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| | issue date = 06/05/1981 | | | issue date = 06/05/1981 |
| | title = Interim Deficiency Rept Re Lack of Required Special Conduit Separation for Certain safety-related Electrical Circuits, Initially Reported on 810408.Safety-related Electrical Circuits Will Be Correctly Separated | | | title = Interim Deficiency Rept Re Lack of Required Special Conduit Separation for Certain safety-related Electrical Circuits, Initially Reported on 810408.Safety-related Electrical Circuits Will Be Correctly Separated |
| | author name = CURTIS N W | | | author name = Curtis N |
| | author affiliation = PENNSYLVANIA POWER & LIGHT CO. | | | author affiliation = PENNSYLVANIA POWER & LIGHT CO. |
| | addressee name = GRIER B H | | | addressee name = Grier B |
| | addressee affiliation = NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) | | | addressee affiliation = NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| | docket = 05000387, 05000388 | | | docket = 05000387, 05000388 |
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| =Text= | | =Text= |
| {{#Wiki_filter:REGULATORY INFORMATION DISTRIBUTION SYSTEM.(RIDS)ACCESSION NBR:8106090406 DOC~DATE!81/06/05NOTARIZED: | | {{#Wiki_filter:REGULATORY INFORMATION DISTRIBUTION SYSTEM. (RIDS) |
| NODOCKE.T'FACIL:50387Susquehanna SteamElectrfcStationsUnft1>Pennsylva0500~08750388Susquehanna SteamElectrfcStatfoneUnft2'PPennsylva05'I)038AUTH',NAME AUTHORAFFILIATTONCURTISEN~W~PennsylvanfaPowerLLfghtCo~RECIP~NAMElRECIPIENT AFFILIATION GRIERiB~H~RegioniiPhfladelphfar Office'ftheDirector(81/03/01)
| | ACCESSION NBR:8106090406 DOC ~ DATE! 81/06/05 NOTARIZED: NO DOCKE.T' FACIL:50 387 Susquehanna Steam Electrf c Stations Unf t 1 > Pennsyl va 0500~087 50 388 Susquehanna Steam Electr f c Statf one Unf t 2'P Pennsyl va 05 'I)038 AUTH',NAME AUTHOR AFFILIATTON CURTIS N ~ W ~ |
| | E Pennsyl vanf a Power L Lf ght Co ~ |
| | RECIP ~ NAMEl RECIPIENT AFFILIATION GRIERiB ~ H ~ Region ii Phfladelphfar Office'f the Director (81/03/01) |
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| ==SUBJECT:== | | ==SUBJECT:== |
| Interimdeficiency reptrelackofrequiredspecialconduitseparation forcertain-safety>>rel'ated electrical cfrcuftsr fnftfally repor'tedon810408Safetyrelatedelectrical circuitswillbecorrectly separated, DISTRIBUTION CODE'::BOI9S'OPIES RECEIVEDiLTR
| | Interim deficiency rept re lack of required special conduit separation for certain- safety>>rel'ated electrical cfrcuftsr fnftfally r epor'ted on 810408 Safety related electrical circuits will be correctly separated, DISTRIBUTION CODE':: BOI9S'OPIES RECEIVEDiLTR ~NCI./ SIZE TITLE,: Construction Deficiency Report (10CFR50 55K) ~ |
| ~NCI./SIZETITLE,:Construction Deficiency Report(10CFR50~55K)NOTES!Send IEE3copfesFSAR5al1amends,1cytBWR>>LRG PM(LRIB')SendIEE3copiesFSAR8allamends,icy:BWR~LRG PM(L~RIB)0500038705000388RECIPIENT ID'ODE/NAMEI ACTION:A/DLICENSNG04LICBR¹2LA06INTERNAL'SLBP/J',HARD EDO8STAFF19HYD/GEOBR22'E/EESMPA20OELD21QABR14STANDRDSDEY21COPIES'TTR'NCL1111111111111111111RECIPIENT'D CODE/NAME" LICBR¹2'C05STARKERS07D/DIRHUMFAC15'QUIP QUALBR11ILEOoLICQUAL'R12'RCPDR02'REV13,EGFILE01COPIESLTTR'NCI. | | NOTES!Send IEE 3 copfes FSAR 5 al 1 amends,1 cytBWR>>LRG PM(L RIB') 05000387 Send IEE 3 copies FSAR 8 all amends,i cy:BWR~LRG PM(L ~ RIB) 05000388 RECIPIENT COPIES' RECIPIENT'D COPIES ID'ODE/NAMEI TTR'NCL CODE/NAME" LTTR'NCI. |
| 111111f11111i.11111EXTERNAL:
| | ACTION: A/D LICENSNG 04 1 1 LIC BR ¹2'C 05 1 1 LIC BR ¹2 LA 06 1 1 STARKERS 07 1 1 INTERNAL'SLBP/J',HARD 1 D/DIR HUM 1 1 f |
| ACRSNSIC16.08161611LPDR0311gag101981$v'gTOTALNUMBER.OFCOPIESREQUIRED:
| | FAC15'QUIP EDO 8 STAFF 19 1 1 QUAL BR1 1 1 HYD/GEO BR 1 1 ILE Oo 1 1 22'E/EES 1 1 LIC QUAL'R 1 1 02' 12'RC MPA 20 1 1 PDR i. 1 OELD 21 1 1 REV 13 1 1 QA BR 14 1 1 ,EG FILE 01 1 1 STANDRDS DEY 21 1 1 EXTERNAL: ACRS 1 6. 16 16 LPDR 03 1 1 NSIC 08 1 1 gag 10 1981 TOTAL NUMBER. OF COPIES REQUIRED: LTTR ~$ v'g ENCL |
| LTTR~ENCL TWONORTHNINTHSTREET,ALLENTOWN, PA.18101PHONE~(215)7/0-5151NORMANW.CURTISVicepfesidenl-Engineeting dConstruction-Nuclear 7705381June5,1981Mr.BoyceH.GrierDirector, RegionIU.S.NuclearRegulatory Commission 631ParkAvenueKingofPrussia,PA19406r-'(gyes,
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| ',S1aI0rC0SUSQUEHANNA STEAMELECTRICSTATIONFINALREPORTOFADEFICIENCY RELATINGTOELECTRICAL SEPARATION ER's100450/100508 FILES840-4/900-10 PLA-827
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| ==DearMr.Grier:== | | TWO NORTH NINTH STREET, ALLENTOWN, PA. 18101 PHONE~ (215) 7/0-5151 NORMAN W. CURTIS Vice pfesidenl-Engineeting d Construction-Nuclear 770 5381 June 5, 1981 r Mr. Boyce H. Grier Director, Region U. S. |
| ThisletterservestoprovidetheCommission withaninterimreportofadeficiency involving thelackofrequiredspecialconduitseparation forcertainsafety-related electrical circuits.
