O.BOX 18 BOWLING GREEN STATION NEW YORK, N.Y.10004 July 15, 1981 AEP:NRC:0584 Donald C.Cook Nuclear Plant Unit Nos.1 and 2 Docket Nos.50-315 and 50-316 License Nos.DPR-58 and DPR-74 NUREG-0737; ITEM II.B.1-REACTOR COOLANT SYSTEM VENTS Mr.Harold R.Denton, Director Office of Nuclear Reactor Regulation U.S.Nuclear Regulatory Commission Washington, D.C.20555

Dear Mr.Denton:

This letter and its attachments document the engineering description, test procedures, background information, generic operating guidelines and supporting details for the reactor vessel head vents being installed in both Units of the Donald C.Cook Nuclear Plant.More specifically, the attachments to this letter contain the following information:

Attachment 1: A brief description of the design, operation and testing requirements Attachment 2: Attachment 3: Background Information for Pressurizer Venting Operation-Rev.0, dated March 1981.s Pressurizer Venting Operation-Rev.0, dated March 1981.Attachment 4: Background Information for Reactor Head Vent Operation-Rev.0,, dated February 1981.Attachment 5: Reactor Vessel Head Vent Operation-Rev.0, dated February 1981.810721 0416 810715 I PDR ADQCK 05000315 P PDR (/(

-'T I J V>I I)J' Mr.'arold R.Denton AEP:NRC:0584 Attachment 6: The following Supporting Information is attached: a)Suggested Technical Specifications.

b)Flow Diagram of the Reactor Head Vent System (Figure 1).c)d)Flow Diagram of the Pressurizer Vent System (Figure 2).Logic Diagram (Figure 3).e)Elementary Wiring Diagram 6.Formal submittal of Technical, Specifications'will take place once, the sys-tem design is finalized.

Westinghouse report WCAP-9600,"Report on Small Break Accidents for Westinghouse NSSS System", June 1979, Section 3.9 has been used as.a reference in developing the design of the vent system.This information is provided as requested in Item II.B.l of NUREG-0737.The Reactor Coolant System Venting Systems at the Cook Plant will be implemented by the required date of July 1, 1982.Very truly yours,.S.unter Vice President cc: John E.Dolan-Columbus R.C.Callen G.Charnoff R.W.Jurgensen D.V.Shaller-Bridgman Joe Williams, Jr.Region III Resident Inspector-Bridgman f I l'I ATTACHMENT 1 TO AEP:NRC:05 Descr i tion of Desi n The reactor Coolant Vent System is comprised of the Reactor Head Vent System and the Pressurizer Vent System.It has been designed to vent a volume of Hydrogen approximately equal to one-half of the re-actor coolant system volume in one hour at system design pressure and temperature, Each of these subsystems consists of two parallel flow paths.'." one inch in size, with redundant isolation valves in each flow path.A 3/8" orifice has been installed upstream of the isolation valves to limit the flow in the case of a break downstream of the orifices to within the capacity of;-one centrifugal charging pump.A break of an RCS Vent Line upstream of, the orifices would result in a small LOCA not greater than.one inch in diameter.This type of break has been analyzed in WCAP-9600 (Reference 1)and would behave similarly to the hot leg break presented.in this report.Therefore a break in the vent line would not result in.a calculated core uncover.A locked open hand valve will be installed upstream of the 3/8" orifices.The isolation valves are D.C.powered, fail closed, solenoid valves with stem position switches.These valves can be operated from.'he control.room..They will be no@nally closed during plant operation.

Indicating

'hghts will be installed in the control room so the operators will know tne valve position.These valves will be qualified to IEEE-323-1974, IEEE-344-1975 an'd IEEE-383-1972.

RTD assemblies have been added downstream of the solenoid valves to detect leakage through these valves..These RTD"ssemblies will set off an alarm in the control room if leakage through the valves should occur..The reactor vessel head vent connects to a part-length control rod drive mechanism housing located near the center of the reactor head.The pressurizer vent is connected to the pressurizer relief line.The possibility of reactor coolant pressure boundary leakage is minimized because of the two isolation valves in series.Isolation valves in one flow path are powered by Train A and the valves in the second flow path are powered by Train B.Both the reactor head vent and the pressurizer vent discharge into the upper volume of the.containment at approx.elevation 673'-0", in an area which will provide adequate dilution of any combustible gas. All piping and equipment used in the reactor head vent from the part-length rod housing to the orifices and all piping and equipment used in the pressurizer vent from the pressurizer relief piping to the orifices are designed in accordance with ASME,Section III Class 1 requirements.

From the orifices up to the first anchor downstream of the second isolation valve the piping and equipment has been designed in accordance with ASME Section III Class 2 requirements.

The remainder of the piping is designed to AEP Seismic Class 1 Level 4.~Testin The isolation valves used on the reactor head vent and pressurizer-vent will be tested in accordance with subsection IWV-3000 of ASME Section XI for Category B valves during refueling outages.~Otal P d The following procedures are attached and aregenerically applicable to the D.C.Cook Plant.1.Background Information for'Pressurizer Venting Operation-Rev.0 dated March 1981.2.Pressurizer Venting Oper ation-Rev.0 dated March 1981.3.Background Information for Reactor Head Vent Operation-Rev.0 dated February 1981.4.Reactor Vessel Head Vent Operation-Rev.0 dated February 1981.References 1.WCAP-9600,"Report on Small Break Accidents for Westinghouse NSSS System," June 1979, (specifically Case.F Section 3.2).

ATTACHMENT E T0 AEP:NRC:0584

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