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| | issue date = 09/30/1985 | | | issue date = 09/30/1985 |
| | title = Notifies of Error in 10CFR50.46 LOCA Analyses Performed for Facilities.Input Error in TOODEE2 Code Used to Calculate Fuel Rod Heatup Resulted in Rod Decay Heat Power Too Low & Subsequent Underpredicted Cladding Temp.Part 21 Related | | | title = Notifies of Error in 10CFR50.46 LOCA Analyses Performed for Facilities.Input Error in TOODEE2 Code Used to Calculate Fuel Rod Heatup Resulted in Rod Decay Heat Power Too Low & Subsequent Underpredicted Cladding Temp.Part 21 Related |
| | author name = MALODY C | | | author name = Malody C |
| | author affiliation = SIEMENS POWER CORP. (FORMERLY SIEMENS NUCLEAR POWER | | | author affiliation = SIEMENS POWER CORP. (FORMERLY SIEMENS NUCLEAR POWER |
| | addressee name = MARTIN J B | | | addressee name = Martin J |
| | addressee affiliation = NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) | | | addressee affiliation = NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| | docket = 05000000, 05000261, 05000315 | | | docket = 05000000, 05000261, 05000315 |
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| {{#Wiki_filter:EQONNUCLEARCOMPANY,INC.2101HORNRAPIDSROAD.POBOX130.RICHLANDWA88352I50gi375-8100TEL%,-15.2878September 30,1985Mr.JohnB.MartinRegionalAdministrator, RegionVUnitedStatesNuclearRegulatory Commission 1450MariaLane,Suite210WalnutCreek,CA94596 | | {{#Wiki_filter:EQON NUCLEAR COMPANY, INC. |
| | 2101 HORN RAPIDS ROAD. PO BOX 130. RICHLAND WA 88352 I50gi 375-8100 TEL%,-15.2878 September 30, 1985 Mr. John B. Martin Regional Administrator, Region V United States Nuclear Regulatory Commission 1450 Maria Lane, Suite 210 Walnut Creek, CA 94596 |
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| ==SUBJECT:== | | ==SUBJECT:== |
| Notification ofErrorinLOCAAnalysesOearMr.Martin:Asreportedinatelephone conversation onSeptember 30,1985betweenMr.YuhasofRegionVandme,anerrorwasdiscovered inthe10CFR50.46lossofcoolantaccident(LOCA)analysesperformed byExxonNuclearfortheH.B.RobinsonUnit2andD.C.CookUnit1reactors. | | Notification of Error in LOCA Analyses Oear Mr. Martin: |
| TheerrorwasaninputerrorintheTOODEE2codewhichisusedtocalculate fuelrodheatup.Theerrorresultedintheroddecayheatpowerbeingtoolowwhichcausedthecalculated peakcladdingtemperature tobeunderpredicted.
| | As reported in a telephone conversation on September 30, 1985 between Mr. |
| Attachedisadetaileddescription oftheeffectoferrorforeachunitandtheresulting under-prediction inthepeakcladdingtemperatures.
| | Yuhas of Region V and me, an error was discovered in the 10 CFR 50.46 loss of coolant accident (LOCA) analyses performed by Exxon Nuclear for the H.B. |
| Allofthepressurized waterreactorsforwhichExxonNuclearprovidesLOCAanalyseshavebeenreviewed.
| | Robinson Unit 2 and D.C. Cook Unit 1 reactors. The error was an input error in the TOODEE2 code which is used to calculate fuel rod heatup. The error resulted in the rod decay heat power being too low which caused the calculated peak cladding temperature to be underpredicted. Attached is a detailed description of the effect of error for each unit and the resulting under-prediction in the peak cladding temperatures. |
| Theerrorwasverifiedtohaveoccurredintheanalysesforonlythesetwoplants.ForD.C.CookUnit1,thecalculation wasrerunwiththeerrorcorrected andusingmorerealistic valuesofthepelletdensityandinternalpressure.Thisanalysiswasincompliance withtherequirements of10CFR50.46.ForH.B.RobinsonUnit2,thecalculated PCTswiththeerrorcorrected wereabove2200F.Areduction inFqwhichcorresponds totheunderestimate oftherodpowerwasnecessary tomaintaincompliance withthe10CFR50.46requirements.
| | All of the pressurized water reactors for which Exxon Nuclear provides LOCA analyses have been reviewed. The error was verified to have occurred in the analyses for only these two plants. For D.C. Cook Unit 1, the calculation was rerun with the error corrected and using more realistic values of the pellet density and internal pressure . This analysis was in compliance with the requirements of 10 CFR 50.46. |
| AsrequiredbytheExxonNuclearprocedures, aHazardsReviewBoardwasconvenedonSeptember 28,1985whentheeffectoftheerrorshadbeendetermined.
| | For H.B. Robinson Unit 2, the calculated PCTs with the error corrected were above 2200 F. A reduction in Fq which corresponds to the underestimate of the rod power was necessary to maintain compliance with the 10 CFR 50.46 requirements. |
| TheBoardconcluded thattheaffectedutilitiesshouldbenotified, thattheyshouldinturnnotifytheNRC,andthatH;B.RobinsonUnit2shouldimmediately reducetheallowedFqasindicated intheattachment.
| | As required by the Exxon Nuclear procedures, a Hazards Review Board was convened on September 28, 1985 when the effect of the errors had been determined. The Board concluded that the affected uti lities should be notified, that they should in turn notify the NRC, and that H;B. Robinson Unit 2 should immediately reduce the allowed Fq as indicated in the attachment. |
| Basedonsubsequent conversations withtheaffectedutilities, theserecom-mendations havebeenfollowed.
| | Based on subsequent conversations with the affected utilities, these recom-mendations have been followed. |
| 851008030i 8Si002'.pDR'"AoaCXOS00>>iS"p,-.-"-PDR. | | " 851008030i p,- |
| Mr.J.Hartin(USNRC)September 30,1985Thisletterprovidesthewrittennotification usingtheprocedures givenin10CFR21.21(b).
| | pDR'" AoaCX . |
| Iftherearequestions, oriffurtherinformation isneeded,pleasecontactme.Sincerely, C.Malody,ManagerCorporate Licensinnaacc:Mr.R.DeYoung(3copies)(D/OIEUSNRC)Mr.J.Bell(AEPSC)Mr.T.Dresser(CPKL)
| | OS00>>iS 8Si002'. |
| Attachment ErrorinLOCA-ECCS AnalysisforH.B.RobinsonUnit2andD.C.CookUnit1Ref.:(1)XN-NF-84-72, "H.B.RobinsonUnit2LargeBreakLOCA-ECCS AnalysiswithIncreased EnthalpyRiseFactor,"ExxonNuclearCompany,July1984(2)XN-NF-84-72, Supp.1,"H.B.RobinsonUnit2LargeBreakLOCA-ECCSAnalysiswithIncreased EnthalpyRiseFactor:BreakSpectrumAnalysis,"
| | -"-PDR. |
| ExxonNuclearCompany,August1984.(3)XN-NF-84-72, Supp.2,"H.B.RobinsonUnit2LargeBreakLOCA-ECCSAnalysiswithIncreased EnthalpyRiseFactor:K(Z)Curve,"ExxonNuclearCompany,August1984(4)XN-NF-83-61, "D.C.CookUnit1LOCA-ECCS AnalysisforExtendedExposure,"
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| ExxonNuclearCompany,August1983(5)Letter,G.F.Owsley,Manager,ReloadLicensing Liaison(ENC)toRichardDeYoung,DirectorofInspection andEnforcement (USNRC),datedMarch22,1985(GFO:85:010)
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| TheLOCA-ECCS analysesforthereactorsH.B.RobinsonUni,t2andD.C.CookUnit1reportedintheabovereferences havebeenfoundtocontainanerror.TheerrorwasintheinputtothecodeTOODEE2.ThecodeTOODEE2calculates thethermalresponse(heatup)ofthehotfuelrodfollowing theendoftheblowdowntransient untilthecoretemperature transient isterminated.
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| Thefuelrodsintheanalysesweremodeledwitheightradialringsinthefuelpellet.Theerrorconsisted oftheassignment ofarelativedecayheatpowerdensityof0.0intheouterringofthefuelpelletandresultedincalculated peakcladtemperatures whichweretoolow.H.B.RobinsonUnit2Asummaryofthepeakcladtemperatures fortheH.B.RobinsonUnit2analysis, reportedinReferences 1,2and3,andofthecalculated peakcladtemperatures'ith theerrorcorrected ispresented intheattachedTable1.ThefirstthreecasesinTable1wereoriginally performed aspartofanexposuresensitivity study,andthefinaltwocaseswereperformed todefinetheaxialpowerpeakingfactordependence (K(2)curve).Ascanbeseenfromthetable,threeofthesecasesresultinpeakcladtemperatures greaterthan2200oFandthusexceedthe10CFR50.46criteria.