| | I Nuclear Regulatory Commission |
| Thedeficiency wasoriginally reportedtotheNRCiTLGeneralElectricletterTRR-26-81/MPN-065-91, datedApril8,1981undertheprovisions of10CFR21.Recognizing its'esponsibility toreviewthecondition forreportability under10CFR50.55(e),
| | -'(gyes, ', |
| PP&Ldetermined thisdeficiency tobepotentially reportable. | | 631 Park Avenue King of Prussia, PA 19406 0r S 1aI C0 SUSQUEHANNA STEAM ELECTRIC STATION FINAL REPORT OF A DEFICIENCY RELATING TO ELECTRICAL SEPARATION ER's 100450/100508 FILES 840-4/900-10 PLA-827 |
| Consequently, Mr.C.Z.McVickerofPPaLsoadvisedNRCRegionIInspector Mr.L.Narrowbytelephone onApril14,1981.Theattachment tothislettercontainsadesription ofthedeficiency, itscause,safetyimplications, andthecorrective actiontakenandplanned.Theinformation issubmitted asafinalreportpursuanttotheprovisions of10CFR50.55(e). | | |
| WetrusttheCommission willfindtheinformation forwarded bythislettertobesatisfactory.
| | ==Dear Mr. Grier:== |
| Verytrulyyours,N.W.CurtisVicePresident-Engineering 6Construction-Nuclear yoi~5FLW/WHG/vs'.
| | |
| PENNSYLVANIA POWERiLLIGHTCOMPANY Mr.BoyceH.Griercc:Mr.VictorStello(15)Director-Office ofinspection | | This letter serves to provide the Commission with an interim report of a deficiency involving the lack of required special conduit separation for certain safety-related electrical circuits. The deficiency was originally reported to the NRC iTL General Electric letter TRR-26-81/MPN-065-91, dated April 8, 1981 under the provisions of 10 CFR 21. Recognizing its to review the condition for reportability under 10 CFR 50.55(e), 'esponsibility PP&L determined this deficiency to be potentially reportable. Consequently, Mr. C. Z. McVicker of PPaL so advised NRC Region I Inspector Mr. L. Narrow by telephone on April 14, 1981. |
| &Enforcement U.S.NuclearRegulatory Commission Washington, D.C.20555Mr.G.McDonald, Director(1)OfficeofManagement Znformation | | The attachment to this letter contains a desription of the deficiency, its cause, safety implications, and the corrective action taken and planned. |
| &ProgramControlU.S.NuclearRegulatory Commission Washington, D.C.20555Mr.GaryRhoadsU.S.NuclearRegulatory Commission P.O.Box52Shickshinny, PA18655 | | The information is submitted as a final report pursuant to the provisions of 10 CFR 50.55(e). |
| .~Attachment toPLA-827SUBJECTSpecialelectrical separation fortheG.E.suppliedPowerGeneration ControlComplexinvolving theHighPressureCoolantInjection (HPCX),ReactorCoreIsolation Cooling(RCIC),andAutomatic Depressurization Systems(ADS)asidentified inNRCZGEInformation Notice79>>32.DESCRIPTION OFDEFICIENCY Thedeficiency involvestheomissionofconduitonelectrical wiringtotheHPCXinboardsteamisolation valveE41-F002andRCICinboardsteamisolation valveE51-F007. | | We trust the Commission will find the information forwarded by this letter to be satisfactory. |
| Theinstallation ofthiscondui.tisrequiredtomeetaspecificrequirement oftheGeneralElectricspecification forelectrical separation, applicable toSusquehanna 162.Thisdeficiency relatestoboththeGEscopeofsupply(i.e.thePowerGeneration ControlComplex)andtheBechtelCorp.scopeofsupply(i.e.BalanceofPlant)forthesecircuits.
| | Very truly yours, N. W. Curtis yoi~ |
| Note:AlthoughGE'sPart21report(ref.TRR-26-81/MFN-065-81 dated4/8/81)includedADScircuitsinthescopeofthereporteddeficiency, asdidtheirgenericresponsetoNRCZ&EInformation Notice79-32,ADShasnotbeenincludedinthescopeofthi.sreportbecausetheSusquehanna ADSdesign,unlikeearliervintageplants,hastworedundant powerandlogictrainsandiscapableofoperation withafailureineitherdivision. | | Vice President-Engineering 6 Construction-Nuclear 5 FLW/WHG/vs'. |
| CAUSETheGeneralElectricspecification forelectrical separation applicable toSusquehanna SES,requiresthatconduitbeinstalled toprovidespecialseparation oftheHPCZandRCXCinboardsteamlineisolation valvecircuitsfromothercircuitsassignedtothesamedivision(seeattacheddiagramofFig.5ofG.E.Doc.22A3052).
| | PENNSYLVANIA POWER iL LIGHT COMPANY |
| Theintent,ofthisspecialseparation require-mentistoprovideconduitseparation ofthe"Division I-X"circuitfromotherDivisionXcircuitsandconduitsseparation ofthe"Division ZZ-X"circuitsfromotherDivisionZIcircuitstherebypreventing apostulated singleelectrical failurefromdisabling boththeHPCXandRCXCsystems.GEandBechtelCorp.,fortheirrespective scopesofsupply,failedtoincorporate thisspecialelectrical separation requirement intothedesignoutputdocuments theypreparedandissuedforthemanufacture andconstruction oftheSusquehanna HPCZandRCZCsystems.ANALYSISOFSAFETYIMPLICATIONS TheintentoftheGErequirement forspecialseparation usingconduitonthesubjectHPCXandRCICcircuitswastopreventapostulated singleelectrical failurefromdisabling boththeHPCXandRCICsystems.Thereisapossibility thatafirecouldcauseahot-short circuitinthecabletotheHPCXinboardisolation valve(Division I)resulting intheclosureofthisvalveandatthesametime,disabling theRCZCsystemwhichisessentially aDivisionXsystem.Thisscenariocould'result inalossofcapability inboththeHPCXandRCIC'Page1of2 Attachment toPLA-827systems.TheRCICsystemisdesignedtoprovideReactorMakeupWaterduringalossofoffsitepowerandtoestablish andmaintainreactorwaterlevelduringshutdownconditions.
| | |
| AlthoughtheADSwouldstillbeavailable intheeventofRCIC'systemfailure,itisnottheintendedfunctionoftheADStobeusedasabackuptoRCICduringareactorshutdown.
