Similar Documents at Cook |
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Category:GENERAL EXTERNAL TECHNICAL REPORTS
MONTHYEARML17335A5451999-09-28028 September 1999
Rev 1 to Containment Sump Level Design Condition & Failure Effects Analysis for Potential Draindown Scenarios.
ML17326A1481999-09-17017 September 1999
Independent Review of Control Rod Insertion Following Cold Leg Lbloca,Dc Cook,Units 1 & 2.
ML17335A5461999-08-0202 August 1999
Rev 0 to Evaluation of Cook Recirculation Sump Level for Reduced Pump Flow Rates.
ML17325B5671999-03-0202 March 1999
Summary of Unit 1 Steam Generator Layup Chemistry from 980101 to 990218.
ML17325B5661999-01-27027 January 1999
Unit 1 Steam Generator Layup Chemistry Out of Specification During 970924 Through 971231.
ML17325B4511998-12-15015 December 1998
Rev 1 to ER-98-009, Preliminary Waste Characterization of DC Cook SG Lower Assemblies.
ML17335A2741998-09-0101 September 1998
Rev 0 to ER-98-009, Preliminary Waste Characterization of DC Cook SG Lower Assemblies.
ML17335A1921998-07-10010 July 1998
Non-proprietary Cook Unit 1 SG Operability Re-Review.
ML17334A6151998-01-0606 January 1998
Containment Sump Operability Determination.
ML17333B0921997-10-0909 October 1997
MAAP4 Analyses of DC Cook Containment Response to Small Break Loca.
ML17333B0041997-08-14014 August 1997
Responses to RAI on Holtec Rept HI-951389 DC Cook Spent Fuel Pool.
ML17333A9561997-07-21021 July 1997
Generator U1R97 Condition Monitoring & Operational Assessment.
ML17333A9571997-07-21021 July 1997
Generators U1R97 2 Volt Interim Plugging Criteria Rept.
ML17333A5641996-08-31031 August 1996
Final Rept, Reactor Vessel Nozzle Bore Data Evaluation.
ML17333A2821995-12-31031 December 1995
DC Cook Nuclear Plant USI A-46 Seismic Evaluation Rept.
ML17333A2801995-12-31031 December 1995
DC Cook Nuclear Plant USI A-46 Safe Shutdown Equipment List Rept.
ML17333A2761995-12-31031 December 1995
DC Cook Unit 1 1995 Interim Plugging Criteria 90 Day Rept.
ML17333A2891995-12-22022 December 1995
Updated Thermal-Hydraulic Analysis of Spent Nuclear Fuel Pool DC Cook Nuclear Plant Indiana Michigan Power Co.
ML17333A3251995-11-30030 November 1995
Criticality Analysis of DC Cook Nuclear Plant New Fuel Storage Vault W/Credit for Integral Fuel Burnable Absorbers, for Nov 1995
ML17333A2831995-11-0606 November 1995
DC Cook Nuclear Plant USI A-46 Relay Evaluation Rept.
ML17333A3321995-07-31031 July 1995
DC Cook Nuclear Plant Boric Acid Concentration Reduction.
ML17333A9051995-07-25025 July 1995
Rev 0 to NRC GL 86-10 Technical Evaluation App R Section III.G.2(b) Twenty Foot Separation Between Redundant Components W/No Intervening Combustibles,Fire Zone 6M & Fire Zone 6S.
ML17332A8021995-06-15015 June 1995
EDG Load-Run Performance & Reliability During Short & Long Duration Test Periods TER
ML17333A9061995-06-0505 June 1995
Rev 0 to NRC GL 86-10 Technical Evaluation,App R Section III.G.2(b) Twenty Foot Separation Between Redundant Components W/No Intervening Combustibles Fire Zone 44N & Fire Zone 44S. W/Two Oversize Drawings
ML17332A7611995-05-0505 May 1995
Svc Water Sys Operational Performance Insp (Swsopi) Self- Assessment Rept.
ML17332A5841995-02-28028 February 1995
DC Cook Nuclear Plant IPE for External Events Revised Fire Pra.
ML17332A5851995-02-28028 February 1995
DC Cook Nuclear Plant Units 1 & 2 Addendum to Seismic PRA Notebook.
ML17332A7121994-12-0505 December 1994
Evaluation of Cook Ipe/Hra Matls.
ML17332A3731994-10-24024 October 1994
Assessment of Indications in DC Cook Unit 2 Head Penetration 75.