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| Ananalysiswasperformed todetermine anFqwhichwouldresultinpeakcladtemperatures lessthan2200oF.Thisrequiredareduction inFqof8Xwhichwasachievedbyareduction ofthehotrodpowerintheTOODEE2codeof8X.Thisisaconservative calculation becausetheFqintheblowdownportionofthetransient hasnotbeenreduced.Theinitialtemperatures atthestartoftheTOODEE2(heatup)calculation aretherefore conservative withrespecttotheFqintheTOODEE2calculation.
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| Areduction oftheFqintheblowdownportionofthetransient wouldresultinthecalculation ofevenlowertemperatures.
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| Theresultsofthesecalculations aresummarized inTable2.
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| TheFqlimitsforH.S.RobinsonUnit2whichwillresultinLOCA-ECCS calculational resultsinconformance withthe10CFR50.46criteriaareshowninTable3.Thelimitsaredividedintotwoexposurerangesconsistent withtheanalysis, 0to9MWD/kgand9MWD/kgto49MWD/kg.D.C.CookUnit1TheerrorintheD.C.CookUnit1analysis(References 4and5)occurredonlyinthecalculation forthecaseat48MWD/kg.Thecasesatlowerexposures donotcontaintheerror.Thecalculation inerrorwasrerunwiththeerrorcorrected andmorerealistic valuesforthepelletdensityandinternalrodpressure.
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| Thereanalysis resultedinapeakcladtemperature changefrom1827Fto2189oF,whichisstillincompliance with10CFR50.46.Thisrevisedcalculation isveryconservative inthatthestoredenergyusedinthecalculation isthepeakstoredenergyovertherange0to48MWD/kgratherthanalowervalueofstoredenergythatwouldbeappropriate forthe48MWD/kgexposureforthiscase.Additionally, itisourunderstanding thattheENC-designed fuelinD.C.CookUnit1isnotintheexposurerangeforwhichthiscalculation isapplicable.
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| Table1H.B.RobinsonUnit2ErrorinTOODEE2Input;RodRadialPowerDistribution CaseDescription (Exposure/Power Shape)PreviousPeakCladTemperature (oF)Corrected PeakCladTemperature (oF)BOL/Cosine 9MWD/kg/Cosine EOL/Cosine BOL/TopPeaked9MWD/kg/Top Peaked20421815178521972183>220019231888>2200>2200 Table2H.B.RobinsonUnit2Reanalysis withFq*.92inTOODEE2Calculation CaseDescription (Exposure/Power Shape)PeakCladTemperature
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| (<<)BOL/Cosine BOL/TopPeaked9MWD/kg/Top Peaked206421952187 Table3H.B.RobinsonUnit2LOCA-ECCS Limits0to9MWD/kgHotRodAveraeExposure9to49MWD/kgHotRodAveraeExposureX/L0.0000.5000.9161.000~F(Z)2.1302.1301.6900.8351.0001.0000.7930.392X/L0.0000.5000,9161.000~F(Z)2.3202.3201.7260.8351.0001.0000.7440.360 Attachment 2toAEP:NRC:0940B OCTOfm85Hj(ONUCLEARCOMPANY,INC.210tHORNRD8ROAO.POBOXI30,RCHLANO,WA 8835210O81318.81TLEX:tb2878Mr.JPropreIndiac/oOneRColuSUBJERef.:September 30,1985JSH:044:85 IIIltIsephL.8elltManager,D.C.CookUnit1a5NichiganElectricCompanyericanElectricPowerServiceCorp.',versidePlazaus,OH43216-6631 T:ErrorinLOCA/ECCS AnalysisforD.C.CookUnit1(1)XN-NF-83-61, "D.C.CookUnit1LOCA-KCCS AnalysisforExtendedExposure,"
| |
| ExxonNuclearCompany,August1983(2)Letter,G,F.Owsley,Manager,ReloadLicensing Liaison(ENC)toRichardOeYoung,DirectorofInspection andEnforcement (USNRC),datedMarch22,1985(GFO:85:010)
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| ==Dearr.8ell:== | | Mr. J. Hartin (USNRC) September 30, 1985 This letter provides the written notification using the procedures given in 10 CFR 21.21(b). If there are questions, or if further information is needed, please contact me. |
| ECCSerror)calcu)ofthhThefhpelletdensicalcuinthvalue~tempesunnathes0to;.4appropsdiscussed withMr.GeorgeJohn(AEP)onSeptember 28,1985,theLOCA-nalysisforD.C.CookUnit1reportedtin References 1and2containsanTheerrorwasintheinputtothecodeTOOOEE2.ThecodeTOODEE2atesthethermalresponse(heatup)ofithehotfuelrodfollowing theendblowdowntransientuntilthecoretemperature transient isterminated.
| | Sincerely, C. Malody, Manager Corporate Licensin naa cc: Mr. R. DeYoung (3 copies) (D/OIE USNRC) |
| elrodintheanalysiswasmodeledwitheightradialringsinthefuelTheerrorconsisted oftheassignment ofarelativedecayheatpoweryof0.0intheouterringofthefuelpellet.Thisresultedinaatedpeakcladtemperature whichwas'oolow.Theerroroccurredonlycalculation forthecaseat48MWD/kg.thecalculation inerrorwasrerunwiththeerrorcorrected andwiththeodpelletdensityincreased andtheinternalrodpressuredecreased toappropriate for48MWD/kg.Thiscalculation resultedinapeakcladatureof2189oFincompliance with10'CFR50.46.Thesecalculations areizedinTable1.Thiscalculation isstillveryconservative inthatoredenergyintheca'Iculation isth)peakstoredenergyovertherange8MWD/kgratherthanalowervalueofstoredenergythatwouldberiateforthe48MWD/kgexposureforthiscase.Additionally, itisourANASS<ATCOSEXXONCOIISaORATON I
| | Mr. J. Bell (AEPSC) |
| I~'SaIIS&&laI~IalMr.J.Bell(AEP)JSH:044:85 September 30,1985gfAttactIaa cc:4.J.M.Cleveland (AEP)Nr.M.P.Alexich(AEP)Hr.G.John(AEP)Mr.H.G.Shaw(ENC)Mr.R.A.Copeland(KNC)r.R.L.Heiks(ENC)understanding thattheENCfuelinO.C.CookUnit1isnotintheexposurerangeforwhichthiscalculation isapplicable. | | Mr. T. Dresser (CPKL) |
| Sincerely, J.S.Holm,ManagerPNSafetyAnalysisRAPID<go..<<~7PAGE~,Oag Table1O.C.CookUnit1ErrorinTOOOEE2Input;RodRadialPowerDistribution seOescritioneviousResult*PeakCladTemperature OF1827CrrectedResultwithincreased pelletdensityandreducedfuelrhdpressurel2189III*Thepreviousresultwasforacosinepowerdistribution at48,0NMD/kgexposure, Fq*l.82,reportedinReferences 1and2.}}
| | |
| | Attachment Error in LOCA-ECCS Analysis for H.B. Robinson Unit 2 and D.C. Cook Unit 1 Ref.: (1) XN-NF-84-72, "H.B. Robinson Unit 2 Large Break LOCA-ECCS Analysis with Increased Enthalpy Rise Factor," Exxon Nuclear Company, July 1984 (2) XN-NF-84-72, Supp. 1, "H.B. Robinson Unit 2 Large Break LOCA-ECCS Analysis with Increased Enthalpy Rise Factor: Break Spectrum Analysis," Exxon Nuclear Company, August 1984 . |
| | (3) XN-NF-84-72, Supp. 2, "H.B. Robinson Unit 2 Large Break LOCA-ECCS Analysis with Increased Enthalpy Rise Factor: K(Z) |
| | Curve," Exxon Nuclear Company, August 1984 (4) XN-NF-83-61, "D.C. Cook Unit 1 LOCA-ECCS Analysis for Extended Exposure," Exxon Nuclear Company, August 1983 (5) Letter, G.F. Owsley, Manager, Reload Licensing Liaison (ENC) to Richard DeYoung, Director of Inspection and Enforcement (USNRC), dated March 22, 1985 (GFO:85:010) |
| | The LOCA-ECCS analyses for the reactors H.B. Robinson Uni,t 2 and D.C. |
| | Cook Unit 1 reported in the above references have been found to contain an error. The error was in the input to the code TOODEE2. The code TOODEE2 calculates the thermal response (heatup) of the hot fuel rod following the end of the blowdown transient until the core temperature transient is terminated. |
| | The fuel rods in the analyses were modeled with eight radial rings in the fuel pellet. The error consisted of the assignment of a relative decay heat power density of 0.0 in the outer ring of the fuel pellet and resulted in calculated peak clad temperatures which were too low. |
| | H. B. Robinson Unit 2 A summary of the peak clad temperatures for the H.B. Robinson Unit 2 analysis, reported in References 1, 2 and 3, and of the calculated peak clad temperatures'ith the error corrected is presented in the attached Table 1. |
| | The first three cases in Table 1 were originally performed as part of an exposure sensitivity study, and the final two cases were performed to define the axial power peaking factor dependence (K(2) curve). As can be seen from the table, three of these cases result in peak clad temperatures greater than 2200oF and thus exceed the 10 CFR 50.46 criteria. |
| | An analysis was performed to determine an Fq which would result in peak clad temperatures less than 2200oF. This required a reduction in Fq of 8X which was achieved by a reduction of the hot rod power in the TOODEE2 code of 8X. This is a conservative calculation because the Fq in the blowdown portion of the transient has not been reduced. The initial temperatures at the start of the TOODEE2 (heatup) calculation are therefore conservative with respect to the Fq in the TOODEE2 calculation. A reduction of the Fq in the blowdown portion of the transient would result in the calculation of even lower temperatures. The results of these calculations are summarized in Table 2. |
| | |
| | The Fq limits for H.S. Robinson Unit 2 which will result in LOCA-ECCS calculational results in conformance with the 10 CFR 50.46 criteria are shown in Table 3. The limits are divided into two exposure ranges consistent with the analysis, 0 to 9 MWD/kg and 9 MWD/kg to 49 MWD/kg. |
