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| issue date = 01/30/1998
| issue date = 01/30/1998
| title = Responds to GL 97-04, Assurance of Sufficient Net Positive Suction Head for ECC & Containment Heat Removal Pumps.
| title = Responds to GL 97-04, Assurance of Sufficient Net Positive Suction Head for ECC & Containment Heat Removal Pumps.
| author name = FITZPATRICK E
| author name = Fitzpatrick E
| author affiliation = INDIANA MICHIGAN POWER CO.
| author affiliation = INDIANA MICHIGAN POWER CO.
| addressee name =  
| addressee name =  
Line 16: Line 16:


=Text=
=Text=
{{#Wiki_filter:~CATEGORY1REGULATORY INFORMATION DISTRIBUTION SYSTEM(RIDS)ACCESSION NBR:9802120302 DOC.DATE:
{{#Wiki_filter:~         CATEGORY 1 REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)
98/Ol/30NOTARIZED:
ACCESSION NBR:9802120302           DOC.DATE:   98/Ol/30    NOTARIZED: YES              DOCKET FACIL:50-315 Donald C. Cook Nuclear Power Plant, Unit 1, Indiana                    M  05000315 50-~16 D'onald C. Cook Nuclear Power Plant, Unit 2, Indiana                  M  05000316 AUTH. NAME            AUTHOR AFFILIATION FITZPATRICK,E.E       Indiana Michigan Power Co.
YESDOCKETFACIL:50-315 DonaldC.CookNuclearPowerPlant,Unit1,IndianaM0500031550-~16D'onaldC.CookNuclearPowerPlant,Unit2,IndianaM05000316AUTH.NAMEAUTHORAFFILIATION FITZPATRICK,E.E IndianaMichiganPowerCo.RECIP.NAME RECIPIENT AFFILIATION DocumentControlBranch(Document ControlDesk)
RECIP.NAME           RECIPIENT AFFILIATION Document Control Branch (Document           Control Desk)


==SUBJECT:==
==SUBJECT:==
SubmitsGL97-04,"Assurance ofSufficient NetPositiveSuctionHeadforECCEcContainment HeatRemovalPumps."DISTRIBUTION CODE:A076DCOPIESRECEIVED:L'VR ENCLSIZE:TITLE:GL97-04Assurance ofSufficient Net>Positive SuctionHeadForNOTES:Emerg~ERECIPIENT IDCODE/NAME PD3-3PDCOPIESRECIPIENT LTTRENCLIDCODE/NAME 11"HICKMAN,J COPIESLTTRENCL110INTERNAL:
Submits GL 97-04, "Assurance of Sufficient Net Positive Suction Head for ECC Ec Containment Heat Removal Pumps."
LECENTENRRSSA/SRXBEXTERNAL:
DISTRIBUTION CODE: A076D        COPIES RECEIVED:L'VR         ENCL        SIZE:
NOAC111.111NRR/DSSA/SCSB NRR/PD3-2 NRCPDR112211D0UENNOTETOALL"RIDS"RECIPIENTS:
TITLE: GL  97-04 Assurance      of Sufficient Net>Positive Suction            Head For Emerg ~
PLEASEHELPUSTOREDUCEWASTE.TOHAVEYOURNAMEORORGANIZATION REMOVEDFROMDISTRIBUTION LISTSORREDUCETHENUMBEROFCOPIESRECEIVEDBYYOUORYOURORGANIZATION, CONTACTTHEDOCUMENTCONTROLDESK(DCD)ONEXTENSION 415-2083TOTALNUMBEROFCOPIESREQUIRED:
NOTES:                                                                                            E RECIPIENT            COPIES              RECIPIENT            COPIES ID CODE/NAME           LTTR ENCL        ID  CODE/NAME        LTTR ENCL PD3-3 PD                  1      1    " HICKMAN,J                 1    1              0 INTERNAL:     LE CENTE                1      1      NRR/DSSA/SCSB             1    1 NRR    SSA/SRXB            1. 1      NRR/PD3-2                 2    2 EXTERNAL: NOAC                        1      1      NRC PDR                  1    1 D
LTTR9ENCL9 a~ft,~i'4f,pVI' IndianaMichiganPowerCompany500CircleDriveBuchanan, Ml491071395 January30,1998AEP:NRC:1280ADocketNos.:50-31550-316U.S.NuclearRegulatory Commission ATTN:DocumentControlDeskWashington, D.C.20555-0001 Gentlemen:
0 U
DonaldC.CookNuclearPlantUnits1and2LICENSENOS.DPR-58ANDDPR-74REQUESTED INFORMATION
E N
-GENERICLETTER(GL)97-04ASSURANCE OFSUFFICIENT NETPOSITIVESUCTIONHEADFOREMERGENCY CORECOOLINGANDCONTAINMENT HEATREMOVALPUMPSOnOctober7,1997,theNuclearRegulatory Commission (NRC)issuedGL97-04,"Assurance ofSufficient NetPositiveSuctionHeadforEmergency CoreCoolingandContainment HeatRemovalPumps",indicating thatadequatenetpositivesuctionheadmaynotbeavailable totheemergency corecoolingsystemandcontainment spraypumpsunderalldesignbasisaccidentscenarios.
NOTE TO ALL  "RIDS" RECIPIENTS:
Theattachment tothislettercontainsourresponsetotheinformation requested inGL97-04."'.E.E.Fitzpatrick VicePresident
PLEASE HELP US TO REDUCE WASTE. TO HAVE YOUR NAME OR ORGANIZATION REMOVED FROM DISTRIBUTION LISTS OR REDUCE THE NUMBER OF COPIES RECEIVED BY YOU OR YOUR ORGANIZATION, CONTACT THE DOCUMENT CONTROL DESK (DCD) ON EXTENSION 415-2083 TOTAL NUMBER OF COPIES REQUIRED: LTTR                9  ENCL      9
'rt,,SWORNTOANDSUBSCRIBED BEFOREMEghTHIS~DAYOF~+~4,1998NotaryPublic//vlbAttachment UNDAL8OEi.CKENotaryPublic,8errienCaunty,MlMyCommission ExpiresJanuary21,2001J.A.AbramsonA.B.BeachMDEQ-DW&RPDNRCResidentInspector J.R.Sampson9802i20302'st80i30 PDRADQCK050003i5PPDRllllllllllllllllllllllllllllIll lllllll li"l ATTACHMENT TOAEP:NRC:1280A REQUESTED INFORMATION
 