ML17332A4141994-08-25025 August 1994
Rev 0 to HI-941183, Spent Nuclear Fuel Pool Thermal- Hydraulic Analysis Rept for DC Cook Nuclear Plant.
ML17331B4301994-06-13013 June 1994
Rev 0 to DC Cook Nuclear Plant E-Plan Classification Vs NUMARC/NESP-007 Deviation Basis Document.
ML17331B4391994-06-0909 June 1994
1 Cycle 13 IPC Assessment.
ML17331B1331993-12-31031 December 1993
DC Cook Units 1 & 2 Main Steam Safety Valve Lift Setpoint Tolerance Relaxation.
ML17331B1411993-12-0909 December 1993
Suppl Info for DC Cook Unit 1 Ipc.
ML17331B1691993-12-0707 December 1993
Reactor Protection & Control Process Instrumentation Replacement Project at Donald C Cook Nuclear Plant Units 1 & 2,Reactor Protection Sys Functional Diversity Assessment.
ML17331B1961993-09-30030 September 1993
Control Rod Misalignment Analysis.
ML17331A0631993-02-28028 February 1993
DC Cook Nuclear Plant Hydrogen Control Evaluation Summary Rept.
ML17329A7141992-12-16016 December 1992
DC Cook Nuclear Plant Units 1 & 2 Reliability & Mtbf Analysis Reactor Protection & Control Sys Replacement Project.
ML17329A7161992-12-16016 December 1992
DC Cook Nuclear Plant Units 1 & 2 Summary Rept for Response Time Evaluations Reactor Protection & Control Sys Replacement Project.
ML17329A7071992-12-16016 December 1992
Engineering Analysis of Temperature & Humidity Effects on Foxboro Spec 200 Instrumentation Reactor Protection & Control Sys Replacement Project.
ML17329A7091992-12-16016 December 1992
Preliminary Emi/Rfi Evaluation Aepsc Reactor Protection & Control Sys Replacement Project.
ML17329A7131992-12-16016 December 1992
DC Cook Nuclear Plant Units 1 & 2 Failure Modes & Effect Analysis (FMEA) Protection Set 1 Foxboro Spec 200 Reactor Protection & Control Sys Replacement Project.
ML17329A7111992-12-16016 December 1992
Engineering Analysis of Grounding Issues Reactor Protection Process Control Group Replacement Project DC Cook Nuclear Plants Units 1 & 2.
ML17329A7101992-12-16016 December 1992
DC Cook Nuclear Plant Units 1 & 2 Summary Rept for Sys Power Quality Evaluation Reactor Protection & Control Sys Replacement Project.
ML17329A7171992-12-15015 December 1992
Reactor Protection & Control Process Instrumentation Replacement Project at DC Cook Nuclear Plant Units 1 & 2 TS Compliance Assessment.
ML17329A7121992-12-15015 December 1992
Regulatory Requirements & Industry Standards Associated W/Reactor Protection Portion of Reactor Protection & Control Process Instrumentation Replacement Project.
ML17329A7201992-12-14014 December 1992
Reactor Protection & Control Process Instrumentation Replacement Project at DC Cook Nuclear Plant Units 1 & 2 Reactor Protection Sys Functional Diversity Assessment.
ML17329A7181992-12-14014 December 1992
Reactor Protection & Control Process Instrumentation Replacement Project at DC Cook Nuclear Plants Units 1 & 2 Qualification Compliance.
ML17329A7151992-12-10010 December 1992
Reactor Protection & Control Process Instrumentation Replacement Project at DC Cook Nuclear Plant Units 1 & 2 Functional Requirement Summary.
ML17329A7191992-12-10010 December 1992
Reactor Protection & Control Process Instrumentation Replacement Project at DC Cook Nuclear Plant Units 1 & 2 Test Program Summary.