| | D. C. Cook Uni t 1 The error in the D.C. Cook Unit 1 analysis (References 4 and 5) occurred only in the calculation for the case at 48 MWD/kg. The cases at lower exposures do not contain the error. The calculation in error was rerun with the error corrected and more realistic values for the pellet density and internal rod pressure. The reanalysis resulted in a peak clad temperature change from 1827 F to 2189oF, which is still in compliance with 10 CFR 50.46. |
| | This revised calculation is very conservative in that the stored energy used in the calculation is the peak stored energy over the range 0 to 48 MWD/kg rather than a lower value of stored energy that would be appropriate for the 48 MWD/kg exposure for this case. Additionally, it is our understanding that the ENC-designed fuel in D.C. Cook Unit 1 is not in the exposure range for which this calculation is applicable. |
| | |
| | Table 1 H.B. Robinson Unit 2 Error in TOODEE2 Input; Rod Radial Power Distribution Previous Peak Clad Corrected Peak Clad Case Description Temperature Temperature (Exposure/Power Shape) (oF) (oF) |
| | BOL/Cosine 2042 > 2200 9 MWD/kg/Cosine 1815 1923 EOL/Cosine 1785 1888 BOL/Top Peaked 2197 > 2200 9 MWD/kg/Top Peaked 2183 > 2200 |
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| | Table 2 H.B. Robinson Unit 2 Reanalysis with Fq*.92 in TOODEE2 Calculation Case Description Peak Clad Temperature (Exposure/Power Shape) (<<) |
| | BOL/Cosine 2064 BOL/Top Peaked 2195 9 MWD/kg/Top Peaked 2187 |
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| | Table 3 H.B. Robinson Unit 2 LOCA-ECCS Limits 0 to 9 MWD/kg 9 to 49 MWD/kg Hot Rod Avera e Exposure Hot Rod Avera e Exposure X/L ~F(Z) X/L ~F(Z) 0.000 2.130 1.000 0.000 2.320 1.000 0.500 2. 130 1.000 0.500 2.320 1.000 0.916 1.690 0.793 0,916 1. 726 0.744 1.000 0.835 0.392 1.000 0.835 0.360 to AEP:NRC:0940B OCTO f m85 Hj(O NUCLEAR COMPANY, INC. |
| | 210t HORN R D8 ROAO. PO BOX I30, RCHLANO,WA88352 10O81 318.81 TLEX: tb2878 September 30, 1985 JSH:044:85 I |
| | I I |
| | lt I |
| | Mr. J seph L. 8ell Propre t Manager, D.C. Cook Unit 1 Indi a a 5 Nichigan Electric Company c/o erican Electric Power Service Corp. ', |
| | One R verside Plaza Colu us, OH 43216-6631 SUBJE T: Error in LOCA/ECCS Analysis for D.C. Cook Unit 1 Ref.: (1) XN-NF-83-61, "D.C. Cook Unit 1 LOCA-KCCS Analysis for Extended Exposure," Exxon Nuclear Company, August 1983 (2) Letter, G,F. Owsley, Manager, Reload Licensing Liaison (ENC) to Richard OeYoung, Director of Inspection and Enforcement (USNRC), dated March 22, 1985 (GFO:85:010) |
| | |
| | ==Dear r. 8ell:== |
| | |
| | s discussed with Mr . George John (AEP) on September 28, 1985, the LOCA-ECCS nalysis for D.C. Cook Unit 1 reportedtin References 1 and 2 contains an error) The error was in the input to the code TOOOEE2. The code TOODEE2 calcu) ates the thermal response (heatup) ofithe hot fuel rod following the end of thh blowdown tr ansient until the core temperature transient is terminated. |
| | The fh el rod in the analysis was modeled with eight radial rings in the fuel pellet The error consisted of the assignment of a relative decay heat power densi y of 0.0 in the outer ring of the fuel pellet. This resulted in a calcu ated peak clad temperature which was'oo low. The error occurred only in th calculation for the case at 48 MWD/kg. |
| | t he calculation in error was rerun with the error corrected and with the od pellet density increased and the internal rod pressure decreased to value~ appropriate for 48 MWD/kg. This calculation resulted in a peak clad tempe ature of 2189oF in compliance with 10'CFR 50.46. These calculations are sunna ized in Table 1. This calculation is still very conservative in that the s ored energy in the ca'Iculation is th) peak stored energy over the range 0 to;.4 8 MWD/kg rather than a lower value of stored energy that would be approp riate for the 48 MWD/kg exposure for this case. Additionally, it is our AN ASS <ATC OS EXXON COIISaORATON I |
| | |
| | I ~ 'Sa I IS& & la I ~ I al JSH:044:85 Mr. J. Bell (AEP) September 30, 1985 understanding that the ENC fuel in O.C. Cook Unit 1 is not in the exposure range for which this calculation is applicable. |
| | Sincerely, J. S. Holm, Manager PN Safety Analysis gf AttactIaa cc: 4 . J. M. Cleveland (AEP) |
| | Nr. M. P. Alexich (AEP) |
| | Hr. G. John (AEP) |
| | Mr. H. G. Shaw (ENC) |
| | Mr. R. A. Copeland (KNC) |
| | : r. R. L. Heiks (ENC) |
| | RAPID< go.. <<~7 PAGE ~ ,Oag |
| | |
| | Table 1 O.C. Cook Unit 1 Error in TOOOEE2 Input; Rod Radial Power Distribution Peak Clad Temperature se Oescri tion OF evious Result* 1827 C rrected Result with increased 2189 pellet density and reduced fuel rhd pressure l |
| | I I |
| | I |
| | *The previous result was for a cosine power distribution at 48,0 NMD/kg exposure, Fq*l.82, reported in References 1 and 2.}} |
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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217J4721999-10-15015 October 1999
Forwards NRC Physical Security Insp Repts 50-315/99-27 & 50-316/99-27 on 990920-24.Two Violations Noted & Being Treated as Ncvs,Consistent with App C of Enforcement Policy. Areas Examined Exempt from Disclosure,Per 10CFR73.21
ML20217D9241999-10-0808 October 1999
First Final Response to FOIA Request for Documents.Documents Listed in App a Being Released in Entirety
IA-99-379, First Final Response to FOIA Request for Documents.Documents Listed in App a Being Released in Entirety1999-10-0808 October 1999
First Final Response to FOIA Request for Documents.Documents Listed in App a Being Released in Entirety
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Forwards LER 99-023-00, Inadequate TS Surveillance Testing of ESW Pump ESF Response Time. Commitments Identified in LER Listed
ML20217D9361999-09-30030 September 1999
FOIA Request for Document Re Section 9.7 of SE by Directorate of Licensing,Us Ae Commission in Matter of Indiana & Michigan Electric Co & Indiana & Michigan Power Co,Dc Cook Nuclear Plan,Units 1 & 2
ML17326A1541999-09-20020 September 1999
Provides Notification of Change in Senior Licensed Operator Status.Operating Licenses for CR Smith,License SOP-30159-4 & Tw Welch,License SOP-30654-2 Are No Longer Required & Should Be Withdrawn
ML17326A1441999-09-17017 September 1999
Submits Trace on Second Shipment of Two Plant,Unit 2 Steam Generators.Info Re Shipment Submitted
ML17326A1261999-09-17017 September 1999
Forwards LER 99-022-00 Re Electrical Bus Degraded Voltage Setpoints Too Low for Safety Related Loads.Listed Commitment Identified in Submittal
ML17326A1531999-09-16016 September 1999
Submits Info Pertaining to Plant Proposed Operator Licensing Exam Requirements Through Yr 2003.NRC Form 536, Operator Licensing Exam Data, Which Provides Required Info Encl
ML17326A1101999-08-27027 August 1999
Forwards LER 99-021-00, GL 96-01 Test Requirements Not Met in Surveillance Tests. List of Commitments Identified in LER Provided
ML17326A0991999-08-26026 August 1999
Forwards LER 99-020-00,re EDGs Being Declared Inoperable. Commitments Made by Util Are Listed
ML20211G9851999-08-26026 August 1999
Ltr Contract:Task Order 244 Entitled, Technical Assistance in Evaluating Proposed Increase in Allowed Ultimate Heat Sink Temperature of Hb Robinson,Unit 2, Under NRC-03-95-026
ML17326A1221999-08-23023 August 1999
Forwards Revised Page 2 to 1998 Annual Environ Operating Rept, for DC Cook Nuclear Plant,Correcting Omission to App I
ML17326A0981999-08-23023 August 1999
Forwards fitness-for-duty Program Performance Data for Period of 990101-0630 for DC Cook Nuclear Plants,Units 1 & 2,per 10CFR26.71(d)
ML17326A0891999-08-16016 August 1999
Forwards LER 99-019-00,re Victoreen Containment High Range Monitors Not Beign Environmentally Qualified to Withstand post-LOCA Conditions.Commitments Made by Util Are Listed
ML17326A0811999-08-10010 August 1999
Notifies NRC of Changes in Commitments Made in Response to GL 98-01,supplement 1, Yr 2000 Readiness of Computer Sys Ar Npps, Dtd 990623
ML17326A0821999-08-0606 August 1999
Informs That Util Is Submitting Encl Scope & Objectives for 991026 DC Cook Nuclear Plant Emergency Plan Exercise to G Shear of NRC Plant Support Branch.Exercise Will Include Full State & County Participation
ML17326A1451999-08-0404 August 1999
Requests Withholding of WCAP-15246, Control Rod Insertion Following Cold Leg Lbloca.