| | Mr. Boyce H. Grier cc: Mr. Victor Stello (15) |
| AtSusquehanna, theADSisprovidedwithtworedundant powerandlogictrainsandwouldalwaysbeavailable foralossofasingledivision.
| | Director-Office of inspection & Enforcement U. S. Nuclear Regulatory Commission Washington, D.C. 20555 Mr. G. McDonald, Director (1) |
| Therefore, nodeficiency existsintheADSdesign.Thishasbeenconfirmed throughdiscussions withGEinMay,1981.PPGLhasdetermined, however,thatthelackofinstalled conduittoprovideseparation fortheelectrical circuitstotheHPCIandRCICinboardisolation valvesdoesrepresent asignificant. | | Office of Management Znformation & Program Control U. S. Nuclear Regulatory Commission Washington, D.C. 20555 Mr. Gary Rhoads U. S. Nuclear Regulatory Commission P. O. Box 52 Shickshinny, PA 18655 |
| deficiency infinaldesignasreleasedforconstruction andistherefore reportable under10CFR50.55(e).CORRECTIVE ACTIONG.E.sitepersonnel havewrittenFieldDeviation Disposition Requests(FDDR-522-12 andFDDR-KRX-542-9) toenclosethecircuitsforvalveE41-F002frompanelH12P617tothePGCCtermination cabinetandthecircuitsforvalveE51-F007frompanelH12P617tothetermination cabinetinflexibleconduit.BechtelhasissuedDesignChangePackage(DCP)308.1tothefieldforthereworkrequiredtoenclosetheremainder oftheHPCIandRCXCinboardvalvecontrolcircuitsinconduit.TheBechtelandGEdesigndocuments identified abovewillprovidethedirection toinstalltheconduitnecessary toachievecompliance withthecitedspecialseparation recpxirement for'heHPCXandRCICsystems.Page2of2 Isolntion InputsTemp6FlowDivIMireu~yRCICLogicCabinetlncl.Timer)Isolation InputsTemp6Flo"DivIIMirawnyLnclai"urc IsolvalvesLogicCabinetI>>cl.TimurIRIGIRL~r-LDurrier+Isolation InputsTemp6FlowID~BIIS\~Barrier.nrnclosurcIsolValvesLogicCabinetIncl.TlcccrIsolation InputsTempSFlowIIPC'ogic Chbinc:t(I>>cl.Timer)PzDivIDCPoucrDC>ICCDivIMireuayDiv"II-X"ConduitACHCCRCICOtlicrIsolIlaolValveValveItartecStnrtciDivIIMirewayDivIIACPowerDivIMirew~ypiv"I-X"ConduitDivIACPoucrDivIIDCPowACYACCOther~lll'CIIsolIIsolValvelValveitrta'sPtnrtcrsDClICCDivIIMircway~rrcr-InN)VToRCICTurbFgpPDiv"II-X"ConduitTo/therDivIIIsolValvecDRIMELI,F-007ToOthe:iDivIIsclValvesDiv"I-X"Co>>duit'CF+~+'RVIy.LL. | | |
| DCToIIPCIF-003Turb0onhx0riZx0h)ICOMPEGNIB5IIPCJ:/RCIC Sl;PAIIATIOH SCIIEMEr~lanegC}}
| | . ~ |
| | Attachment to PLA-827 SUB JECT Special electrical separation for the G.E. supplied Power Generation Control Complex involving the High Pressure Coolant Injection (HPCX), Reactor Core Isolation Cooling (RCIC), and Automatic Depressurization Systems (ADS) as identified in NRC ZGE Information Notice 79>>32. |
| | DESCRIPTION OF DEFICIENCY The deficiency involves the omission of conduit on electrical wiring to the HPCX inboard steam isolation valve E41-F002 and RCIC inboard steam isolation valve E51-F007. The installation of this condui.t is required to meet a specific requirement of the General Electric specification for electrical separation, applicable to Susquehanna 1 6 2. This deficiency relates to both the GE scope of supply (i.e. the Power Generation Control Complex) and the Bechtel Corp. scope of supply (i.e. Balance of Plant) for these circuits. |
| | Note: Although GE's Part 21 report (ref. TRR-26-81/MFN-065-81 dated 4/8/81) included ADS circuits in the scope of the reported deficiency, as did their generic response to NRC Z&E Information Notice 79-32, ADS has not been included in the scope of thi.s report because the Susquehanna ADS design, unlike earlier vintage plants, has two redundant power and logic trains and is capable of operation with a failure in either division. |
| | CAUSE The General Electric specification for electrical separation applicable to Susquehanna SES, requires that conduit be installed to provide special separation of the HPCZ and RCXC inboard steam line isolation valve circuits from other circuits assigned to the same division (see attached diagram of Fig. 5 of G.E. Doc. 22A3052). The intent, of this special separation require-ment is to provide conduit separation of the "Division I-X" circuit from other Division X circuits and conduits separation of the "Division ZZ-X" circuits from other Division ZI circuits thereby preventing a postulated single electrical failure from disabling both the HPCX and RCXC systems. GE and Bechtel Corp., |
| | for their respective scopes of supply, failed to incorporate this special electrical separation requirement into the design output documents they prepared and issued for the manufacture and construction of the Susquehanna HPCZ and RCZC systems. |
| | ANALYSIS OF SAFETY IMPLICATIONS The intent of the GE requirement for special separation using conduit on the subject HPCX and RCIC circuits was to prevent a postulated single electrical failure from disabling both the HPCX and RCIC systems. There is a possibility that a fire could cause a hot-short circuit in the cable to the HPCX inboard isolation valve (Division I) resulting in the closure of this valve and at the same time, disabling the RCZC system which is essentially a Division X system. |
| | This scenario could'result in a loss of capability in both the HPCX and RCIC Page 1 of 2 |
| | |
| | Attachment to PLA-827 systems. The RCIC system is designed to provide Reactor Makeup Water during a loss of offsite power and to establish and maintain reactor water level during shutdown conditions. Although the ADS would still be available in the event of RCIC 'system failure, it is not the intended function of the ADS to be used as a backup to RCIC during a reactor shutdown. At Susquehanna, the ADS is provided with two redundant power and logic trains and would always be available for a loss of a single division. Therefore, no deficiency exists in the ADS design. This has been confirmed through discussions with GE in May, 1981. PPGL has determined, however, that the lack of installed conduit to provide separation for the electrical circuits to the HPCI and RCIC inboard isolation valves does represent a significant. deficiency in final design as released for construction and is therefore reportable under 10 CFR 50.55(e) . |