1999-09-28
[Table view]
Category:TEXT-SAFETY REPORT
MONTHYEARML17335A5641999-10-18018 October 1999
LER 99-024-00:on 990708,literal TS Requirements Were Not Met by Accumlator Valve Surveillance.Caused by Misjudgement Made in Conversion from Initial DC Cook TS to W Std Ts.Submitted License Amend Request.With 991018 Ltr
ML17335A5531999-10-0707 October 1999
LER 99-023-00:on 990907,inadequate TS Surveillance Testing of ESW Pump ESF Response Time Noted.Caused by Inadequate Understanding of Plant Design Basis.Surveillance Tests Will Be Revised & Implemented
ML17335A5631999-09-30030 September 1999
Monthly Operating Rept for Sept 1999 for DC Cook Nuclear Plant,Unit 1.With 991012 Ltr
ML17335A5621999-09-30030 September 1999
Monthly Operating Rept for Sept 1999 for DC Cook Nuclear Plant,Unit 2.With 991012 Ltr
ML17335A5481999-09-30030 September 1999
Non-proprietary DC Cook Nuclear Plant Units 1 & 2 Mods to Containment Sys W SE (Secl 99-076,Rev 3).
ML17335A5451999-09-28028 September 1999
Rev 1 to Containment Sump Level Design Condition & Failure Effects Analysis for Potential Draindown Scenarios.
ML17326A1291999-09-17017 September 1999
LER 99-022-00:on 990609,electrical Bus Degraded Voltage Setpoints Too Low for Safety Related Loads,Was Discovered. Caused by Lack of Understanding of Design of Plant.No Immediate Corrective Actions Necessary
ML17326A1481999-09-17017 September 1999
Independent Review of Control Rod Insertion Following Cold Leg Lbloca,Dc Cook,Units 1 & 2.
ML17326A1211999-08-31031 August 1999
Monthly Operating Rept for Aug 1999 for Cook Nuclear Plant, Unit 2.With 990915 Ltr
ML17326A1201999-08-31031 August 1999
Monthly Operating Rept for Aug 1999 for Cook Nuclear Plant, Unit 1.With 990915 Ltr
ML17326A1121999-08-27027 August 1999
LER 99-021-00:on 990728,determined That GL 96-01 Test Requirements Were Not Met in Surveillance Tests.Caused by Failure to Understand Full Extent of GL Requirements. Surveillance Procedures Will Be Revised or Developed
ML17326A1011999-08-26026 August 1999
LER 99-020-00:on 990727,EDGs Were Declared Inoperable.Caused by Inadequate Protection of Air Intake,Exhaust & Room Ventilation Structures from Tornado Missile Hazards. Implemented Compensatory Measures in Form of ACs
ML17326A0911999-08-16016 August 1999
LER 99-019-00:on 990716,noted Victoreen Containment Hrrms Not Environmentally Qualified to Withstand post-LOCA Conditions.Caused by Inadequate Design Control.Reviewing Options to Support Hrrms Operability in Modes 1-4
ML17326A0771999-08-0404 August 1999
LER 98-029-01:on 980422,noted That Fuel Handling Area Ventilation Sys Was Inoperable.Caused by Original Design Deficiency.Radiological Analysis for Spent Fuel Handling Accidents in Auxiliary Bldg Will Be Redone by 990830
ML17335A5461999-08-0202 August 1999
Rev 0 to Evaluation of Cook Recirculation Sump Level for Reduced Pump Flow Rates.
ML17326A0871999-07-31031 July 1999
Monthly Operating Rept for July 1999 for DC Cook Nuclear Plant,Unit 1.With 990812 Ltr
ML17326A0861999-07-31031 July 1999
Monthly Operating Rept for July 1999 for DC Cook Nuclear Plant,Units 2.With 990812 Ltr
ML17326A0741999-07-29029 July 1999
LER 99-018-00:on 990629,determined That Valve Yokes May Yield Under Combined Stress of Seismic Event & Static,Valve Closed,Stem Thrust.Caused by Inadequate Design of Associated Movs.Operability Determinations Were Performed for Valves
ML17326A0661999-07-26026 July 1999
LER 99-017-00:on 990625,noted That Improperly Installed Fuel Oil Return Relief Valve Rendered EDG Inoperable.Caused by Personnel Error.Fuel Oil Return Valve Was Replaced with Valve in Correct Orientation.With 990722 Ltr
ML17326A0651999-07-22022 July 1999
LER 98-014-03:on 980310,noted That Response to high-high Containment Pressure Procedure Was Not Consistent with Analysis of Record.Caused by Inadequate Interface with W. FRZ-1 Will Be Revised to Be Consistent with New Analysis
ML17326A0491999-07-13013 July 1999