ML17326A0751999-08-0404 August 1999
Forwards LER 98-029-01, Fuel Handling Area Ventilation Sys Inoperable Due to Original Design Deficiency. Supplemental Rept Represents Extensive Rev to Original LER & Replaces Rept in Entirely.Commitment Listed
ML17326A0721999-07-29029 July 1999
Forwards LER 99-018-00 Re Refueling Water Storage Tank Suction Motor Operated Valves Inoperable,Due to Inadequate Design.Listed Commitments Were Identified in LER
ML17326A0711999-07-27027 July 1999
Responds to 980123 RAI Re NRC GL 87-02, Verification of Seismic Adequacy of Mechanical & Electrical Equipment in Operating Reactors,Unresolved Safety Issue (USI) A-46.
ML17326A0631999-07-22022 July 1999
Forwards LER 98-014-03, Response to High-High Containment Pressure Procedure Not Consistent with Analysis of Record. Revised Info Marked by Sidebars in Right Hand Margin. Commitments Made by Util,Listed
ML17326A0601999-07-22022 July 1999
Forwards UFSAR, IAW 10CFR50.71(e) & Rept of Changes,Tests & Experiments as Required by 10CFR50.59(b)(2) for DC Cook Nuclear Plant,Units 1 & 2.Without UFSAR
ML17326A0311999-07-0101 July 1999
Forwards LER 99-004-01 Re Failure to Perform TS Surveillance Analyses of Reactor Coolant Chemistry with Fuel Removed. Commitments Made by Util Are Listed
ML20196K5961999-06-30030 June 1999
Ltr Contract:Task Order 40, DC Cook Extended Sys Regulatory Review Oversight Insp, Under Contract NRC-03-98-021
ML17326A0281999-06-28028 June 1999
Provides Response to 981116 & 960228 RAIs Re GL 92-01. Revised Pressurized Thermal Shock Evaluation Based on New Weld Chemistry Info & Copy of W Rept WCAP-15074, Evaluation of 1P3571 Weld Metal from Surveillance Programs... Encl
ML17326A0241999-06-23023 June 1999
Responds to GL 98-01,Suppl 1, Y2K Readiness of Computer Sys at Nuclear Power Plants. Y2K Readiness Disclosure for Plant & List of Commitments Encl
ML17326A0121999-06-18018 June 1999
Forwards LER 99-014-00 Re Requirement of TS 4.0.5 Not Met for Boron Injection Tank Bolting.Commitments Identified in Submittal Listed
ML17326A0111999-06-11011 June 1999
Provides Response to NRC RAI Re GL 97-01, Degradation of Crdm/Cedm Nozzle & Other Vessel Closure Head Penetrations.
ML17325B6401999-06-0101 June 1999
Forwards LER 99-013-00 Re Safety Injection & Centrifugal Charging Throttle Valve Cavitation During LOCA Could Lead to ECCS Pump Failure.Listed Commitments Identified in Submittal
ML17325B6281999-06-0101 June 1999
Forwards LER 99-S03-00,re Nonconforming Vital Area Barriers.Commitments Made by Util Are Listed
ML17325B6331999-05-28028 May 1999
Forwards LER 99-S02-00,re Vulnerability in Safeguard Sys That Could Allow Unauthorized or Undetected Access to Protected Area.Commitments Made by Util Are Listed
ML17265A8201999-05-24024 May 1999
Forwards LER 98-037-01,representing Extensive Rev to Original LER & Replacing Rept in Entirety.Listed Commitments Identified in Submittal
ML20207A9201999-05-21021 May 1999
Ack Receipt of 990319 Response to Notice of Violation & Proposed Imposition of Civil Penalty .On 981124, Licensee Remitted Check for Payment of Civil Penalties. Licensee Requests for Extension for Response,Granted
ML17325B6031999-05-21021 May 1999
Provides Response to NRC GL 98-04, Potential for Degradation of ECCS & Containment Spray Sys After LOCA Because of Const & Protective Coating Deficiencies & Foreign Matl in Containment.
ML17325B6111999-05-21021 May 1999
Forwards Annual Radioactive Effluent Release Rept for 980101-1231 for DC Cook Nuclear Plant,Units 1 & 2. Transmittal of Submittal Was Delayed Due to Administrative Error in Regulatory Affairs Dept
ML17325B5971999-05-20020 May 1999
Forwards LER 99-012-00,re Auxiliary Building ESF Ventilation Sys Not Being Capable of Maintaining ESF Room Temps post-accident.Commitment,listed
ML20206Q5281999-05-17017 May 1999
Responds to 990304 Request for Two Rail Routes to Be Used for Transport of Spent Fuel from Brunswick Steam Electric Plant,Southport,Nc & Hb Robinson Steam Electric Plant, Hartsville,Sc to Shearon Harris Npp,Near New Hill,Sc
ML17335A5281999-05-12012 May 1999
Forwards DC Cook Nuclear Plant Fitness for Duty Program Performance Dtd for six-month Period of 980701-1231,IAW 10CFR26.71(d).Info Was Delayed Due to Administrative Error in Regulatory Affairs Dept
ML17335A5271999-05-11011 May 1999
Forwards Details Re Sources & Levels of Insurance Maintained for DC Cook,Units 1 & 2,as of 990401,per 10CFR50.54(w)(3). Info Was Delayed Beyond Required Date Due to Internal Oversight
ML17325B5841999-05-10010 May 1999
Forwards LER 99-002-00 Re TS 4.0.5 Requirements Not Being Met Due to Improperly Performed Test.Commitments Identified in Ler,Listed
ML17325B5871999-05-0707 May 1999
Forwards Current Revs of Expanded Sys Readiness Review (Essr) Implementing Procedures,For Info Purposes to Support Current NRC Insps.Current Esrr Schedule Provided for Info Purposes,Reflecting Revised Target Dates
ML17325B5821999-05-0404 May 1999
Provides Addl Background,Description & Clarification of Previous & Revised Commitments Re UFSAR Revalidation Effort. Commitment Change Involved Alignment of UFSAR Revalidation Program Methodology to Strategy Contained in Current Plan
ML17325B5791999-05-0404 May 1999
Forwards LER 99-011-00,concerning Air Sys for EDG Not Supporting Long Term Operability.Commitments Made by Util Listed
ML17325B5741999-05-0303 May 1999
Forwards LER 99-010-00 Re RCS Leak Detection Sys Sensitivity Not in Accoradnce with Design Requirements.Listed Commitments Identified in Submittal
ML17325B5631999-04-22022 April 1999
Forwards Results of Independent Chemical Evaluations Performed from Sept 1997 Through Feb 1999,re Resolution of Issues Related to License Amend 227
ML17325B5561999-04-16016 April 1999
Forwards LER 99-006-00, Fuel Crane Loads Lifted Over SFP Could Impact Energies Greater than TS Limits, IAW 10CFR50.73.Submittal Was Delayed to Allow for Resolution of Questions.Commitment Made by Licensee,Listed
ML20205P0591999-04-14014 April 1999
Ninth Partial Response to FOIA Request for Documents.App Records Already Available in Pdr.Records in App T Encl & Being Made Available in Pdr.App U Records Being Released in Part (Ref FOIA Exemption 7).App V Records Withheld Entirely