| | CORRECTIVE ACTION G.E. site personnel have written Field Deviation Disposition Requests (FDDR-522-12 and FDDR-KRX-542-9) to enclose the circuits for valve E41-F002 from panel H12P617 to the PGCC termination cabinet and the circuits for valve E51-F007 from panel H12P617 to the termination cabinet in flexible conduit. |
| | Bechtel has issued Design Change Package (DCP) 308.1 to the field for the rework required to enclose the remainder of the HPCI and RCXC inboard valve control circuits in conduit. |
| | The Bechtel and GE design documents identified above will provide the direction to install the conduit necessary to achieve compliance with the cited special separation recpxirement for'he HPCX and RCIC systems. |
| | Page 2 of 2 |
| | |
| | P Isolntion Isolation Isolation Isolation Inputs Inputs Inputs Inputs z Temp 6 Flow Temp 6 Flo" Temp 6 Flow Temp S Flow Div I RIG I |
| | I RL~ r Div II I D~ BIIS Mireu~y Mirawny \ |
| | L Durrier + ~Barrier |
| | .nr RCIC Logic Lnclai"urc Isol valves Isol Valves nclosurc IIPC'ogic Cabinet Logic Cabinet Logic Cabinet Chb inc: t lncl. Timer) (I>>cl. |
| | I>>cl. Timur Incl. Tlcccr Timer ) |
| | ~ rrc Div I r Mireuay Div II Div I p iv "I-X" Div II Div "II-X" Mireway Mirew~y Conduit Mircway -I Div I Conduit DC Poucr AC HCC Div II n DC Pow RCIC Otlicr Other~ lll'CI DC |
| | >ICC Isol I laol Div II Div I Isol IIsol DC lICC Valve I |
| | Valve AC Power AC Poucr Valve l Valve AC tarte c Stnrtci itrta'sP tnrtcrs YACC Div "II-X" Div "I-X" Conduit To /ther Co>>duit Div II To Othe:i Div I Isol Valvec Iscl 'C Valves 0 o |
| | N)V h n DC x |
| | 0 ri To Z To IIPCI RCIC Turb F gp P DRIMELI, F -007 F +~+'RVIy.LL. F-003 Turb x 0 |
| | I h) |
| | CO M PEGNIB 5 IIPCJ:/RCIC Sl;PAIIATIOH SCIIEME r~l a n |
| | eg C}} |
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|---|
Category:DEFICIENCY REPORTS (PER 10CFR50.55E & PART 21)
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Part 21 Rept Re Hilti Fastening Sys Anchor Bolts Failing to Meet Average Ultimate Tensile Loads.Initially Reported on 860509.Design Review & Resolutions of Installed Items Underway
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Part 21 Rept Re Possible Wiring Defect in Fabricated Primer Chamber Assemblies for Standby Liquid Control Valves. Initially Reported on 860214.Listed Corrective Actions Will Be Completed by 860328
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Part 21 Rept Forwarding Ltr Sent to Customers Re Check Valves Missing Lock Welds on Hinge Supports or Hinge Support Capscrews,Per 851121 Request.List of Customers Receiving Ltr Also Encl
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Revised Final Deficiency Rept Re RHR Throttling Valves. Initially Reported on 820316.Reversal of Valve Disks & Valves No Longer Considered Necessary
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PLA-2189, Final Part 21 Rept Re GE Reactor Mode Switch.Initially Reported on 830407.Mode Switch Design Modified,Per Franklin Inst Research Lab Recommendations1984-05-21021 May 1984
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ML20084C2851984-04-19019 April 1984
Final Deficiency Rept Re Waterhammer Loading of Scram Discharge Vol (SDV) Vent & Drain Lines After Opening SDV Vent & Drain Valves on Scram Reset.Initially Reported on 830628.Vent Line Supports Will Be Modified Prior to 841231
PLA-2180, Final Part 21/deficiency Rept Re Improper Relief Valve Settings,Design Pressures & Temps.Initially Reported on 831118.Calculations Performed Assure Lines Adequate for Intended Svc1984-04-19019 April 1984
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Part 21 Rept Re Failure of Crosby IMF-2 Solenoids Supplied by Ge.Initially Reported on 840403.Licensee & GE Jointly Developed Test Procedures to Bench Test Spares & Solenoids on Both Units.Testing Complete on Unit 1
PLA-2137, Revised Final Deficiency Rept Re Fraying of Hydrogen Recombiner Cables.Initially Reported on 830728.Fraying Caused by Handling Process for Shipment,Installation & Testing.Cables Repaired1984-03-23023 March 1984
Revised Final Deficiency Rept Re Fraying of Hydrogen Recombiner Cables.Initially Reported on 830728.Fraying Caused by Handling Process for Shipment,Installation & Testing.Cables Repaired
PLA-2140, Second Interim Deficiency Rept Re Base Metal Cracking in Angle Fittings.Initially Reported on 840206.Angle Fittings Added to Defective Device List & Conduit Installation Spec Revised.Also Reportable Per 10CFR211984-03-22022 March 1984
Second Interim Deficiency Rept Re Base Metal Cracking in Angle Fittings.Initially Reported on 840206.Angle Fittings Added to Defective Device List & Conduit Installation Spec Revised.Also Reportable Per 10CFR21
PLA-2074, Third Interim Deficiency Rept Re Electrical Separation Inside Multiple Division Junction & Pull Box.Initially Reported on 830721.Design Basis Criteria & Barrier Configuration Established.Also Reported Per Part 211984-03-20020 March 1984
Third Interim Deficiency Rept Re Electrical Separation Inside Multiple Division Junction & Pull Box.Initially Reported on 830721.Design Basis Criteria & Barrier Configuration Established.Also Reported Per Part 21
PLA-2120, Interim Part 21/deficiency Rept Re Base Metal Cracking in Fittings Used on Class IE Electrical Raceways & HVAC Supports.Initially Reported on 840206.Final Rept Expected Prior to Initial Criticality1984-03-0707 March 1984
Interim Part 21/deficiency Rept Re Base Metal Cracking in Fittings Used on Class IE Electrical Raceways & HVAC Supports.Initially Reported on 840206.Final Rept Expected Prior to Initial Criticality