LER 99-016-00:on 990615,TS Requirements for Source Range Neutron Flux Monitors Not Met.Caused by Failure to Understand Design Basis of Plant.Procedures Revised.With 990713 Ltr
ML17326A0331999-07-0101 July 1999
LER 99-004-01:on 971030,failure to Perform TS Surveillance Analyses of Reactor Coolant Chemistry with Fuel Removed Was Noted.Caused by Ineffective Mgt of Tss.Chemistry Personnel Have Been Instructed on Requirement to Follow TS as Written
ML17326A0511999-06-30030 June 1999
Monthly Operating Rept for June 1999 for DC Cook Nuclear Plant,Unit 2.With 990709 Ltr
ML17326A0501999-06-30030 June 1999
Monthly Operating Rept for June 1999 for DC Cook Nuclear Plant,Unit 1.With 990709 Ltr
ML17326A0151999-06-18018 June 1999
LER 99-014-00:on 990521,determined That Boron Injection Tank Manway Bolts Were Not Included in ISI Program,Creating Missed Exam for Previous ISI Interval.Caused by Programmatic Weakness.Isi Program & Associated ISI Database Modified
ML17325B6421999-06-0101 June 1999
LER 99-013-00:on 990327,safety Injection & Centrifugal Charging Throttle Valve Cavitation During LOCA Could Have Led to ECCS Pump Failure.Caused by Inadequate Original Design Application of Si.Throttle Valves Will Be Developed
ML17325B6311999-06-0101 June 1999
LER 99-S03-00:on 990430,vital Area Barrier Degradation Was Noted.Caused by Inadequate Insp & Maint of Vital Area Barrier.Repairs & Mods Were Made to Barriers to Eliminate Degraded & Nonconforming Conditions
ML17326A0061999-05-31031 May 1999
Monthly Operating Rept for May 1999 for Dcp.With 990609 Ltr
ML17326A0071999-05-31031 May 1999
Monthly Operating Rept for May 1999 for DC Cook Nuclear Plant,Unit 2.With 990609 Ltr
ML17325B6351999-05-28028 May 1999
LER 99-S02-00:on 990428,vulnerability in Safeguard Sys That Could Allow Unauthorized Access to Protected Area Was Noted. Caused by Inadequate Original Plant Design.Mods Were Made to Wall Opening to Eliminate Nonconforming Conditions
ML17265A8231999-05-24024 May 1999
LER 98-037-01:on 990422,determined That Ice Condenser Bypass Leakage Exceeds Design Basis Limit.Caused by Pressure Seal Required by Revised W Design Not Incorporated Into Aep Design.Numerous Matl Condition Walkdowns & Assessments Made
ML17325B6001999-05-20020 May 1999
LER 99-012-00:on 990420,concluded That Auxiliary Bldg ESF Ventilation Sys Not Capable of Maintaining ESF Room Temps post-accident.Caused by Inadequate Control of Sys Design Inputs.Comprehensive Action Plan Being Developed
ML17325B5861999-05-10010 May 1999
LER 99-002-00:on 990415,discovered That TS 4.0.5 Requirements Were Not Met Due to Improperly Performed Test. Caused by Incorrect Interpretation of ASME Code.App J Testing Will Be Completed & Procedures Will Be Revised
ML17325B5811999-05-0404 May 1999
LER 99-011-00:on 990407,air Sys for EDG Will Not Support Long Operability.Caused by Original Design Error.Temporary Mod to Supply Makeup Air Capability in Modes 5 & 6 Was Prepared
ML17325B5771999-05-0303 May 1999
LER 99-010-00:on 990401,RCS Leak Detection Sys Sensitivity Not in Accordance with Design Requirements Occurred.Caused by Inadequate Original Design of Containment Sump Level. Evaluation Will Be Performed to Clearly Define Design
ML17335A5301999-04-30030 April 1999
Monthly Operating Rept for Apr 1999 for DC Cook Nuclear Plant,Unit 1.With 990508 Ltr
ML17335A5291999-04-30030 April 1999
Monthly Operating Rept for Apr 1999 for DC Cook Nuclear Plant,Unit 2.With 990508 Ltr
ML17325B5581999-04-16016 April 1999
LER 99-006-00:on 990115,personnel Identified Discrepancy Between TS 3.9.7 Impact Energy Limit & Procedure 12 Ohp 4030.STP.046.Caused by Lack of Design Basis Control.Placed Procedure 12 Ohp 4030.STP.046 on Administrative Hold
ML17325B5471999-04-12012 April 1999
LER 99-009-00:on 990304,as-found RHR Safety Relief Valve Lift Setpoint Greater than TS Limit Occurred.Cause Investigation for Condition Has Not Been Completed.Update to LER Will Be Submitted,Upon Completion of Investigation