ML17325B5451999-04-12012 April 1999
Forwards LER 99-009-00 Re as-found RHR Safety Relief Valve Lift Setpoint Greater than TS Limit.Commitments Identified in Submittal Listed
ML17325B5301999-04-0707 April 1999
Forwards LER 99-S01-01, Vulnerability in Locking Mechanism of Four Vital Area Gates, Per 10CFR50.73.Commitments Made by Util,Listed
1999-09-30
[Table view]
Category:INCOMING CORRESPONDENCE
MONTHYEARML17335A5511999-10-0707 October 1999
Forwards LER 99-023-00, Inadequate TS Surveillance Testing of ESW Pump ESF Response Time. Commitments Identified in LER Listed
ML20217D9361999-09-30030 September 1999
FOIA Request for Document Re Section 9.7 of SE by Directorate of Licensing,Us Ae Commission in Matter of Indiana & Michigan Electric Co & Indiana & Michigan Power Co,Dc Cook Nuclear Plan,Units 1 & 2
ML17326A1541999-09-20020 September 1999
Provides Notification of Change in Senior Licensed Operator Status.Operating Licenses for CR Smith,License SOP-30159-4 & Tw Welch,License SOP-30654-2 Are No Longer Required & Should Be Withdrawn
ML17326A1441999-09-17017 September 1999
Submits Trace on Second Shipment of Two Plant,Unit 2 Steam Generators.Info Re Shipment Submitted
ML17326A1261999-09-17017 September 1999
Forwards LER 99-022-00 Re Electrical Bus Degraded Voltage Setpoints Too Low for Safety Related Loads.Listed Commitment Identified in Submittal
ML17326A1531999-09-16016 September 1999
Submits Info Pertaining to Plant Proposed Operator Licensing Exam Requirements Through Yr 2003.NRC Form 536, Operator Licensing Exam Data, Which Provides Required Info Encl
ML17326A1101999-08-27027 August 1999
Forwards LER 99-021-00, GL 96-01 Test Requirements Not Met in Surveillance Tests. List of Commitments Identified in LER Provided
ML17326A0991999-08-26026 August 1999
Forwards LER 99-020-00,re EDGs Being Declared Inoperable. Commitments Made by Util Are Listed
ML17326A1221999-08-23023 August 1999
Forwards Revised Page 2 to 1998 Annual Environ Operating Rept, for DC Cook Nuclear Plant,Correcting Omission to App I
ML17326A0981999-08-23023 August 1999
Forwards fitness-for-duty Program Performance Data for Period of 990101-0630 for DC Cook Nuclear Plants,Units 1 & 2,per 10CFR26.71(d)
ML17326A0891999-08-16016 August 1999
Forwards LER 99-019-00,re Victoreen Containment High Range Monitors Not Beign Environmentally Qualified to Withstand post-LOCA Conditions.Commitments Made by Util Are Listed
ML17326A0811999-08-10010 August 1999
Notifies NRC of Changes in Commitments Made in Response to GL 98-01,supplement 1, Yr 2000 Readiness of Computer Sys Ar Npps, Dtd 990623
ML17326A0821999-08-0606 August 1999
Informs That Util Is Submitting Encl Scope & Objectives for 991026 DC Cook Nuclear Plant Emergency Plan Exercise to G Shear of NRC Plant Support Branch.Exercise Will Include Full State & County Participation
ML17326A1451999-08-0404 August 1999
Requests Withholding of WCAP-15246, Control Rod Insertion Following Cold Leg Lbloca.
ML17326A0751999-08-0404 August 1999
Forwards LER 98-029-01, Fuel Handling Area Ventilation Sys Inoperable Due to Original Design Deficiency. Supplemental Rept Represents Extensive Rev to Original LER & Replaces Rept in Entirely.Commitment Listed
ML17326A0721999-07-29029 July 1999
Forwards LER 99-018-00 Re Refueling Water Storage Tank Suction Motor Operated Valves Inoperable,Due to Inadequate Design.Listed Commitments Were Identified in LER
ML17326A0711999-07-27027 July 1999
Responds to 980123 RAI Re NRC GL 87-02, Verification of Seismic Adequacy of Mechanical & Electrical Equipment in Operating Reactors,Unresolved Safety Issue (USI) A-46.
ML17326A0631999-07-22022 July 1999
Forwards LER 98-014-03, Response to High-High Containment Pressure Procedure Not Consistent with Analysis of Record. Revised Info Marked by Sidebars in Right Hand Margin. Commitments Made by Util,Listed
ML17326A0601999-07-22022 July 1999
Forwards UFSAR, IAW 10CFR50.71(e) & Rept of Changes,Tests & Experiments as Required by 10CFR50.59(b)(2) for DC Cook Nuclear Plant,Units 1 & 2.Without UFSAR
ML17326A0311999-07-0101 July 1999
Forwards LER 99-004-01 Re Failure to Perform TS Surveillance Analyses of Reactor Coolant Chemistry with Fuel Removed. Commitments Made by Util Are Listed
ML17326A0281999-06-28028 June 1999
Provides Response to 981116 & 960228 RAIs Re GL 92-01. Revised Pressurized Thermal Shock Evaluation Based on New Weld Chemistry Info & Copy of W Rept WCAP-15074, Evaluation of 1P3571 Weld Metal from Surveillance Programs... Encl
ML17326A0241999-06-23023 June 1999
Responds to GL 98-01,Suppl 1, Y2K Readiness of Computer Sys at Nuclear Power Plants. Y2K Readiness Disclosure for Plant & List of Commitments Encl
ML17326A0121999-06-18018 June 1999
Forwards LER 99-014-00 Re Requirement of TS 4.0.5 Not Met for Boron Injection Tank Bolting.Commitments Identified in Submittal Listed
ML17326A0111999-06-11011 June 1999
Provides Response to NRC RAI Re GL 97-01, Degradation of Crdm/Cedm Nozzle & Other Vessel Closure Head Penetrations.
ML17325B6401999-06-0101 June 1999
Forwards LER 99-013-00 Re Safety Injection & Centrifugal Charging Throttle Valve Cavitation During LOCA Could Lead to ECCS Pump Failure.Listed Commitments Identified in Submittal
ML17325B6281999-06-0101 June 1999
Forwards LER 99-S03-00,re Nonconforming Vital Area Barriers.Commitments Made by Util Are Listed
ML17325B6331999-05-28028 May 1999
Forwards LER 99-S02-00,re Vulnerability in Safeguard Sys That Could Allow Unauthorized or Undetected Access to Protected Area.Commitments Made by Util Are Listed
ML17265A8201999-05-24024 May 1999
Forwards LER 98-037-01,representing Extensive Rev to Original LER & Replacing Rept in Entirety.Listed Commitments Identified in Submittal
ML17325B6111999-05-21021 May 1999
Forwards Annual Radioactive Effluent Release Rept for 980101-1231 for DC Cook Nuclear Plant,Units 1 & 2. Transmittal of Submittal Was Delayed Due to Administrative Error in Regulatory Affairs Dept
ML17325B6031999-05-21021 May 1999
Provides Response to NRC GL 98-04, Potential for Degradation of ECCS & Containment Spray Sys After LOCA Because of Const & Protective Coating Deficiencies & Foreign Matl in Containment.