-GENERICLETTER(97-04),ASSURANCE OFSUFFICIENT NETPOSITIVESUCTIONHEADFOREMERGENCY CORECOOLINGANDCONTAINMENT HEATREMOVALPUMPSa'pl%llh\'
a ~f
Attachment toAEP:NRC:1280A Page1Following isourresponsetotheinformation requested ingenericletter(GL)97-04,"Assurance ofSufficient NetPositiveSuctionHeadforEmergency CoreCoolingandContainment HeatRemovalPumps",datedOctober7,1997.GL97-04REVESTNO.1"Specifythegeneralmethodology usedtocalculate theheadlossassociated withtheECCSsuctionstrainers."
  ~
OURRESPONSETOREVESTNO.1Theemergency corecoolingsystem(ECCS)suctionstrainers atCookNuclearPlantconsistofgratingandscreensattheinlettothecontainment recirculation sump.Thesumpdesignincludestwolayersofcoarsegratingatthesumpentrancethatsandwichasinglelayerof1/4"finemeshscreen.Thenetpositivesuctionhead(NPSH)calculation fortheECCSandcontainment spray(CTS)pumpsassumesaheadlossof1ft.acrossthecontainment recirculation sumpataflowof15,600gpm.Thisheadlossrepresents lossesfromupstreamoftheouterlayerofgrating,throughthesump,andintothepipesatthesumpexit.Theassumedheadlossisbasedonempirical datafromsumpmodeltesting,plusconservatism.
t i'4 f,p V
Ourcontainment recirculation sumpdesignwasmodeltestedduringthelate1970satAldenResearchLaboratory tostudyvortexing andairentrainment.
I'
Theresultsfromthemodeltestingweresubmitted totheNRCinourletterAEP:NRC:00112, datedDecember20,1978.Aby-product fromthemodeltesting,whichincludedtestingforvarious"plateblockage" schemesatthesumpentrance, wasempirical headlossdataacrosstheentiresumpatminimumwaterlevel,elevation 602'-10".
 