ML17325B5321999-04-0707 April 1999
LER 99-S01-00:on 990308,discovered That Lock for Vital Gate Leading to Plant 4KV Switchgear Area Was Nonconforming & Vulnerable to Unauthorized Access.Caused by Inadequate Gate Design & Inadequate Procedures.Mods Are Being Made to Gate
ML17325B5161999-04-0101 April 1999
LER 99-007-00:on 981020,calculations Showed That Divider Barrier Between Upper & Lower Containment Vols Were Overstressed.Engineers Are Currently Working on Analyses of Loads & Stress on Enclosures
ML17325B5491999-03-31031 March 1999
Monthly Operating Rept for Mar 1999 for DC Cook Nuclear Plant Unit 2.With 990408 Ltr
ML17325B5441999-03-31031 March 1999
Monthly Operating Rept for Mar 1999 for DC Cook Nuclear Plant,Unit 1.With 990408 Ltr
ML17325B5221999-03-29029 March 1999
LER 99-001-00:on 960610,degraded Component Cooling Water Flow to Containment Main Steam Line Penetrations,Identified on 990226.Caused by Inadequate Understanding of Design Basis.Additional Investigations Ongoing
ML17325B4801999-03-18018 March 1999
LER 99-004-00:on 971030,failure to Perform TS Surveillance Analyses of Rc Chemistry with Fuel Removed Was Noted.Cause of Event Is Under Investigation.Corrected Written Job Order Activities Used to Control SD Chemistry Sampling
ML17325B4741999-03-18018 March 1999
LER 99-005-00:on 940512,determined That Rt Breaker Manual Actuations During Rod Drop Testing Were Not Previously Reported.Caused by Lack of Training.Addl Corrective Actions,Including Preventative Actions May Be Developed
ML17325B5671999-03-0202 March 1999
Summary of Unit 1 Steam Generator Layup Chemistry from 980101 to 990218.
ML17325B4631999-02-28028 February 1999
Monthly Operating Rept for Feb 1999 for DC Cook Nuclear Power Station,Unit 2.With 990308 Ltr
ML17325B4621999-02-28028 February 1999
Monthly Operating Rept for Feb 1999 for DC Cook Nuclear Plant,Unit 1.With 990308 Ltr
ML17325B4571999-02-24024 February 1999
LER 99-003-00:on 990107,CR Pressurization Sys Surveillance Test Did Not Test Sys in Normal Operating Condition.Caused by Failure to Recognize Door 12DR-AUX415 as Part of CR Pressure Boundary.Performed Walkdown of Other Doors
1999-09-30
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Text
APPROVED"INGENERAL"MECHANICAL ENGINEERING DIVISIONAMERICANELECTRICPOWERSERVICECORP-PERDATESCPP4'.C.COOKUNIT1REACTORVESSELRTPTSEVALUATIONS gy~<3nenF
~5J.M.ChicottsN.K.RayMARCH1990workperformed underShopOrderNo.AOZP-108Approved:
T.A.Meyer,MagerStructural Materials andReliability Technology PreparedbyMestinghouse ElectricCorporation fortheAmericanElectricPowerCompany4111si031290:10 RESTINGHOUSEELECTRICCORPORATION NuclearandAdvancedTechnology OivisionP.O.8ox2728Pittsburgh, Pennsylvania 15230(920728027i 920713PDRADOCN050003i5PPDR TABLEOFCONTENTSSectionTABLEOFCONTENTSLISTOFTABLESLISTOFFIGURESTitle~PaeSUMMARYOFRESULTSPRESSURIZED THERMALSHOCK2-1ThePressurized ThermalShockRule2-12-2MethodsforCalculation ofRTPTS2-32-3Determination ofRTPTSValuesforAllBeltlineRegionMaterials 2-52-4StatusofReactorVesselintegrity inTermsofRTPTSVersusFluenceResults2-6REFERENCES 3-1etTEel031290:10 LISTOFTABLESTableTitle~Pae2-10,C.CookUnit1ReactorVesselBeltlineRegionMaterialProperties 2-82-2SummaryofFluence(E>1.0MeV)UsedfortheEvaluation ofRTPTS2-92-3RTPTSVa1uesPerPTSRulefor0~C~CookUnit12"10RTPTSValuesPerRegulatory Guide1.99,Revision2for0.C.CookUnit12-114IIIel03I290:IO11 j
LISTOFFIGURES~FiereTitie~Pae2-12-22-3Identification"and-Location ofHeltlineRegionMaterialforthe..D..C.CookUnit1ReactorVesselRTPTSvs~FluenceperPTSRule-CookUnit1,RT>>~vs.FluenceperRegulatory Guide1.99,Rekilion2,CookUnit1,2-72-112"12i111sl031290:10 SECT10N1SUMMARYOFRESULTSThePressurized thermalshockevaluations wereperformed forD.C.CookUnit1ReactorVesselBeltlineregionmaterials andresultedthefollowing conclusion:
oUsingPTSrule:Thelimitingmaterialisfoundtobethecircumferential weld(Table2-3).RTPTSvaluesare200'Fand216'Fforlifeupto23and32EFPYrespectively.