ML17325B5971999-05-20020 May 1999
Forwards LER 99-012-00,re Auxiliary Building ESF Ventilation Sys Not Being Capable of Maintaining ESF Room Temps post-accident.Commitment,listed
ML17335A5281999-05-12012 May 1999
Forwards DC Cook Nuclear Plant Fitness for Duty Program Performance Dtd for six-month Period of 980701-1231,IAW 10CFR26.71(d).Info Was Delayed Due to Administrative Error in Regulatory Affairs Dept
ML17335A5271999-05-11011 May 1999
Forwards Details Re Sources & Levels of Insurance Maintained for DC Cook,Units 1 & 2,as of 990401,per 10CFR50.54(w)(3). Info Was Delayed Beyond Required Date Due to Internal Oversight
ML17325B5841999-05-10010 May 1999
Forwards LER 99-002-00 Re TS 4.0.5 Requirements Not Being Met Due to Improperly Performed Test.Commitments Identified in Ler,Listed
ML17325B5871999-05-0707 May 1999
Forwards Current Revs of Expanded Sys Readiness Review (Essr) Implementing Procedures,For Info Purposes to Support Current NRC Insps.Current Esrr Schedule Provided for Info Purposes,Reflecting Revised Target Dates
ML17325B5791999-05-0404 May 1999
Forwards LER 99-011-00,concerning Air Sys for EDG Not Supporting Long Term Operability.Commitments Made by Util Listed
ML17325B5821999-05-0404 May 1999
Provides Addl Background,Description & Clarification of Previous & Revised Commitments Re UFSAR Revalidation Effort. Commitment Change Involved Alignment of UFSAR Revalidation Program Methodology to Strategy Contained in Current Plan
ML17325B5741999-05-0303 May 1999
Forwards LER 99-010-00 Re RCS Leak Detection Sys Sensitivity Not in Accoradnce with Design Requirements.Listed Commitments Identified in Submittal
ML17325B5631999-04-22022 April 1999
Forwards Results of Independent Chemical Evaluations Performed from Sept 1997 Through Feb 1999,re Resolution of Issues Related to License Amend 227
ML17325B5561999-04-16016 April 1999
Forwards LER 99-006-00, Fuel Crane Loads Lifted Over SFP Could Impact Energies Greater than TS Limits, IAW 10CFR50.73.Submittal Was Delayed to Allow for Resolution of Questions.Commitment Made by Licensee,Listed
ML17325B5451999-04-12012 April 1999
Forwards LER 99-009-00 Re as-found RHR Safety Relief Valve Lift Setpoint Greater than TS Limit.Commitments Identified in Submittal Listed
ML17325B5301999-04-0707 April 1999
Forwards LER 99-S01-01, Vulnerability in Locking Mechanism of Four Vital Area Gates, Per 10CFR50.73.Commitments Made by Util,Listed
ML17325B5241999-04-0505 April 1999
Forwards Revs 0 & 1 to Cook Nuclear Plant Restart Plan, Dtd 980307 & 0407.Rev 5 Is Current Cook Nuclear Plant Restart & Supercedes Previous Revs in All Respects
ML17325B5121999-04-0101 April 1999
Forwards LER 99-007-00, Calculations Show That Divider Barrier Between Upper & Lower Containment Vols May Be Overstressed. Commitments Made by Util Are Listed
RA-99-0071, Forwards Rev 7 to Training & Qualification Plan & Rev 1 to Physical Security & Safeguards Contingency Plan for HBR2,per 10CFR50.54(p)(2).Changes Do Not Decrease Safeguards Effectiveness of Plan.Encl Withheld1999-04-0101 April 1999
Forwards Rev 7 to Training & Qualification Plan & Rev 1 to Physical Security & Safeguards Contingency Plan for HBR2,per 10CFR50.54(p)(2).Changes Do Not Decrease Safeguards Effectiveness of Plan.Encl Withheld
ML17325B5141999-03-30030 March 1999
Forwards Rept on Status of Decommissioning Funding.Attached Rept Includes Amount of Decommissioning Funds Estimated to Be Required Pursuant to 10CFR50.75(b) & (C)
ML17325B5191999-03-29029 March 1999
Forwards LER 99-001-00,re Degraded Component Cw Flow to Containment Main Steam Line Penetrations.Commitment, Listed
ML20204F6401999-03-19019 March 1999
Responds to NRC 981013 NOV & Proposed Imposition of Civil Penalty.Violations Cited in Subject NOV Were Initially Identified in Referenced Five Insp Repts.Corrective Actions: Ice Condensers Have Been Completely Thawed of Any Blockage
ML17325B4751999-03-18018 March 1999
Forwards LER 99-004-00,re Failure to Perform TS Surveillance Analyses of Reactor Coolant Chemistry with Fuel Removed. Commitment Made by Util,Listed
ML17325B4721999-03-18018 March 1999
Forwards LER 99-005-00,re Reactor Trip Breaker Manual Actuations During Rod Drop Testing Not Previously Reported. Listed Commitments Identified in Submittal
1999-09-30
[Table view]
Category:VENDOR/MANUFACTURER TO NRC
MONTHYEARML17328A3091990-06-20020 June 1990
Requests That Proprietary WCAP-12623 & Rev 4-P to CEN-313-P, Steam Generator Sleeving Rept & Steam Generator Tube Repair Using Leak Tight Sleeves, Respectively,Be Withheld from Public Disclosure (Ref 10CFR2.790)
ML20043C0771990-05-14014 May 1990
Requests That Proprietary WCAP-12576, Westinghouse Revised Thermal Design Procedure Instrument Uncertainty Methodology for American Electric Power DC Cook Unit 2 Nuclear Power Station, Be Withheld (Ref 10CFR2.790)
ML19325E9001989-10-19019 October 1989
Forwards Text of Info Communicated to All Util W/ Westinghouse NSSS Design on Pressurizer Safety Valve Set Pressure Deviation Info Request Response
ML19327A8441989-10-11011 October 1989
Forwards Pleadings,Motions & Orders Filed in Alchemie Reorganization Action.Alchemie Currently Preparing Reorganization Plan Which Will Serve as Framework for Future Company Business Activities
ML19327B2491989-10-0606 October 1989
Forwards Justification for Extension of Applicability of 890807 SER Re Acceptance of BAW-10175, Rod Exchange Methodology Topical Rept.
ML19327A8511989-10-0505 October 1989
Forwards Wh Arowood 890907 Ltr & Other Supplemental Info to Replace Info Previously Filed
ML20247F4121989-08-31031 August 1989
Advises That Response to Order Modifying Licenses & Order to Show Cause Why Licenses Should Not Be Revoked Will Be Sent. Responses to NRC Three Basic Questions Re Status of Licensee Finances & Rationale for Having License Provided
ML20246B1671989-08-0808 August 1989
Forwards Response to 890717 Request for Info Re Filings W/ Us Bankruptcy Court & Financial Capabilities.Ownership of Unclassified Equipment Remains Unchanged
ML20247Q5521989-05-24024 May 1989
Notifies That J Smelser Contract Ended,Effective 890517. Mgt of Company by Listed Board of Director Members Will Continue Until New Chief Executive Officer Selected
ML20247P8071989-04-0404 April 1989
Forwards Ltr in Which Concerns for Potential Significant Deficiency Under 10CFR21 Expressed
ML20247G4991989-03-30030 March 1989
Forwards Proprietary BAW-10175P, Rod Exchange Methodology, Developed for Calculating Parameters While Performing Control Rod Measurements Using Rod Exchange Technique to Be Used at Plants.Rept Withheld (Ref 10CFR2.790)
ML19324C3151989-02-20020 February 1989
Informs of Change in Vendor Plans for Inspecting Fuel Rods Containing Fuel Pellets Supplied by Ge.Ultrasonic Insp of Fuel Rods at Oconee 1 Found No Failed Rods in three-cycle, Discharged Fuel Assemblies
ML20235M8971989-02-10010 February 1989
Requests Withholding of Proprietary WCAP 12125, Catawba Unit 1 Evaluation for Tube Vibration Induced Fatigue, Per 10CFR2.790
ML20206D6241988-11-11011 November 1988
Forwards Projected Decommission Costs of Centrifuge Machines to Be Transferred to New Facility at Oliver Spring,Tn. Licensee Will Be Able to Offset Total Decommissioning Costs by Setting Aside Annual Decommissioning Cost Plus Reserve
ML20205Q6331988-11-0202 November 1988
Forwards Revised Proprietary Pages to BAW-10164P, RELAP5/Mod2-B&W,Advanced Computer Program for LWR LOCA & Non-LOCA Transient Analysis. Cso Film Boiling Correlation Replaced w/Condie-Bengston IV Correlation & Typos Corrected
ML20205P9511988-11-0101 November 1988
Forwards Rev 6 to Security Plan for Alchemie Facility 1 - Cpdf,Oak Ridge,Tn & Rev 6 to Security Plan for Alchemie Facility 2 - Oliver Springs,Oliver Springs,Tn. Revs Withheld (Ref 10CFR2.790(d))
ML20195E4291988-10-31031 October 1988
Forwards Numbers 1-5 of Rev 5 to Alchemie Security Plans. Requests Replacement of Pages 23-25 & 35 & Encl Rev Page
ML20205N3301988-10-27027 October 1988
Forwards Sketch of Feed Sys,Withdrawal Sys Refrigeration Cart & Typical Withdrawal,Large & Small,Pumping Stations
ML20195B6091988-10-21021 October 1988
Forwards Summary of B&W Fuel Co Position Re Small Break LOCA Calculations Contained in Util FSARs for Upcoming Reload Cores Which Will Contain Fuel Mfg by B&W
ML20154K3841988-09-12012 September 1988
Forwards Enhanced Facts Re Adequacy of Funding for Decontamination & Decommissioning (D&D) of Facilities. Intends to Establish Funded Reserve for D&D at Completion of Sale of Unclassified Equipment Not Needed for Production
ML20154E6451988-08-31031 August 1988
Requests That 880722 & 0812 Ltrs Re Security Sys Components Be Withheld from Public Disclosure (Ref 10CFR2.790(d))