Sumpentryscreenblockageofupto50%wasmodeled.Losscoefficients weredetermined forvarioustestschemes,andarerepresented bytheequation:
Indiana Michigan Power Company 500 Circle Drive Buchanan, Ml 491071395 January 30, 1998                                                          AEP: NRC: 128 0A Docket Nos.:         50-315 50-316 U.S. Nuclear Regulatory Commission ATTN:       Document    Control Desk Washington, D.C. 20555-0001 Gentlemen:
h~Cq=".y'2gwhere:Cghvgdimensionless losscoefficient theheadlossinft.fluidvelocityatthesumpexitpipes32.2ft./sec.'oss coefficient datafromtable10oftheAldenLaboratory testreport,whenusedwiththeaboveequation, indicated thatthehighestobservedheadlossacrossthesumpwas0.77ft.Maximumflowduringsumpmodeltestingwas15,400gpm,7,700gpmpersumpoutletpipe,whichcompareswelltoamaximumexpectedflowof15,600gpmpercurrentcalculations.
Donald C. Cook Nuclear Plant Units                1 and 2 LICENSE NOS. DPR-58 AND DPR-74 REQUESTED INFORMATION - GENERIC LETTER (GL) 97-04 ASSURANCE OF SUFFICIENT NET POSITIVE SUCTION HEAD FOR EMERGENCY CORE COOLING AND CONTAINMENT HEAT REMOVAL PUMPS On  October 7, 1997, the Nuclear Regulatory Commission (NRC) issued GL    97-04, "Assurance of Sufficient Net Positive Suction Head for Emergency Core Cooling and Containment Heat Removal Pumps",
Thisdifference inflowwasconsidered insignificant indetermining headlossacrossthesumpinletandthroughthesump.Theas-modeled sumpdesignincludedasinglecoarsegratingandasinglefinemeshscreen.AldenLaboratory alsoprovidedheadlossdataforlossesacrossthegratingandscreen.Becausethecurrentsumpentranceincludestwolayersofcoarsegrating,oneupstreamandonedownstream ofthefinemeshscreen,theheadlossacrossthegratingandscreenwascountedtwicetoconservatively accountforthesecondgrating.
indicating that adequate net positive suction head may not be available to the emergency core cooling system and containment spray pumps under all design basis accident scenarios.
IIAttachment toAEP:NRC:1280A Page2Basedontheheadlossthroughthesumpof0.77ft.intheas-modeledconfiguration, andaheadlossof0.052ft.acrossthesecondgrating,thecurrentNPSHcalculation conservatively assumesa1ft.headlossacrossthesump.Althoughthesumpheadlossdataaboveincludeslossesfromupstreamofthesumpentrancetoinsidethepipesatthesumpexit,entrancelossesatthesumpexitpipeswerealsocalculated separately andincludedintheNPSHcalculations forconservatism.
The    attachment to this letter contains                    our response      to the information requested in GL 97-04.
GL97-04REVESTNO.2"Identify therequiredNPSHandtheavailable NPSH."OURRESPONSETOREVESTNO.2Thenetpositivesuctionheadrequired(NPSHR)andnetpositivesuctionheadavailable (NPSHA)fortheresidualheatremoval(RHR)andCTSpumps,whichtakesuctiondirectlyfromthecontainment recirculation sump,areasfollows:~PumNPSHRNPSHARHRCTS20ft.abs9ft.abs29ft.abs31ft.absAsa"pointofinformation, theNPSHRandNPSHAforthesafetyinjection (SI)andcentrifugal charging(CC)pumps,whichtakesuctionfromtheRHRpumpswhentheECCSisintherecirculation modeofoperation, are:~PumSICCNPSHR13ft.abs17ft.absNPSHA122ft.abs48ft.absTheNPSHR,tabulated above,wasobtainedfromtheindividual ECCSpumpperformance curvesattheexpectedECCSpumpflow.Available NPSH,tabulated above,wascalculated usingthegeneralmethodology detai'led, below.Asindicated
          "'. E. E. Fitzpatrick Vice President
'in,ourresponsetoquestion.
'r t,
No.,l,,'head,lossof1'ft.'a'cross thesump'screhnwasas'sumedin,the.NPSH,calculation at15,600gpm.Thebasicequationforcalculating NPSHis:NPSH=h,-h,+h-hfdfwhere:h,habsolutepressure, infeetoftheliquidbeingpumped,onthesurfaceoftherecirculation sumplevel,head,infeet,corresponding tothevaporpressureoftherecirculation sumpliquidatthetemperature beingpumped,staticheight,infeet,thattherecirculation sumpliquidlevelisaboveorbelowthepumpsuctioncenterline orimpellereye,and Attachment toAEP:NRC:1280A Page3h=allfrictionlosses,infeet,including entrancelossesandfrictionlossesthroughpipe,valves,andfittings, etc.Additional detailsoneachoftheabovetermsareprovidedbelow.h,-Absolutepressureonthesurfaceoftherecirculation sumplevel.Thistermisthecontainment pressureassumedintheanalysis.
THIS  ~
Becausenocreditistakenforcontainment overpressure, atmospheric pressureisusedastheliquid'sabsolutepressure.
SWORN TO AND SUBSCRIBED BEFORE ME gh DAY OF  ~+~4,       1998 Notary Public
h,-Headcorresponding tothevaporpressureoftherecirculation sumpliquidatthetemperature beingpumped.Thistermisafunctionofthetemperature ofthefluid.Themaximumexpectedrecirculation sumptemperature of190'.isused.Thisconservatively boundsbothunits.h-Staticheightthattherecirculation sumpliquidlevelisaboveorbelowthepumpsuctioncenterline orimpellereye.Thistermistheminimumstaticheightoffluidabovethepumpcenterline.
                                                          /
Aminimumsumpwaterlevelcorresponding toelevation 602'-10"wasused,whichwasconfirmed viasumpmodeltestingtobealevelthatprecludes airentrainment andvortexing.
UNDA L 8OEi.CKE
Sumpinventory calculations confirmthatthislevelwillbesustained forpostulated accidents.
              /vlb                                  Notary Public, 8errien Caunty, Ml 2001 My Commission Expires January 21, Attachment J. A. Abramson A. B. Beach MDEQ - DW & RPD NRC    Resident Inspector J. R. Sampson 9802i20302'st80i30                                 llllllllllllllllllllllllllllIll lllllll PDR    ADQCK 050003i5 P                        PDR
h-Allfrictionlossesincluding entrancelossesandfrictionlossesthroughpipe,valvesandfittings.
 
Thisterminvolvessuctionlinelossesassociated withtheECCSpumpbeingevaluated.
l i" l
Theheadlossesconsidered inthistermarefrictionlossesbasedonpiperoughness, pipelength,velocityheadlosses,headlossassociated withsumpscreen,entrancelosses,andnumberortypeofvalvesandifittings inthe,suctionpiping.i~w~,IiQL.97-04REVESTNO.'""Specifywhetherthecurrentdesign-basis NPSHanalysisdiffersfromthemostrecentanalysisreviewedandapprovedbytheNRCforwhichasafetyevaluation wasissued."OURRESPONSETOREVESTNO.3ThecurrentdesignbasisNPSHanalysisdiffersfromthemostrecentanalysissubmitted totheNRCinthemannerinwhichtheRHRsystemwasanalyzed.
 
ThemostrecentNPSHanalysissubmitted totheNRCwasprovidedinresponsetoFSARchapter6.3,question212.29(unit2,appendixQ;amendment 78,October1977).Question212.29consisted ofthreeparts,oneofwhichwasspecifictotheNPSHanalysesfortheECCSpumps.Thisquestionrequested detaileddescriptions oftheNPSHcalculations fortheECCSpumpsduringpostulated postloss-of-coolantaccidentconditions, including pertinent elevations, limitingpumpandvalvealignment thatwouldprovidethesmallestNPSHmargin,pumpNPSHrequirements, justificationofthesumpwatertemperature, suctionlinehydraulic losses,andresultant Attachment toAEP:NRC:1280A Page4NPSHmargininaccordance withregulatory guide1.1.Aspartoftheresponsetothisquestion, acopyoftheNPSHcalculation wasincludedasanattachment.
ATTACHMENT TO AEP:NRC:1280A REQUESTED INFORMATION - GENERIC LETTER (97-04),
Areviewofthatattachment indicates thattheNPSHwascalculated basedonthefollowing.
ASSURANCE OF SUFFICIENT NET POSITIVE SUCTION HEAD FOR EMERGENCY CORE COOLING AND CONTAINMENT HEAT REMOVAL PUMPS a
Watertemperature, 1904F.Containment
pl % ll h
: pressure, oneatmosphere (absolute)
                        \
Pumpsoperating atmaximumflowrateasdetermined bysystemresistance calculations assumingreactorcoolantsystempressureequalto0psigandallaffectedvalvesconsidered wideopen.ThesinglefailurethatwillresultinthelowestNPSHmarginisthefailureofoneRHRpumptooperate.Inthisinstance, theremaining RHRpumpwilloperateatarunoutcondition.
 