PLA-2103, Final Deficiency Rept Re Cavitation of Jet Pumps Due to Induction Heating Stress Improvement Cooling.Initially Reported on 831206.No Erosion Found.Also Reportable Per Part 21.Item Not Reportable Per 10CFR50.55(e)1984-03-0606 March 1984
Final Deficiency Rept Re Cavitation of Jet Pumps Due to Induction Heating Stress Improvement Cooling.Initially Reported on 831206.No Erosion Found.Also Reportable Per Part 21.Item Not Reportable Per 10CFR50.55(e)
PLA-2075, Second Interim Deficiency Rept Re Improper Relief Valve Setting,Design Pressures & Design Temp within Several Sys. Initially Reported on 831118.Spec M-199 Revised & Code Data Repts Amended.Also Reported Per Part 211984-03-0202 March 1984
Second Interim Deficiency Rept Re Improper Relief Valve Setting,Design Pressures & Design Temp within Several Sys. Initially Reported on 831118.Spec M-199 Revised & Code Data Repts Amended.Also Reported Per Part 21
PLA-2089, Final Deficiency & Part 21 Repts Re Safety Parameter Display Sys Technology Energy Corp Model 156 Isolators.Initially Reported on 840106.Non-IE Power Supply Will Be Provided for Isolator Prior to End of First Refueling1984-02-27027 February 1984
Final Deficiency & Part 21 Repts Re Safety Parameter Display Sys Technology Energy Corp Model 156 Isolators.Initially Reported on 840106.Non-IE Power Supply Will Be Provided for Isolator Prior to End of First Refueling
PLA-2062, Final Deficiency Rept Re Bechtel Failure to Accomplish Design Verification of safety-related Power & Control Cables.Caused by Failure to Complete Required Cable Length Verification.Deficiency Not Reportable Per 10CFR50.55(e)1984-02-13013 February 1984
Final Deficiency Rept Re Bechtel Failure to Accomplish Design Verification of safety-related Power & Control Cables.Caused by Failure to Complete Required Cable Length Verification.Deficiency Not Reportable Per 10CFR50.55(e)
PLA-2073, Final Part 21 Rept Re Hydrogen Catalyst Used in Comsip Custom Line Model K-IV Containment Gas Monitoring Panels. Initially Reported on 840113.Comsip Redesigned Catalyst Will Be Installed1984-02-13013 February 1984
Final Part 21 Rept Re Hydrogen Catalyst Used in Comsip Custom Line Model K-IV Containment Gas Monitoring Panels. Initially Reported on 840113.Comsip Redesigned Catalyst Will Be Installed
PLA-2063, Interim Part 21 Rept Re Safety Parameter Display Sys Model 156 Isolators Mfg by Technology for Energy Corp (Tec). Initially Reported on 840106.All Tec Isolators Reviewed for Corrective Actions1984-02-0606 February 1984
Interim Part 21 Rept Re Safety Parameter Display Sys Model 156 Isolators Mfg by Technology for Energy Corp (Tec). Initially Reported on 840106.All Tec Isolators Reviewed for Corrective Actions
PLA-2045, Followup Deficiency Rept Re Mod of RHR Globe Valves F017A & FO17B to Enable Valves in Shutdown Cooling Mode to Perform W/O Adverse Cavitation & Vibration at Low Flow Rates.Initially Reported on 811112.Valves Replaced1984-01-25025 January 1984
Followup Deficiency Rept Re Mod of RHR Globe Valves F017A & FO17B to Enable Valves in Shutdown Cooling Mode to Perform W/O Adverse Cavitation & Vibration at Low Flow Rates.Initially Reported on 811112.Valves Replaced
PLA-2033, Interim Deficiency Rept Re Clamps on Control Rod Drive Insert/Withdraw Lines Not Providing Axial Restraint. Initially Reported on 831209.Design Mod to Pedestal Support Initiated.Also Reportable Per Part 211984-01-12012 January 1984
Interim Deficiency Rept Re Clamps on Control Rod Drive Insert/Withdraw Lines Not Providing Axial Restraint. Initially Reported on 831209.Design Mod to Pedestal Support Initiated.Also Reportable Per Part 21
PLA-2026, Interim Deficiency Rept Re GE Reactor Mode Switch.Proposed Redesign of Mode Switch by GE Rejected,Based on Results of Testing Conducted at Franklin Inst Research Lab.Alternate Switch Ordered Through Electroswitch.Final Rept by Apr 19841984-01-12012 January 1984
Interim Deficiency Rept Re GE Reactor Mode Switch.Proposed Redesign of Mode Switch by GE Rejected,Based on Results of Testing Conducted at Franklin Inst Research Lab.Alternate Switch Ordered Through Electroswitch.Final Rept by Apr 1984
PLA-2009, Final Deficiency Rept Re Standby Gas Treatment Sys (SGTS) Performance Not as Described in Fsar.Fsar Change Prepared to Indicate SGTS May Be Required to Maintain Secondary Containment Integrity1984-01-0909 January 1984
Final Deficiency Rept Re Standby Gas Treatment Sys (SGTS) Performance Not as Described in Fsar.Fsar Change Prepared to Indicate SGTS May Be Required to Maintain Secondary Containment Integrity
PLA-1990, Final Deficiency Rept Re Isolation of Nitrogen Makeup Sys. Permanent Mod Consists of Rerouting Drywell & Wetwell Nitrogen Makeup Lines to Spare Penetrations.Divisionalized Isolation Valves Will Be Installed1983-12-30030 December 1983
Final Deficiency Rept Re Isolation of Nitrogen Makeup Sys. Permanent Mod Consists of Rerouting Drywell & Wetwell Nitrogen Makeup Lines to Spare Penetrations.Divisionalized Isolation Valves Will Be Installed
PLA-1946, Interim Deficiency Rept Re Bechtel Failure to Accomplish Design Verification of safety-related Power & Control Cables.Bechtel Completed & Documented Required Cable Length Verification & Calculations1983-12-30030 December 1983
Interim Deficiency Rept Re Bechtel Failure to Accomplish Design Verification of safety-related Power & Control Cables.Bechtel Completed & Documented Required Cable Length Verification & Calculations
PLA-1991, Final Deficiency Rept Re Cracks in Pacific Scientific PSA-1 & PSA-3 Snubber Capstan Springs.Caused by Improper Spring Forming.Snubbers Will Be Corrected Prior to Completion of First Refueling Outage.Also Reported Per Part 211983-12-27027 December 1983
Final Deficiency Rept Re Cracks in Pacific Scientific PSA-1 & PSA-3 Snubber Capstan Springs.Caused by Improper Spring Forming.Snubbers Will Be Corrected Prior to Completion of First Refueling Outage.Also Reported Per Part 21