ML20207L7651988-08-30030 August 1988
Requests That Proprietary WCAP 11935, McGuire Unit 2 Evaluation for Tube Vibration Induced Fatigue, Be Withheld from Public Disclosure (Ref 10CFR2.790)
ML20151H9381988-07-25025 July 1988
Forwards Proprietary BAW-10168P, B&W LOCA Evaluation Model for Recirculating Steam Generator Plants
ML17326B4001988-07-22022 July 1988
Forwards Listed Topical Repts,Providing Fuel Storage Facility Thermal Hydraulic & Criticality Analysis Results. W/O Stated Encls
ML20151M9211988-07-20020 July 1988
Responds to 880621 Request for Addl Info Re Enrichment of Naturally Occurring radioisotopes.Te-123 Will Be Enriching Approx 60 G to About 50%
ML20151L3321988-07-20020 July 1988
Forwards DOE Ltr Indicating Acceptance of Classified Matter. Licensee Agrees to Remove Any Toxic or Hazardous Matl from Classified Equipment Prior to Transfer to DOE for Disposal
ML20151G9761988-07-14014 July 1988
Forwards Rev 2 to Security Plan for Shipment of Classified Matter.Rev Withheld (Ref 10CFR2.790)
ML20150F1561988-07-0808 July 1988
Advises of Changes to Alchemie Board of Directors,Per 880618 Annual Stockholders Meeting
ML20155F4441988-05-0404 May 1988
Responds to NRC & Request at 880504 Meeting Describing GE Program to Reconfirm Design Adequacy of Associated Circuits in GE Bwrs.Upon Completion of Phases 1 & 2 of Evaluation of Bwrs,Ge Will Submit Summary by 881104
ML20151F7661988-03-29029 March 1988
Forwards Updated Pages to Proprietary BAW-10171P, REFLOD3B- Model for Multinode Core Reflooding Analysis, Per ECCS Methodology for Facilities Reloads.Mod Removes Henry Quench Temp Criteria & Potential Conflict in Logic.Pages Withheld
ML20234C2231987-12-28028 December 1987
Forwards Proprietary BAW-10164P, RELAP5/MOD2-B&W,Advanced Program for LWR LOCA & Non-LOCA Transient Analysis. Rept Describes Computer Code Used to Analyze RCS Behavior During Blowdown Phase of LOCA Transient.Rept Withheld
ML20234D1101987-12-14014 December 1987
Forwards Proprietary BAW-10171P, REFLOD3B,Model for Multinode Core Reflooding Analysis. Rept Describes Computer Code That B&W Will Be Using to Analyze RCS Behavior During Refill of LOCA Transient.Rept Withheld
ML20237C3611987-11-24024 November 1987
Requests That Proprietary Rev 2 to WCAP-11386, Byron/ Braidwood T-Hot Reduction Final Licensing Rept, Be Withheld (Ref 10CFR2.790(b)(4))
ML20236C0261987-10-22022 October 1987
Forwards Proprietary BAW-10165P, FRAP-T6-B&W:Computer Code for Transient Analysis of LWR Fuel Rods. Rept Describes Computer Code That B&W Will Be Using for Future Transient Analyses of LWR Fuel Rods.Rept Withheld (Ref 10CFR2.790)
LD-87-056, Forwards Summary of C-E Fuel Irradiated &/Or Discharged in 1986 on plant-by-plant Basis in Response to 870807 Request1987-09-18018 September 1987
Forwards Summary of C-E Fuel Irradiated &/Or Discharged in 1986 on plant-by-plant Basis in Response to 870807 Request
ML17334B1281987-08-25025 August 1987
Forwards Proprietary Version of Rev 1 to ANF-87-91(P), DC Cook 2 Debris-Resistant Lower Tie Plate Pressure Drop Test Rept, Supporting Operation of Facility.Rept Withheld (Ref 10CFR2.790(b))
ML20236H4971987-07-29029 July 1987
Forwards Draft Proprietary Topical Rept BAW-10166P, Beach Computer Code for Reflood Heat Transfer During Loca. Draft Submitted to Permit Interaction Between B&W,Nrc & Util. Affidavit for Withholding Encl.Fee Paid
ML20236B4141987-07-13013 July 1987
Forwards Proprietary Draft 1 of BAW-10168P, ...B&W LOCA Evaluation Model for Recirculating Steam Generator Plants, to Be Used for LOCA Analysis of Catawba & McGuire Reload Fuel Cycles.Rept Withheld (Ref 10CFR2.790).Fee Paid
ML20196K1621987-07-0909 July 1987
Partially Deleted Ltr Submitting Addl Info in Response to NRC 861230 & 870211 Requests Re 860918 Application for Exemption from Requirement to Convert from High Enriched U to Low Enriched U for Reactor Fuel,Per Generic Ltr 86-12
ML20215L0591987-06-22022 June 1987
Responds to Request for Assurance That Facility Neutron Monitoring Sys Design Similar to Design of Other Plants.List of Plants W/Similar Design,Already Reviewed & Approved by Nrc,Encl
ML17325A1271987-05-29029 May 1987
Forwards Proprietary XN-NF-87-31(P), Steamline Break Analysis for DC Cook Unit 2, Addressing Asymmetric Thermal Hydraulic & Neutronic Core Characteristics Resulting from Event.Rept Withheld (Ref 10CFR2.790)
ML20215D4081987-05-15015 May 1987
FOIA Request for Reactor Vessel Surveillance Capsule Repts for Turkey Point 4,Zion 2 & DC Cook 1
ML20237D2761987-04-27027 April 1987
Forwards List of 200 Parameters That Company Will Provide to Offsite Agencies,Per Request to D Schultz.List of Parameters That Will Be Available to NRC Via Zion Data Link During Coming Federal Field Exercise & Dryrun Also Encl
ML20212R4711987-04-15015 April 1987
Forward Proprietary Draft 1 to BAW-10171P, REFLOD3B,Model for Multinode Core Reflooding Analysis, for Review of ECCS Methodology for Plants Fuel Reloads,Per . W/Affidavit.Draft Withheld (Ref 10CFR2.790).Fee Paid
LD-87-017, Responds to 870327 Questions Re Steam Generator Tube Vibration Observed at Palo Verde Units 1 & 2.Definition & Scope of Program to Review Phenomenon Will Be Available for Review W/Nrc in Approx 90 Days1987-04-10010 April 1987
Responds to 870327 Questions Re Steam Generator Tube Vibration Observed at Palo Verde Units 1 & 2.Definition & Scope of Program to Review Phenomenon Will Be Available for Review W/Nrc in Approx 90 Days
ML20206E7851987-04-0202 April 1987
Confirms Intention to Use FOAM2 Computer Program as Part of ECCS Evaluation Model for Westinghouse Designed Plants. Review of Applicability of Code to Westinghouse Designed Plants Requested Prior to 880701
ML20237D6431987-03-25025 March 1987
Forwards Technical & Cost Proposal for Task Order 009, Continuing Exercise Support to NRC Operations Ctr, Electronic Transmission of Plant Parameters During Exercises, Under Contract NRC-05-86-170
ML20237D6681987-03-0404 March 1987
Forwards Revised Draft Statement of Work Proposed for Task Order 009, Continuing Exercise Support to NRC Operations Ctr,Electronic Transmission of Plant Parameters During Exercises, for Contract NRC-05-86-170
ML20237D6881987-02-14014 February 1987
Forwards Parameters & Computer Points That Author Will Be Attempting to Get Util to Make Available for Transmission to NRC During Federal Field Exercise - 2
ML20205G1591987-01-20020 January 1987
Requests Proprietary Responses to NRC Review Questions Re Resistance Temp Detector Bypass Elimination Be Withheld (Ref 10CFR2.790)
1990-06-20
[Table view] |
Text
EQON NUCLEAR COMPANY, INC.
2101 HORN RAPIDS ROAD. PO BOX 130. RICHLAND WA 88352 I50gi 375-8100 TEL%,-15.2878 September 30, 1985 Mr. John B. Martin Regional Administrator, Region V United States Nuclear Regulatory Commission 1450 Maria Lane, Suite 210 Walnut Creek, CA 94596
SUBJECT:
Notification of Error in LOCA Analyses Oear Mr. Martin:
As reported in a telephone conversation on September 30, 1985 between Mr.
Yuhas of Region V and me, an error was discovered in the 10 CFR 50.46 loss of coolant accident (LOCA) analyses performed by Exxon Nuclear for the H.B.
Robinson Unit 2 and D.C. Cook Unit 1 reactors. The error was an input error in the TOODEE2 code which is used to calculate fuel rod heatup. The error resulted in the rod decay heat power being too low which caused the calculated peak cladding temperature to be underpredicted. Attached is a detailed description of the effect of error for each unit and the resulting under-prediction in the peak cladding temperatures.
All of the pressurized water reactors for which Exxon Nuclear provides LOCA analyses have been reviewed. The error was verified to have occurred in the analyses for only these two plants. For D.C. Cook Unit 1, the calculation was rerun with the error corrected and using more realistic values of the pellet density and internal pressure . This analysis was in compliance with the requirements of 10 CFR 50.46.
For H.B. Robinson Unit 2, the calculated PCTs with the error corrected were above 2200 F. A reduction in Fq which corresponds to the underestimate of the rod power was necessary to maintain compliance with the 10 CFR 50.46 requirements.
As required by the Exxon Nuclear procedures, a Hazards Review Board was convened on September 28, 1985 when the effect of the errors had been determined. The Board concluded that the affected uti lities should be notified, that they should in turn notify the NRC, and that H;B. Robinson Unit 2 should immediately reduce the allowed Fq as indicated in the attachment.
Based on subsequent conversations with the affected utilities, these recom-mendations have been followed.