Noreactorcoolantwaternoricebedmeltdownisusedtoestablish activecontainment sumpwaterinventory.
Attachment to AEP:NRC:1280A                                                 Page  1 Following is our response to the information requested in generic letter (GL) 97-04, "Assurance of Sufficient Net Positive Suction Head for Emergency Core Cooling and Containment Heat Removal Pumps",   dated October 7, 1997.
TheNPSHAcalculations utilizeonlythatportionoftherefueling waterstoragetank(RWST)inventory thathasbeenpumpedintothecontainment priortotheswitchover ofthefirstECCStrainswitch-over fromRWSTtotheactivecontainment sump.RHRpumpdischarge crosstievalves,IMO-314andIM0-324,areopenallowingRHRflowfromonepumptoflowthroughbothRHRheatexchangers.
GL  97-04  RE VEST NO. 1 "Specify the general methodology used to calculate the head loss associated with the ECCS suction strainers."
Containment recirculation sumpdesignincludescoarsegratingatthesumpentranceandfinegrating,perforated plate,inthesumpbackchamberjustupstxeamofthesumpoutletpipes.ThecurrentdesignbasisNPSHcalculation isbasedonthefollowing.\2.3'.'atertemperature, 1904F.Containment
OUR RESPONSE  TO RE VEST NO. 1 The emergency core cooling system (ECCS) suction strainers at Cook Nuclear Plant consist of grating and screens at the inlet to the containment recirculation sump.                   The sump design includes two layers of coarse grating at the sump entrance that sandwich a single layer of 1/4" fine mesh screen. The net positive suction head (NPSH) calculation for the ECCS and containment spray (CTS) pumps assumes    a head loss of 1 ft. across                    the containment recirculation sump at a flow of 15,600 gpm. This head loss represents losses from upstream of the outer layer of grating, through the sump, and into the pipes at the sump exit. The assumed head loss is based on empirical data from sump model testing, plus conservatism.
: pressure, one,atmosphere (absolute)..
Our containment recirculation sump design was model tested during the late 1970s at Alden Research Laboratory to study vortexing and air entrainment. The results from the model testing were submitted to the NRC in our letter AEP:NRC:00112, dated December 20, 1978.
IPumpsoperating asdetermined bysystemresistance calculations assumingreactorcoolantsystempressureequalto0psig,andECCSSIandCCvalvessetasrequiredbytechnical specifications.
A by-product from the model testing, which included testing for various "plate blockage" schemes at the sump entrance, was empirical head loss data across the entire sump at minimum water level, elevation 602'-10". Sump entry screen blockage of up to 50%
ThesinglefailureappliedisthefailureofoneRHRpumptooperate.Inthisinstance, theremaining RHRpumpwillsupplytwoSIpumpsandtwoCCpumpsthroughasingleRHRheatexchanger (see6below).Reactorcoolantwaterandicebedmeltdownisusedtoestablish activecontainment sumpwaterinventory.
was modeled. Loss coefficients were determined for various test schemes, and are represented by the equation:
Thischangewasdetermined tobeanunreviewed safetyquestion.
h~
Alicenseamendment hasbeenissuedinresponsetooursubmittal AEP:NRC:0900K, datedOctober8,1997.RHRpumpdischarge crosstievalvesareclosedasrequiredbyourprocedure OHP4023.ES-1.3, "Transfer toColdLegRecirculation".
Cq =
TheRHRpumpdischarge crosstievalvesarenormallyclosedtoprecludedead-heading ofaweakerRHRpump.
                                        ".y'   2g where:
Attachment toAEP:NRC:1280A Page5Containment recirculation sumpdesignasmodifiedtoincorporate recommendations fromsumpmodeltestingbyAldenResearchLaboratory.
Cg          dimensionless loss coefficient h          the head loss in ft.
Modifiedsumpdesignincludestwolayersofgratingthatsandwichasinglelayeroffinemeshscreen,atthesumpentrance.
v            fluid velocity at the sump exit pipes g            32.2 ft./sec.'oss coefficient data from table 10 of the Alden Laboratory test report, when used with the above equation, indicated that the highest observed head loss across the sump was 0.77 ft. Maximum flow during sump model testing was 15,400 gpm, 7,700 gpm per sump outlet pipe, which compares well to a maximum expected flow of 15,600 gpm per current calculations.                 This difference in flow was considered insignificant in determining head loss across the sump inlet and through the sump. The as-modeled sump design included a single coarse grating and a single fine mesh screen.                         Alden Laboratory also provided head loss data for losses across the grating and screen. Because the current sump entrance includes two layers of coarse grating, one upstream and one downstream of the fine mesh screen, the head loss across the grating and screen was counted twice to conservatively account for the second grating.
Finegratingandperforated plateinthesumpbackchamberwereremoved.Therefore, thecurrentdesignbasisNPSHanalysisdiffersfromthemostrecentanalysissubmitted totheNRCasindicated bythedifferences betweenitems3,4,5,6,and7above.GL97-04REVESTNO.4"Specifywhethercontainment overpressure (i.e.,containment pressureabovethevaporpressureofthesumporsuppression poolfluid)wascreditedinthecalculation ofavailable NPSH.Specifytheamountofoverpressure neededandtheminimumoverpressure available."
 