Thesevaluesarebelowthescreening criteriaof300'Fforcircumferential weld.oUsingRegulatory Guide1.99,Revision2Thelimitingmaterialisfoundtobethecircumferential weld(Table2-4).RTPTSvaluesare221'Fand238Fforlifeupto23and32EFPYrespectively.
Thesevaluesarebelowthescreening criteriaof300'Fforcircumferential weld.ll1le/0312QO:lO SECTION2PRESSURIZED THERMALSHOCK2-1.THEPRESSURIZED THERMALSHOCKRULEThePressurized ThermalShock(PTS)RulewasapprovedbytheU.S.NuclearI:1]Regulatory Commissioners onJune20,1985,andappearedintheFederalRegisteronJuly23,1985.ThedatethattheRulewaspublished intheFederalRegisteristhedatethattheRulebecamearegulatory requirement.
1TheRuleoutlinesregulations toaddressthepotential forPTSeventsonpressurized waterreactor(PHR)vesselsinnuclearpowerplantsthatareoperatedwithalicensefromtheUnitedStatesNuclearRegulatory Commission (USNRC).PTSeventshavebeenshownfromoperating experience tobetransients thatresultinarapidandseverecooldownintheprimarysystemcoincident withahighorincreasing primarysystempressure.
ThePTSconcern~~~~~arisesifoneofthesetransients actsonthebeltlineregionofareactorvesselwhereareducedfractureresistance existsbecauseofneutronirradiation.
Suchaneventmayproducethepropagation offTawspostulated toexistneartheinnerwallsurface,therebypotent'ially affecting theintegrity ofthevessel.TheRuleestablishes thefollowing requirements foralldomestic, operating PMRs:*TheRT~7~(measureoffractureresistance)
Screening Criterion forthereh0'torvesselbeltlineregionis270'Fforplates,forgings, axialwelds300'Fforcircumferential weldmaterials 4111@/031290;10 2-1 6MonthsFromOateofRule:Allplantssubmitted theirpresentRT>>~values(pertheprescribed methodology) andprojected RT>>~valuesattheexpiration dateoftheoperating license.Thedat4thatthissubmittal hadtobereceivedbytheNRCforplantswithoperating licenseswasJanuary23,1986.9MonthsFromOateofRule:Plantsprojected toexceedthePTSScreening Criterion hadtosubmitananalysisandascheduleforimplementation ofsuchfluxreduction programsasarereasonably practicable toavoidreachingtheScreening Criterion.
Thedateforthissubmittal hadtobereceivedbytheNRCforplantswith'operating licensesbyApril23,1986.*Plant-specific PTSsafetyanalysesarerequiredbeforeaplantiswithin3yearsofreachingtheScreening Criterion, including analysesofalternat,ives tominimizethePTSconcern.*NRCapprovalforoperation beyondtheScreening Criterion isrequired.
Forapplicants ofoperating
- licenses, valuesoftheprojected RTpTSaretobeprovidedintheFinalSafetyAnalysisReport.Thisrequirement isaddedaspartof10CFRPart50.34.0IntheRule,theNRCprovidesguidanceregarding thecalculation ofthetoughness stateofthereactorvesselmaterials
-the"reference temperature fornil-ductility transition" (RTNOT).ForpurposesoftheRule,RTNOTisnowdefinedas"thereference temperature forpressurized thermalshock"(RTPTS)andcalculated asprescribed by10CFR50.61(b)oftheRule.EachUSNRClicensedPMRwasrequiredtosubmitaprojection ofRTpTSvaluesfromthetimeofthesubmittal tothelicenseexpiration date.Thisassessment wasrequiredtobesubmitted within6monthsaftertheeffective dateoftheRule,onJanuary23,1986,withupdateswheneverchangesoccuraffecting projected values.Thecalculation mustbemadeforeachweldandplate,orforging,inthereactorvesselbeltline.