PLA-2000, Interim Deficiency Rept Re Electrical Sys Separation in Multiple Div Pull & Junction Boxes.One Box Identified Containing Redundant Channel C & D Circuits Insufficiently Separated by Approved Barrier1983-12-27027 December 1983
Interim Deficiency Rept Re Electrical Sys Separation in Multiple Div Pull & Junction Boxes.One Box Identified Containing Redundant Channel C & D Circuits Insufficiently Separated by Approved Barrier
PLA-2006, Interim Part 21 Rept Re Improper Relief Valve Settings & Design Pressures & Temps Found in Hpci,Rcic,Rhr,Core Spray & Essential Svc Water Sys.Initially Reported on 831118. Hydrotests Performed1983-12-20020 December 1983
Interim Part 21 Rept Re Improper Relief Valve Settings & Design Pressures & Temps Found in Hpci,Rcic,Rhr,Core Spray & Essential Svc Water Sys.Initially Reported on 831118. Hydrotests Performed
PLA-1987, Updated Interim Deficiency Rept Re Scram Discharge Vol Vent & Drain Valve Waterhammer.Testing & Subsequent Analysis Will Be Completed in Mar 1984.Util Will Submit Final Rept by Apr 19841983-12-14014 December 1983
Updated Interim Deficiency Rept Re Scram Discharge Vol Vent & Drain Valve Waterhammer.Testing & Subsequent Analysis Will Be Completed in Mar 1984.Util Will Submit Final Rept by Apr 1984
PLA-1967, Final Deficiency Rept Re Suppression Pool Temp Monitoring Sys (Spotmos).Initially Reported on 821015.Modified Installation Configuration Tested.Review of Test Results Will Be Completed by End of Mar 19841983-12-13013 December 1983
Final Deficiency Rept Re Suppression Pool Temp Monitoring Sys (Spotmos).Initially Reported on 821015.Modified Installation Configuration Tested.Review of Test Results Will Be Completed by End of Mar 1984
PLA-1968, Final Deficiency & Part 21 Repts Re Final Design of GE 7700 Series 250-volt Dc Control Ctrs.Plant Operating Procedures Revised to Include Methods of Clearing Obstructions as Provided by GE & Exam & Reforming of Draw Out Contacts1983-12-0505 December 1983
Final Deficiency & Part 21 Repts Re Final Design of GE 7700 Series 250-volt Dc Control Ctrs.Plant Operating Procedures Revised to Include Methods of Clearing Obstructions as Provided by GE & Exam & Reforming of Draw Out Contacts
1998-07-09
[Table view]
Category:TEXT-SAFETY REPORT
MONTHYEARML20217A9931999-09-30030 September 1999
NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data
ML17146B1741999-08-0303 August 1999
GL 96-06 Risk Assessment for Sses.
ML20206D3331999-04-27027 April 1999
SER of Individual Plant Examination of External Events Submittal on Susquehanna Steam Electric Station,Units 1 & 2. Staff Notes That Licensee IPEEE Complete with Regard to Info Requested by Suppl 4 to GL 88-20
ML20195B2381999-03-31031 March 1999
Redacted Version for 10CFR2.790 Request for Decommissioning Status Rept for Sses,Units 1 & 2
ML17164A8451998-10-31031 October 1998
SSES Unit 1 Tenth Refueling & Insp Outage ISI Outage Summary Rept.
ML20236N6751998-07-0909 July 1998
Part 21 & Deficiency Rept Re Notification of Potential Safety Hazard from Breakage of Cast Iron Suction Heads in Apkd Type Pumps.Caused by Migration of Suction Head Journal Sleeve Along Lower End of Pump Shaft.Will Inspect Pumps
ML20217Q4891998-04-21021 April 1998
Rev 1 to Draft LDCN 2482, FSAR Chapter 13.4 & FSAR Chapter 17.2 Changes to Support ITS Implementation
ML18026A4931998-03-30030 March 1998
LER 97-007-01:on 971017,entry Into TS 3.0.3 Occurred to Allow Completion of Surveillance Testing of One Channel of Rbm.Caused by Failure of Components in LPRM Output to Rbm. Submitted TS Change Request to Extend LCO Action Statement
ML18026A5401998-02-28028 February 1998
Monthly Operating Repts for Feb 1998 for Susquehanna Steam Electric Station.W/980313 Ltr
ML18026A4891997-11-17017 November 1997
LER 97-007-00:on 971017,TS 3.0.3 Entry Voluntarily Made. Caused by Inadequate Post Maint Testing Following Earlier Work Associated W/Components.Failed Components Repaired, Replaced & Testing Completed
ML18017A2921997-10-28028 October 1997
1997 Nrc/Fema Observed Exercise.
ML17158C1861997-06-0505 June 1997
Proceedings of Intl Topical Meeting on Advanced Reactors Safety Vol II, on 970601-05
ML20140A9661997-05-29029 May 1997
Part 21 Rept Re Ksv Emergency Diesel Generator Power Piston Failure.Caused by Jacket Water in Combustion Chamber. Recommends That Users Verify That Crown Thickness at Valve Cutout Be 100 Minimum
ML18026A4781997-03-28028 March 1997
Rev 1 to Application of Anfb to ATRIUM-10 for Susquehanna Reloads.
ML20137G6261997-03-25025 March 1997
Svcs Part 21 Rept Re Emergency Generators Installed at Zion Station Which Developed Significant Drop in Crankcase Lube Oil Level.Caused by Crack in Liner Wall,Allowing Jacket Water to Enter Chamber
ML20155F7661996-07-25025 July 1996
Partially Deleted Job Number 739619-96, Investigation of E Diesel Breaker Misalignment
ML20155F7491996-07-24024 July 1996
Independent Safety Evaluation Svcs Project Rept 3-96, Investigation of E Diesel Generator In-Operability Event
ML20117G4641996-05-14014 May 1996
Part 21 Rept Re Cooper Bessemer Reciprocating Products,Div of Cooper Cameron Corp,Issued Ltr to Define Utils/Plants Containing Similar Equipment as Supplied on Cooper Bessemer Ksv & Enterprise Dsr EDGs
ML18026A5961996-01-0202 January 1996
LER 95-013-00:on 951119,thermally Induced Pressure Locking of HPCI Valve Occurred Under Bonnet Pressure of 3,000-7,000 Psig.Damaged HPCI Injection Valve repaired.W/960102 Ltr
ML18017A0511995-11-30030 November 1995
Monthly Operating Repts for Nov 1995 for SSES Units 1 & 2. W/951215 Ltr
ML20092H7641995-08-31031 August 1995
Monthly Operating Repts for Aug 1995 for Susquehanna Ses
ML17158A8771995-08-15015 August 1995
Exercise Manual.
ML17158A8061995-07-14014 July 1995
Books 1 & 2 of ISI Outage Summary Rept SSES Unit 1 8th Refuel Outage.