OURRESPONSETOREVESTNO.4Creditwasnottakenforthecontainment pressureindetermining theNPSHavailable totheECCSpumps.Thecontainment pressureusedindetermining theNPSHavailable isoneatmosphere, absolute.
Attachment to AEP:NRC:1280A                                             Page 2 I
Nooverpressure orminimumoverpressure wasusedindetermining theavailable NPSH.GL97-04REUESTNO.5"Whencontainment overpressure iscreditedinthecalculation ofavailable NPSH,confirmthatanappropriate containment pressureanalysiswasdonetoestablish theminimumcontainment pressure."
I Based on the head loss through the sump of 0.77                ft. in the as-modeled configuration, and a head loss of 0.052                ft.
OURRESPONSETOREVESTNO.5Creditisnottakenforcontainment overpressure pressureindetermining theNPSHavailable totheECCSpumps.Thecontainment pressureusedindetermining theNPSHavailable isoneatmosphere.
second grating, the current NPSH calculation conservatively assumes across the a 1  ft. head loss across the sump.           Although the sump head loss data above includes losses from upstream of the sump entrance to inside the pipes at the sump exit, entrance losses at the sump exit pipes were also calculated separately and included in the NPSH calculations for conservatism.
'Itlll4}}
GL  97-04  RE VEST NO. 2 "Identify the required        NPSH    and the  available    NPSH."
OUR RESPONSE      TO RE VEST NO. 2 The  net positive suction head required (NPSHR) and net positive suction head available (NPSHA) for the residual heat removal (RHR) and CTS pumps, which take suction directly from the containment recirculation sump, are as follows:
            ~Pum                NPSHR                  NPSHA RHR              20  ft. abs          29  ft. abs CTS                9  ft. abs          31  ft. abs As a"   point of information, the NPSHR and NPSHA for the safety injection      (SI) and centrifugal charging (CC) pumps, which take suction from the RHR pumps when the ECCS is in the recirculation mode of operation, are:
            ~Pum                NPSHR                  NPSHA SI              13  ft. abs          122  ft. abs CC              17  ft. abs            48  ft. abs The NPSHR,     tabulated above, was obtained from the individual ECCS pump  performance curves at the expected ECCS pump flow. Available NPSH, tabulated above, was calculated using the general methodology detai'led, below.       As indicated 'in,our response to question. No.,l,,'
head, loss of 1'ft.'a'cross the sump 'screhn was as'sumed in, the.NPSH ,
calculation at 15,600 gpm.
The  basic equation for calculating          NPSH  is:
NPSH=     h,   -h,     +h-hfdf where:
h,             absolute pressure, in feet of the liquid being pumped, on the surface of the recirculation sump level, head, in feet, corresponding to the vapor pressure of the recirculation sump liquid at the temperature being pumped, h              static height, in feet, that the recirculation sump liquid level is above or below the pump suction centerline or impeller eye,     and
 
Attachment to AEP:NRC:1280A                                           Page 3 h      =     all friction    losses, in feet, including entrance    losses    and  friction losses through pipe, valves, and fittings, etc.
Additional details      on each  of the above terms are provided below.
h, - Absolute pressure      on  the surface of the recirculation sump level.
This term is the containment pressure assumed in the analysis.
Because      no credit is taken          for containment overpressure, atmospheric pressure is used as the liquid's absolute pressure.
h , - Head corresponding      to the vapor pressure of the recirculation sump  liquid at the temperature being pumped.
This term is a function of the temperature of the fluid.                 The maximum expected    recirculation  sump  temperature of  190'. is    used.
This conservatively bounds both units.
h - Static height that the recirculation sump liquid level is above or below the pump suction centerline or impeller eye.
This term is the minimum static height of fluid above the pump centerline. A minimum sump water level corresponding to elevation 602'-10" was used, which was confirmed via sump model testing to be a level that precludes air entrainment and vortexing.                   Sump inventory calculations confirm that this level will be sustained for postulated accidents.
h - All friction losses including entrance losses          and  friction losses through pipe, valves and fittings.
This term involves suction line losses associated with the ECCS pump being evaluated. The head losses considered in this term are friction losses based on pipe roughness, pipe length, velocity head losses, head loss associated with sump screen, entrance losses, and number or type of valves andifittings in the, suction piping.
        ~,                                            i w
                                                        ~
i QL. 97-04 I
RE VEST  NO.'"
"Specify whether the current design-basis NPSH analysis differs from the most recent analysis reviewed and approved by the NRC for which a safety evaluation was issued."
OUR RESPONSE    TO RE VEST NO. 3 The  current design basis NPSH analysis differs from the most recent analysis submitted to the NRC in the manner in which the RHR system was  analyzed.
The most    recent  NPSH  analysis submitted to the NRC was provided in response    to FSAR  chapter 6.3, question 212.29 (unit 2, appendix Q; amendment 78, October 1977).         Question 212.29 consisted of three parts, one of which was specific to the NPSH analyses for the ECCS pumps. This question requested detailed descriptions of the NPSH calculations for the ECCS pumps during postulated post loss-of-coolant accident conditions, including pertinent elevations, limiting pump and valve alignment that would provide the smallest NPSH margin, pump NPSH requirements,           justification of the sump water temperature, suction line hydraulic losses, and resultant
 