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Mr. J. Hartin (USNRC) September 30, 1985 This letter provides the written notification using the procedures given in 10 CFR 21.21(b). If there are questions, or if further information is needed, please contact me.
Sincerely, C. Malody, Manager Corporate Licensin naa cc: Mr. R. DeYoung (3 copies) (D/OIE USNRC)
Mr. J. Bell (AEPSC)
Mr. T. Dresser (CPKL)
Attachment Error in LOCA-ECCS Analysis for H.B. Robinson Unit 2 and D.C. Cook Unit 1 Ref.: (1) XN-NF-84-72, "H.B. Robinson Unit 2 Large Break LOCA-ECCS Analysis with Increased Enthalpy Rise Factor," Exxon Nuclear Company, July 1984 (2) XN-NF-84-72, Supp. 1, "H.B. Robinson Unit 2 Large Break LOCA-ECCS Analysis with Increased Enthalpy Rise Factor: Break Spectrum Analysis," Exxon Nuclear Company, August 1984 .
(3) XN-NF-84-72, Supp. 2, "H.B. Robinson Unit 2 Large Break LOCA-ECCS Analysis with Increased Enthalpy Rise Factor: K(Z)
Curve," Exxon Nuclear Company, August 1984 (4) XN-NF-83-61, "D.C. Cook Unit 1 LOCA-ECCS Analysis for Extended Exposure," Exxon Nuclear Company, August 1983 (5) Letter, G.F. Owsley, Manager, Reload Licensing Liaison (ENC) to Richard DeYoung, Director of Inspection and Enforcement (USNRC), dated March 22, 1985 (GFO:85:010)
The LOCA-ECCS analyses for the reactors H.B. Robinson Uni,t 2 and D.C.
Cook Unit 1 reported in the above references have been found to contain an error. The error was in the input to the code TOODEE2. The code TOODEE2 calculates the thermal response (heatup) of the hot fuel rod following the end of the blowdown transient until the core temperature transient is terminated.
The fuel rods in the analyses were modeled with eight radial rings in the fuel pellet. The error consisted of the assignment of a relative decay heat power density of 0.0 in the outer ring of the fuel pellet and resulted in calculated peak clad temperatures which were too low.
H. B. Robinson Unit 2 A summary of the peak clad temperatures for the H.B. Robinson Unit 2 analysis, reported in References 1, 2 and 3, and of the calculated peak clad temperatures'ith the error corrected is presented in the attached Table 1.
The first three cases in Table 1 were originally performed as part of an exposure sensitivity study, and the final two cases were performed to define the axial power peaking factor dependence (K(2) curve). As can be seen from the table, three of these cases result in peak clad temperatures greater than 2200oF and thus exceed the 10 CFR 50.46 criteria.
An analysis was performed to determine an Fq which would result in peak clad temperatures less than 2200oF. This required a reduction in Fq of 8X which was achieved by a reduction of the hot rod power in the TOODEE2 code of 8X. This is a conservative calculation because the Fq in the blowdown portion of the transient has not been reduced. The initial temperatures at the start of the TOODEE2 (heatup) calculation are therefore conservative with respect to the Fq in the TOODEE2 calculation. A reduction of the Fq in the blowdown portion of the transient would result in the calculation of even lower temperatures. The results of these calculations are summarized in Table 2.
The Fq limits for H.S. Robinson Unit 2 which will result in LOCA-ECCS calculational results in conformance with the 10 CFR 50.46 criteria are shown in Table 3. The limits are divided into two exposure ranges consistent with the analysis, 0 to 9 MWD/kg and 9 MWD/kg to 49 MWD/kg.
D. C. Cook Uni t 1 The error in the D.C. Cook Unit 1 analysis (References 4 and 5) occurred only in the calculation for the case at 48 MWD/kg. The cases at lower exposures do not contain the error. The calculation in error was rerun with the error corrected and more realistic values for the pellet density and internal rod pressure. The reanalysis resulted in a peak clad temperature change from 1827 F to 2189oF, which is still in compliance with 10 CFR 50.46.
This revised calculation is very conservative in that the stored energy used in the calculation is the peak stored energy over the range 0 to 48 MWD/kg rather than a lower value of stored energy that would be appropriate for the 48 MWD/kg exposure for this case. Additionally, it is our understanding that the ENC-designed fuel in D.C. Cook Unit 1 is not in the exposure range for which this calculation is applicable.
Table 1 H.B. Robinson Unit 2 Error in TOODEE2 Input; Rod Radial Power Distribution Previous Peak Clad Corrected Peak Clad Case Description Temperature Temperature (Exposure/Power Shape) (oF) (oF)
BOL/Cosine 2042 > 2200 9 MWD/kg/Cosine 1815 1923 EOL/Cosine 1785 1888 BOL/Top Peaked 2197 > 2200 9 MWD/kg/Top Peaked 2183 > 2200
Table 2 H.B. Robinson Unit 2 Reanalysis with Fq*.92 in TOODEE2 Calculation Case Description Peak Clad Temperature (Exposure/Power Shape) (<<)
BOL/Cosine 2064 BOL/Top Peaked 2195 9 MWD/kg/Top Peaked 2187
Table 3 H.B. Robinson Unit 2 LOCA-ECCS Limits 0 to 9 MWD/kg 9 to 49 MWD/kg Hot Rod Avera e Exposure Hot Rod Avera e Exposure X/L ~F(Z) X/L ~F(Z) 0.000 2.130 1.000 0.000 2.320 1.000 0.500 2. 130 1.000 0.500 2.320 1.000 0.916 1.690 0.793 0,916 1. 726 0.744 1.000 0.835 0.392 1.000 0.835 0.360 to AEP:NRC:0940B OCTO f m85 Hj(O NUCLEAR COMPANY, INC.
210t HORN R D8 ROAO. PO BOX I30, RCHLANO,WA88352 10O81 318.81 TLEX: tb2878 September 30, 1985 JSH:044:85 I
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Mr. J seph L. 8ell Propre t Manager, D.C. Cook Unit 1 Indi a a 5 Nichigan Electric Company c/o erican Electric Power Service Corp. ',
One R verside Plaza Colu us, OH 43216-6631 SUBJE T: Error in LOCA/ECCS Analysis for D.C. Cook Unit 1 Ref.: (1) XN-NF-83-61, "D.C. Cook Unit 1 LOCA-KCCS Analysis for Extended Exposure," Exxon Nuclear Company, August 1983 (2) Letter, G,F. Owsley, Manager, Reload Licensing Liaison (ENC) to Richard OeYoung, Director of Inspection and Enforcement (USNRC), dated March 22, 1985 (GFO:85:010)
Dear r. 8ell:
s discussed with Mr . George John (AEP) on September 28, 1985, the LOCA-ECCS nalysis for D.C. Cook Unit 1 reportedtin References 1 and 2 contains an error) The error was in the input to the code TOOOEE2. The code TOODEE2 calcu) ates the thermal response (heatup) ofithe hot fuel rod following the end of thh blowdown tr ansient until the core temperature transient is terminated.
The fh el rod in the analysis was modeled with eight radial rings in the fuel pellet The error consisted of the assignment of a relative decay heat power densi y of 0.0 in the outer ring of the fuel pellet. This resulted in a calcu ated peak clad temperature which was'oo low. The error occurred only in th calculation for the case at 48 MWD/kg.
t he calculation in error was rerun with the error corrected and with the od pellet density increased and the internal rod pressure decreased to value~ appropriate for 48 MWD/kg. This calculation resulted in a peak clad tempe ature of 2189oF in compliance with 10'CFR 50.46. These calculations are sunna ized in Table 1. This calculation is still very conservative in that the s ored energy in the ca'Iculation is th) peak stored energy over the range 0 to;.4 8 MWD/kg rather than a lower value of stored energy that would be approp riate for the 48 MWD/kg exposure for this case. Additionally, it is our AN ASS <ATC OS EXXON COIISaORATON I
I ~ 'Sa I IS& & la I ~ I al JSH:044:85 Mr. J. Bell (AEP) September 30, 1985 understanding that the ENC fuel in O.C. Cook Unit 1 is not in the exposure range for which this calculation is applicable.
Sincerely, J. S. Holm, Manager PN Safety Analysis gf AttactIaa cc: 4 . J. M. Cleveland (AEP)
Nr. M. P. Alexich (AEP)
Hr. G. John (AEP)
Mr. H. G. Shaw (ENC)
Mr. R. A. Copeland (KNC)
- r. R. L. Heiks (ENC)
RAPID< go.. <<~7 PAGE ~ ,Oag
Table 1 O.C. Cook Unit 1 Error in TOOOEE2 Input; Rod Radial Power Distribution Peak Clad Temperature se Oescri tion OF evious Result* 1827 C rrected Result with increased 2189 pellet density and reduced fuel rhd pressure l
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- The previous result was for a cosine power distribution at 48,0 NMD/kg exposure, Fq*l.82, reported in References 1 and 2.