ML18017A0461995-07-0707 July 1995
LER 95-008-00:on 950609,shift Average Licensed Core Thermal Power Was Exceeded.Caused by Failed Instrumentation Drift. Repaired & Recalibrated Subject Instrumentation
ML17164A6631995-04-11011 April 1995
Impact of Extending T-10 AOT from 3 to 7 Days.
ML17164A5871995-01-31031 January 1995
Monthly Operating Repts for Jan 1995 for Susquehanna Ses
ML18026A5351994-10-31031 October 1994
SSES Unit 1 & 2 MSIV Leakage Alternate Treatment Method Seismic Evaluation. W/One Oversize Drawing
ML17158A4821994-08-23023 August 1994
ISI Outage Summary Rept Unit 2 6th Refueling Outage, Books 1 & 2 of 2
ML17158A2391994-04-0505 April 1994
Books 1 & 2 of SSES Unit 1 Seventh Refueling & Insp Outage ISI Outage Summary Rept.
ML18017A2701993-12-31031 December 1993
PP&L Annual Rept 1993.
ML17158A2651993-12-31031 December 1993
Allegheny Electric Cooperative,Inc Annual Rept 1993.
ML17158A1631993-12-0909 December 1993
Remote Indication of Spent Fuel Pool Level & Temperature.
ML18026A4281993-08-16016 August 1993
PP&L Response to NRC Concerns Re Loss of Spent Fuel Pool Cooling Following Loca,Sses,Units 1 & 2.
ML18026A4261993-06-0909 June 1993
LER 90-007-01:on 900705,primary Power Supply to RPS a Power Distribution Panel Lost When One Electrical Protection Assembly (EPA) Breaker Tripped.Epa Logic Cards Reviewed & RPS Power Supply Will Be redesigned.W/930609 Ltr
ML17157C2441993-02-28028 February 1993
Monthly Operating Rept for Feb 1993 for Susquehanna Steam Electric Station,Units 1 & 2
ML18017A2031993-02-0101 February 1993
Books 1 & 2 of Unit 2 Fifth Refueling & Insp Outage,Isi Outage Summary Rept.
ML20044C2741993-01-31031 January 1993
Corrected Monthly Operating Rept for Jan 1993 for Susquehanna Steam Electric Station,Unit 2,consisting of Info on Unit Shutdowns & Power Reductions
ML17157C3691992-12-31031 December 1992
PP&L Annual Rept 1992.
ML20056C3941992-12-31031 December 1992
Allegheny Electric Cooperative,Inc Annual Rept 1992
ML18017A0421992-12-14014 December 1992
Suppl to 921127 Part 21 Rept Re High Air Concentration in Reactor Bldg Making Area Uninhabitable for Retrieving Air Filters,Per NUREG-0737,Item II.F.1.Util Current Position Re Fuel Pool Cooling Issues Contrary to Reg Guide 1.3
ML18026A2481992-11-27027 November 1992
Part 21 Rept Re Substantial Safety Hazard in Design of Facility for Loss of Normal Spent Fuel Pool Cooling
ML18026A4231992-11-17017 November 1992
LER 92-016-00:on 920416,discovered That Existing Analysis for Two Spent Fuel Storage Pools Did Not Reflect Current Fuel Design & Plant Operation.Caused by Failure to Modify FSAR Analysis.Fsar Will Be revised.W/921117 Ltr
ML17157C1421992-10-21021 October 1992
Engineering Assessment of Fuel Pool Cooling Piping EDR-G20020.
ML17157C1411992-08-31031 August 1992
Loss of Fuel Pool Cooling Event Evaluation.
ML17157C1401992-08-31031 August 1992
Review of Fuel Pool Cooling During Postulated Off-Normal & Accident Events SSES Units 1 & 2.
ML20082C4941992-08-14014 August 1992
Evaluation of Unit 1 & Unit 2 Derating of Power Cables in Raceways Wrapped W/Thermo-Lag Matl
ML17157C1381992-07-27027 July 1992
Safety Consequences of Boiling Spent Fuel Pool at Susquehanna Steam Electric Station.
ML17157B9331992-07-24024 July 1992
Sixth Refueling & Insp Outage Inservice Insp Outage Summary Rept, Books 1 & 2
ML20097D4681991-12-31031 December 1991
Pennsylvania Power & Light Company,1991 Annual Rept
ML18017A0391991-07-26026 July 1991
LER 91-010-00:on 910628,RWCU Isolated on Two Occassions Due to Actuations of Steam Leak Detection Instrumentation. Caused by Design Deficiency & Elevated Ambient Penetration Room Temps.Temp Modules replaced.W/910726 Ltr
1999-09-30
[Table view] |
Text
REGULATORY INFORMATION DISTRIBUTION SYSTEM. (RIDS)
ACCESSION NBR:8106090406 DOC ~ DATE! 81/06/05 NOTARIZED: NO DOCKE.T' FACIL:50 387 Susquehanna Steam Electrf c Stations Unf t 1 > Pennsyl va 0500~087 50 388 Susquehanna Steam Electr f c Statf one Unf t 2'P Pennsyl va 05 'I)038 AUTH',NAME AUTHOR AFFILIATTON CURTIS N ~ W ~
E Pennsyl vanf a Power L Lf ght Co ~
RECIP ~ NAMEl RECIPIENT AFFILIATION GRIERiB ~ H ~ Region ii Phfladelphfar Office'f the Director (81/03/01)
SUBJECT:
Interim deficiency rept re lack of required special conduit separation for certain- safety>>rel'ated electrical cfrcuftsr fnftfally r epor'ted on 810408 Safety related electrical circuits will be correctly separated, DISTRIBUTION CODE':: BOI9S'OPIES RECEIVEDiLTR ~NCI./ SIZE TITLE,: Construction Deficiency Report (10CFR50 55K) ~
NOTES!Send IEE 3 copfes FSAR 5 al 1 amends,1 cytBWR>>LRG PM(L RIB') 05000387 Send IEE 3 copies FSAR 8 all amends,i cy:BWR~LRG PM(L ~ RIB) 05000388 RECIPIENT COPIES' RECIPIENT'D COPIES ID'ODE/NAMEI TTR'NCL CODE/NAME" LTTR'NCI.