Attachment to AEP:NRC:1280A                                             Page 4 NPSH  margin in accordance with regulatory guide 1. 1. As part of the response to this question, a copy of the NPSH calculation was included as an attachment. A review of that attachment indicates that the NPSH was calculated based on the following.
Water temperature,         1904 F.
Containment pressure,         one atmosphere    (absolute)
Pumps    operating at maximum flow rate as determined by system resistance calculations assuming reactor coolant system pressure equal to 0 psig and all affected valves considered wide open.
The    single failure that will result in the lowest NPSH margin is the failure of one RHR pump to operate. In this instance, the remaining    RHR pump    will operate    at  a runout condition.
No  reactor coolant water nor ice bed melt down is used to establish active containment sump water inventory. The NPSHA calculations utilize only that portion of the refueling water storage tank (RWST) inventory that has been pumped into the containment prior to the switchover of the first ECCS train switch-over from RWST to the active containment sump.
RHR pump discharge crosstie valves, IMO-314 and IM0-324, are open allowing RHR flow from one pump to flow through both RHR heat exchangers.
Containment     recirculation sump design includes coarse grating at the    sump entrance and fine grating, perforated plate, in the    sump back chamber just upstxeam of the sump outlet pipes.
The  current      design  basis      NPSH  calculation    is    based on  the following  .
temperature,    1904F.
\
3'.'ater
: 2. Containment     pressure,I    one, atmosphere   (absolute)..
Pumps      operating as determined by system resistance calculations assuming reactor coolant system pressure equal to 0 psig, and ECCS SI and CC valves set as required by technical specifications.
The single failure applied is the failure of one RHR pump to operate.       In this instance, the remaining RHR pump will supply two SI pumps and two CC pumps through a single RHR heat exchanger      (see    6 below).
Reactor coolant water and ice bed melt                  down is used to establish active containment sump water                inventory. This change was determined to be an unreviewed                safety question.
A license amendment has been issued in                  response to our submittal AEP:NRC:0900K, dated October 8,             1997.
RHR pump    discharge crosstie valves are closed as required by our procedure OHP 4023.ES-1.3,                 "Transfer to Cold Leg Recirculation". The RHR pump discharge crosstie valves are normally closed to preclude dead-heading of a weaker RHR pump.
 
Attachment to AEP:NRC:1280A                                     Page 5 Containment    recirculation sump design as modif ied to incorporate recommendations from sump model testing by Alden Research Laboratory.     Modified sump design includes two layers of grating that sandwich a single layer of fine mesh screen, at the sump entrance. Fine grating and perforated plate in the sump back chamber were removed.
Therefore, the current design basis NPSH analysis differs from the most recent analysis submitted to the NRC as indicated by the differences between items 3, 4, 5, 6, and 7 above.
GL  97-04  RE VEST NO. 4 "Specify whether containment overpressure         (i.e., containment pressure above the vapor pressure of the sump or suppression pool fluid) was credited in the calculation of available NPSH. Specify the amount of overpressure needed and the minimum overpressure available."
OUR RESPONSE    TO RE VEST NO. 4 Credit  was  not taken for the containment pressure in determining the  NPSH  available to the ECCS pumps. The containment pressure used in determining the NPSH available is one atmosphere, absolute.
No overpressure or minimum overpressure was used in determining the available NPSH.
GL  97-04  RE UEST NO. 5 "When containment overpressure is credited in the calculation of available NPSH, confirm that an appropriate containment pressure analysis was done to establish the minimum containment pressure."
OUR RESPONSE    TO RE VEST NO. 5 Credit is not taken for containment overpressure pressure in determining the NPSH available to the ECCS pumps. The containment pressure used in determining the NPSH available is one atmosphere.
                                                          'I ll tl 4}}

Latest revision as of 00:36, 4 February 2020

Responds to GL 97-04, Assurance of Sufficient Net Positive Suction Head for ECC & Containment Heat Removal Pumps.
ML17334B683
Person / Time
Site: Cook  American Electric Power icon.png
Issue date: 01/30/1998
From: Fitzpatrick E
INDIANA MICHIGAN POWER CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
AEP:NRC:1280A, GL-97-04, GL-97-4, NUDOCS 9802120302
Download: ML17334B683 (10)


Text

~ CATEGORY 1 REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)

ACCESSION NBR:9802120302 DOC.DATE: 98/Ol/30 NOTARIZED: YES DOCKET FACIL:50-315 Donald C. Cook Nuclear Power Plant, Unit 1, Indiana M 05000315 50-~16 D'onald C. Cook Nuclear Power Plant, Unit 2, Indiana M 05000316 AUTH. NAME AUTHOR AFFILIATION FITZPATRICK,E.E Indiana Michigan Power Co.

RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)

SUBJECT:

Submits GL 97-04, "Assurance of Sufficient Net Positive Suction Head for ECC Ec Containment Heat Removal Pumps."

DISTRIBUTION CODE: A076D COPIES RECEIVED:L'VR ENCL SIZE:

TITLE: GL 97-04 Assurance of Sufficient Net>Positive Suction Head For Emerg ~

NOTES: E RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD3-3 PD 1 1 " HICKMAN,J 1 1 0 INTERNAL: LE CENTE 1 1 NRR/DSSA/SCSB 1 1 NRR SSA/SRXB 1. 1 NRR/PD3-2 2 2 EXTERNAL: NOAC 1 1 NRC PDR 1 1 D

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NOTE TO ALL "RIDS" RECIPIENTS:

PLEASE HELP US TO REDUCE WASTE. TO HAVE YOUR NAME OR ORGANIZATION REMOVED FROM DISTRIBUTION LISTS OR REDUCE THE NUMBER OF COPIES RECEIVED BY YOU OR YOUR ORGANIZATION, CONTACT THE DOCUMENT CONTROL DESK (DCD) ON EXTENSION 415-2083 TOTAL NUMBER OF COPIES REQUIRED: LTTR 9 ENCL 9

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Indiana Michigan Power Company 500 Circle Drive Buchanan, Ml 491071395 January 30, 1998 AEP: NRC: 128 0A Docket Nos.: 50-315 50-316 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555-0001 Gentlemen:

Donald C. Cook Nuclear Plant Units 1 and 2 LICENSE NOS. DPR-58 AND DPR-74 REQUESTED INFORMATION - GENERIC LETTER (GL) 97-04 ASSURANCE OF SUFFICIENT NET POSITIVE SUCTION HEAD FOR EMERGENCY CORE COOLING AND CONTAINMENT HEAT REMOVAL PUMPS On October 7, 1997, the Nuclear Regulatory Commission (NRC) issued GL 97-04, "Assurance of Sufficient Net Positive Suction Head for Emergency Core Cooling and Containment Heat Removal Pumps",

indicating that adequate net positive suction head may not be available to the emergency core cooling system and containment spray pumps under all design basis accident scenarios.

The attachment to this letter contains our response to the information requested in GL 97-04.

"'. E. E. Fitzpatrick Vice President

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SWORN TO AND SUBSCRIBED BEFORE ME gh DAY OF ~+~4, 1998 Notary Public

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UNDA L 8OEi.CKE

/vlb Notary Public, 8errien Caunty, Ml 2001 My Commission Expires January 21, Attachment J. A. Abramson A. B. Beach MDEQ - DW & RPD NRC Resident Inspector J. R. Sampson 9802i20302'st80i30 llllllllllllllllllllllllllllIll lllllll PDR ADQCK 050003i5 P PDR

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ATTACHMENT TO AEP:NRC:1280A REQUESTED INFORMATION - GENERIC LETTER (97-04),

ASSURANCE OF SUFFICIENT NET POSITIVE SUCTION HEAD FOR EMERGENCY CORE COOLING AND CONTAINMENT HEAT REMOVAL PUMPS a

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Attachment to AEP:NRC:1280A Page 1 Following is our response to the information requested in generic letter (GL) 97-04, "Assurance of Sufficient Net Positive Suction Head for Emergency Core Cooling and Containment Heat Removal Pumps", dated October 7, 1997.

GL 97-04 RE VEST NO. 1 "Specify the general methodology used to calculate the head loss associated with the ECCS suction strainers."

OUR RESPONSE TO RE VEST NO. 1 The emergency core cooling system (ECCS) suction strainers at Cook Nuclear Plant consist of grating and screens at the inlet to the containment recirculation sump. The sump design includes two layers of coarse grating at the sump entrance that sandwich a single layer of 1/4" fine mesh screen. The net positive suction head (NPSH) calculation for the ECCS and containment spray (CTS) pumps assumes a head loss of 1 ft. across the containment recirculation sump at a flow of 15,600 gpm. This head loss represents losses from upstream of the outer layer of grating, through the sump, and into the pipes at the sump exit. The assumed head loss is based on empirical data from sump model testing, plus conservatism.

Our containment recirculation sump design was model tested during the late 1970s at Alden Research Laboratory to study vortexing and air entrainment. The results from the model testing were submitted to the NRC in our letter AEP:NRC:00112, dated December 20, 1978.

A by-product from the model testing, which included testing for various "plate blockage" schemes at the sump entrance, was empirical head loss data across the entire sump at minimum water level, elevation 602'-10". Sump entry screen blockage of up to 50%

was modeled. Loss coefficients were determined for various test schemes, and are represented by the equation:

h~

Cq =

".y' 2g where:

Cg dimensionless loss coefficient h the head loss in ft.

v fluid velocity at the sump exit pipes g 32.2 ft./sec.'oss coefficient data from table 10 of the Alden Laboratory test report, when used with the above equation, indicated that the highest observed head loss across the sump was 0.77 ft. Maximum flow during sump model testing was 15,400 gpm, 7,700 gpm per sump outlet pipe, which compares well to a maximum expected flow of 15,600 gpm per current calculations. This difference in flow was considered insignificant in determining head loss across the sump inlet and through the sump. The as-modeled sump design included a single coarse grating and a single fine mesh screen. Alden Laboratory also provided head loss data for losses across the grating and screen. Because the current sump entrance includes two layers of coarse grating, one upstream and one downstream of the fine mesh screen, the head loss across the grating and screen was counted twice to conservatively account for the second grating.

Attachment to AEP:NRC:1280A Page 2 I

I Based on the head loss through the sump of 0.77 ft. in the as-modeled configuration, and a head loss of 0.052 ft.

second grating, the current NPSH calculation conservatively assumes across the a 1 ft. head loss across the sump. Although the sump head loss data above includes losses from upstream of the sump entrance to inside the pipes at the sump exit, entrance losses at the sump exit pipes were also calculated separately and included in the NPSH calculations for conservatism.

GL 97-04 RE VEST NO. 2 "Identify the required NPSH and the available NPSH."

OUR RESPONSE TO RE VEST NO. 2 The net positive suction head required (NPSHR) and net positive suction head available (NPSHA) for the residual heat removal (RHR) and CTS pumps, which take suction directly from the containment recirculation sump, are as follows:

~Pum NPSHR NPSHA RHR 20 ft. abs 29 ft. abs CTS 9 ft. abs 31 ft. abs As a" point of information, the NPSHR and NPSHA for the safety injection (SI) and centrifugal charging (CC) pumps, which take suction from the RHR pumps when the ECCS is in the recirculation mode of operation, are:

~Pum NPSHR NPSHA SI 13 ft. abs 122 ft. abs CC 17 ft. abs 48 ft. abs The NPSHR, tabulated above, was obtained from the individual ECCS pump performance curves at the expected ECCS pump flow. Available NPSH, tabulated above, was calculated using the general methodology detai'led, below. As indicated 'in,our response to question. No.,l,,'

head, loss of 1'ft.'a'cross the sump 'screhn was as'sumed in, the.NPSH ,

calculation at 15,600 gpm.

The basic equation for calculating NPSH is:

NPSH= h, -h, +h-hfdf where:

h, absolute pressure, in feet of the liquid being pumped, on the surface of the recirculation sump level, head, in feet, corresponding to the vapor pressure of the recirculation sump liquid at the temperature being pumped, h static height, in feet, that the recirculation sump liquid level is above or below the pump suction centerline or impeller eye, and

Attachment to AEP:NRC:1280A Page 3 h = all friction losses, in feet, including entrance losses and friction losses through pipe, valves, and fittings, etc.