ACTION: A/D LICENSNG 04 1 1 LIC BR ¹2'C 05 1 1 LIC BR ¹2 LA 06 1 1 STARKERS 07 1 1 INTERNAL'SLBP/J',HARD 1 D/DIR HUM 1 1 f
FAC15'QUIP EDO 8 STAFF 19 1 1 QUAL BR1 1 1 HYD/GEO BR 1 1 ILE Oo 1 1 22'E/EES 1 1 LIC QUAL'R 1 1 02' 12'RC MPA 20 1 1 PDR i. 1 OELD 21 1 1 REV 13 1 1 QA BR 14 1 1 ,EG FILE 01 1 1 STANDRDS DEY 21 1 1 EXTERNAL: ACRS 1 6. 16 16 LPDR 03 1 1 NSIC 08 1 1 gag 10 1981 TOTAL NUMBER. OF COPIES REQUIRED: LTTR ~$ v'g ENCL
TWO NORTH NINTH STREET, ALLENTOWN, PA. 18101 PHONE~ (215) 7/0-5151 NORMAN W. CURTIS Vice pfesidenl-Engineeting d Construction-Nuclear 770 5381 June 5, 1981 r Mr. Boyce H. Grier Director, Region U. S.
I Nuclear Regulatory Commission
-'(gyes, ',
631 Park Avenue King of Prussia, PA 19406 0r S 1aI C0 SUSQUEHANNA STEAM ELECTRIC STATION FINAL REPORT OF A DEFICIENCY RELATING TO ELECTRICAL SEPARATION ER's 100450/100508 FILES 840-4/900-10 PLA-827
Dear Mr. Grier:
This letter serves to provide the Commission with an interim report of a deficiency involving the lack of required special conduit separation for certain safety-related electrical circuits. The deficiency was originally reported to the NRC iTL General Electric letter TRR-26-81/MPN-065-91, dated April 8, 1981 under the provisions of 10 CFR 21. Recognizing its to review the condition for reportability under 10 CFR 50.55(e), 'esponsibility PP&L determined this deficiency to be potentially reportable. Consequently, Mr. C. Z. McVicker of PPaL so advised NRC Region I Inspector Mr. L. Narrow by telephone on April 14, 1981.
The attachment to this letter contains a desription of the deficiency, its cause, safety implications, and the corrective action taken and planned.
The information is submitted as a final report pursuant to the provisions of 10 CFR 50.55(e).
We trust the Commission will find the information forwarded by this letter to be satisfactory.
Very truly yours, N. W. Curtis yoi~
Vice President-Engineering 6 Construction-Nuclear 5 FLW/WHG/vs'.
PENNSYLVANIA POWER iL LIGHT COMPANY
Mr. Boyce H. Grier cc: Mr. Victor Stello (15)
Director-Office of inspection & Enforcement U. S. Nuclear Regulatory Commission Washington, D.C. 20555 Mr. G. McDonald, Director (1)
Office of Management Znformation & Program Control U. S. Nuclear Regulatory Commission Washington, D.C. 20555 Mr. Gary Rhoads U. S. Nuclear Regulatory Commission P. O. Box 52 Shickshinny, PA 18655
. ~
Attachment to PLA-827 SUB JECT Special electrical separation for the G.E. supplied Power Generation Control Complex involving the High Pressure Coolant Injection (HPCX), Reactor Core Isolation Cooling (RCIC), and Automatic Depressurization Systems (ADS) as identified in NRC ZGE Information Notice 79>>32.
DESCRIPTION OF DEFICIENCY The deficiency involves the omission of conduit on electrical wiring to the HPCX inboard steam isolation valve E41-F002 and RCIC inboard steam isolation valve E51-F007. The installation of this condui.t is required to meet a specific requirement of the General Electric specification for electrical separation, applicable to Susquehanna 1 6 2. This deficiency relates to both the GE scope of supply (i.e. the Power Generation Control Complex) and the Bechtel Corp. scope of supply (i.e. Balance of Plant) for these circuits.
Note: Although GE's Part 21 report (ref. TRR-26-81/MFN-065-81 dated 4/8/81) included ADS circuits in the scope of the reported deficiency, as did their generic response to NRC Z&E Information Notice 79-32, ADS has not been included in the scope of thi.s report because the Susquehanna ADS design, unlike earlier vintage plants, has two redundant power and logic trains and is capable of operation with a failure in either division.
CAUSE The General Electric specification for electrical separation applicable to Susquehanna SES, requires that conduit be installed to provide special separation of the HPCZ and RCXC inboard steam line isolation valve circuits from other circuits assigned to the same division (see attached diagram of Fig. 5 of G.E. Doc. 22A3052). The intent, of this special separation require-ment is to provide conduit separation of the "Division I-X" circuit from other Division X circuits and conduits separation of the "Division ZZ-X" circuits from other Division ZI circuits thereby preventing a postulated single electrical failure from disabling both the HPCX and RCXC systems. GE and Bechtel Corp.,
for their respective scopes of supply, failed to incorporate this special electrical separation requirement into the design output documents they prepared and issued for the manufacture and construction of the Susquehanna HPCZ and RCZC systems.
ANALYSIS OF SAFETY IMPLICATIONS The intent of the GE requirement for special separation using conduit on the subject HPCX and RCIC circuits was to prevent a postulated single electrical failure from disabling both the HPCX and RCIC systems. There is a possibility that a fire could cause a hot-short circuit in the cable to the HPCX inboard isolation valve (Division I) resulting in the closure of this valve and at the same time, disabling the RCZC system which is essentially a Division X system.
This scenario could'result in a loss of capability in both the HPCX and RCIC Page 1 of 2
Attachment to PLA-827 systems. The RCIC system is designed to provide Reactor Makeup Water during a loss of offsite power and to establish and maintain reactor water level during shutdown conditions. Although the ADS would still be available in the event of RCIC 'system failure, it is not the intended function of the ADS to be used as a backup to RCIC during a reactor shutdown. At Susquehanna, the ADS is provided with two redundant power and logic trains and would always be available for a loss of a single division. Therefore, no deficiency exists in the ADS design. This has been confirmed through discussions with GE in May, 1981. PPGL has determined, however, that the lack of installed conduit to provide separation for the electrical circuits to the HPCI and RCIC inboard isolation valves does represent a significant. deficiency in final design as released for construction and is therefore reportable under 10 CFR 50.55(e) .
CORRECTIVE ACTION G.E. site personnel have written Field Deviation Disposition Requests (FDDR-522-12 and FDDR-KRX-542-9) to enclose the circuits for valve E41-F002 from panel H12P617 to the PGCC termination cabinet and the circuits for valve E51-F007 from panel H12P617 to the termination cabinet in flexible conduit.
Bechtel has issued Design Change Package (DCP) 308.1 to the field for the rework required to enclose the remainder of the HPCI and RCXC inboard valve control circuits in conduit.
The Bechtel and GE design documents identified above will provide the direction to install the conduit necessary to achieve compliance with the cited special separation recpxirement for'he HPCX and RCIC systems.
Page 2 of 2
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