Additional details on each of the above terms are provided below.

h, - Absolute pressure on the surface of the recirculation sump level.

This term is the containment pressure assumed in the analysis.

Because no credit is taken for containment overpressure, atmospheric pressure is used as the liquid's absolute pressure.

h , - Head corresponding to the vapor pressure of the recirculation sump liquid at the temperature being pumped.

This term is a function of the temperature of the fluid. The maximum expected recirculation sump temperature of 190'. is used.

This conservatively bounds both units.

h - Static height that the recirculation sump liquid level is above or below the pump suction centerline or impeller eye.

This term is the minimum static height of fluid above the pump centerline. A minimum sump water level corresponding to elevation 602'-10" was used, which was confirmed via sump model testing to be a level that precludes air entrainment and vortexing. Sump inventory calculations confirm that this level will be sustained for postulated accidents.

h - All friction losses including entrance losses and friction losses through pipe, valves and fittings.

This term involves suction line losses associated with the ECCS pump being evaluated. The head losses considered in this term are friction losses based on pipe roughness, pipe length, velocity head losses, head loss associated with sump screen, entrance losses, and number or type of valves andifittings in the, suction piping.

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i QL. 97-04 I

RE VEST NO.'"

"Specify whether the current design-basis NPSH analysis differs from the most recent analysis reviewed and approved by the NRC for which a safety evaluation was issued."

OUR RESPONSE TO RE VEST NO. 3 The current design basis NPSH analysis differs from the most recent analysis submitted to the NRC in the manner in which the RHR system was analyzed.

The most recent NPSH analysis submitted to the NRC was provided in response to FSAR chapter 6.3, question 212.29 (unit 2, appendix Q; amendment 78, October 1977). Question 212.29 consisted of three parts, one of which was specific to the NPSH analyses for the ECCS pumps. This question requested detailed descriptions of the NPSH calculations for the ECCS pumps during postulated post loss-of-coolant accident conditions, including pertinent elevations, limiting pump and valve alignment that would provide the smallest NPSH margin, pump NPSH requirements, justification of the sump water temperature, suction line hydraulic losses, and resultant

Attachment to AEP:NRC:1280A Page 4 NPSH margin in accordance with regulatory guide 1. 1. As part of the response to this question, a copy of the NPSH calculation was included as an attachment. A review of that attachment indicates that the NPSH was calculated based on the following.

Water temperature, 1904 F.

Containment pressure, one atmosphere (absolute)

Pumps operating at maximum flow rate as determined by system resistance calculations assuming reactor coolant system pressure equal to 0 psig and all affected valves considered wide open.

The single failure that will result in the lowest NPSH margin is the failure of one RHR pump to operate. In this instance, the remaining RHR pump will operate at a runout condition.

No reactor coolant water nor ice bed melt down is used to establish active containment sump water inventory. The NPSHA calculations utilize only that portion of the refueling water storage tank (RWST) inventory that has been pumped into the containment prior to the switchover of the first ECCS train switch-over from RWST to the active containment sump.

RHR pump discharge crosstie valves, IMO-314 and IM0-324, are open allowing RHR flow from one pump to flow through both RHR heat exchangers.

Containment recirculation sump design includes coarse grating at the sump entrance and fine grating, perforated plate, in the sump back chamber just upstxeam of the sump outlet pipes.

The current design basis NPSH calculation is based on the following .

temperature, 1904F.

\

3'.'ater

2. Containment pressure,I one, atmosphere (absolute)..

Pumps operating as determined by system resistance calculations assuming reactor coolant system pressure equal to 0 psig, and ECCS SI and CC valves set as required by technical specifications.

The single failure applied is the failure of one RHR pump to operate. In this instance, the remaining RHR pump will supply two SI pumps and two CC pumps through a single RHR heat exchanger (see 6 below).

Reactor coolant water and ice bed melt down is used to establish active containment sump water inventory. This change was determined to be an unreviewed safety question.

A license amendment has been issued in response to our submittal AEP:NRC:0900K, dated October 8, 1997.

RHR pump discharge crosstie valves are closed as required by our procedure OHP 4023.ES-1.3, "Transfer to Cold Leg Recirculation". The RHR pump discharge crosstie valves are normally closed to preclude dead-heading of a weaker RHR pump.

Attachment to AEP:NRC:1280A Page 5 Containment recirculation sump design as modif ied to incorporate recommendations from sump model testing by Alden Research Laboratory. Modified sump design includes two layers of grating that sandwich a single layer of fine mesh screen, at the sump entrance. Fine grating and perforated plate in the sump back chamber were removed.

Therefore, the current design basis NPSH analysis differs from the most recent analysis submitted to the NRC as indicated by the differences between items 3, 4, 5, 6, and 7 above.

GL 97-04 RE VEST NO. 4 "Specify whether containment overpressure (i.e., containment pressure above the vapor pressure of the sump or suppression pool fluid) was credited in the calculation of available NPSH. Specify the amount of overpressure needed and the minimum overpressure available."

OUR RESPONSE TO RE VEST NO. 4 Credit was not taken for the containment pressure in determining the NPSH available to the ECCS pumps. The containment pressure used in determining the NPSH available is one atmosphere, absolute.

No overpressure or minimum overpressure was used in determining the available NPSH.

GL 97-04 RE UEST NO. 5 "When containment overpressure is credited in the calculation of available NPSH, confirm that an appropriate containment pressure analysis was done to establish the minimum containment pressure."

OUR RESPONSE TO RE VEST NO. 5 Credit is not taken for containment overpressure pressure in determining the NPSH available to the ECCS pumps. The containment pressure used in determining the NPSH available is one atmosphere.

'I ll tl 4