'4111s>031290:10 2-2 Calculations werecarriedoutusingthelatestplantspecificmaterial~~~~~~~properties inaccordance withboththecurrentPTSruleandRegulatory I:1lGuide1.99-Revision 2,whichwasrecentlyissuedasthelatestregulatory methodforpredicting irradiation embrittlement ofreactorvesselmaterials.
TheNRCplanstoincorporate Revision2ofRegulatory Guide1.99intothePTSrulewithoutchangingthePTSscreening criteriaperNRCGenericLetter88-11.TheRTPTSresultsforallCook,Unit1reactorvesselbeltline[3lregionmaterials arepresented following adescription ofthesetworegulatory calculational methodologies.
22METHODSFORCALCULATION OFRTPTS2-2.1PTSRuleMethodolo lnthePTSRule,theNRCStaffhasselectedaconservative anduniformmethodfordetermining plant-specific valuesofRTPTSatagiventime.Theprescribed equations inthePTSruleforcalculating RTPTSareactuallyoneofseveralwaystocalculate RTNOT.Forthepurposeofcomparison withtheScreening Criterion, thevalueofRTPTSforthereactorvesselmustbecalculated foreachweldandplate,orforginginthebeltlineregionasgivenbelow.Foreachmaterial, RTPTSistheloweroftheresultsgivenbyEquations 1and2.Equation1:RTpTSI+M+[10+470(Cu)+350(Cu)(Nl)]fEquation2:RT=I+M+283f0'194PTS(2)4111giOQ~%0.102-3 whereI=theinitialreference transition temperature oftheunirradiated materialmeasuredasdefinedintheASHECode,NS-331,Ifameasuredvalueisnotavailable, thefollowing genericmeanvaluesmustbeused:O'FforweldsmadewithLinde80flux,and-56'FforweldsmadewithLinde0091,1092and124andARCOS8-5weldfluxes.H=themargintobeaddedtocoveruncertainties inthevaluesofinitialRTNpTcopperandnieke1content,f1uence,andca1culationprocedures
~InEquation1,M=48'FifameasuredvalueofIwasused,andM=59'FifthegenericmeanvalueofIwasused.InEquation2,M=O'FifameasuredvalueofIwasused,andM=34'FifthegenericmeanvalueofIwasused.CuandNi=thebestestimateweightpercentofcopperandnickelinthematerial.
f=themaximumneutronfluence,inunitsof10n/cm(Egreaterthanor192equalto1MeV),attheclad-base-metal interface ontheinsidesurfaceofthevesselatthelocationwherethematerialinquestionreceivesthehighestfluencefortheperiodofserviceinquestion.
Notethatthechemistry valuesgiveninequations 1and2arebestestimatemeanvalues.Themargin,M,increases theRTPTSvaluestobeupperboundpredictions.
Thus,themeanmaterialchemistry valuesaretobeusedwhenavailable soasnottocompoundconservatism.
2-2.2Reoulator Guide1.99Revision2Hethodolo Revision2toRegulatory Guide1.99wasissuedinMay1988.TheAdjustedl2]Reference Temperature (ART),basedonthemethodsofRegulatory Guide1.99Revision2,canbecompactly described bythesequenceofequations listedbelow:4'Ills>071290;>0 2-4 ART=InitialRTNpy+ARTNDT+MargindRT=(CF]F(0.28
-0.10LOGf)NDTwere,(3)(4)f=Neutronfluence,n/cm(E>1MeV),dividedby10CF=Chemistry factorfromtablesforweldsandforbasemetal(platesandforgings)
(ifnodatause0.35%Cuand1.0%Ni)Margin=2[ol+a<]'here,2(5)aIstandarddeviation ofinitialRTNpyIftheinitialRTNpyismeasured,oIistobeestimated fromtheprecision ofthetestmethod;otherwise, aIisobtainedfromthesamesetofdatathatisusedtogetinitialRTNpy.o<=Standarddeviation ofLRTNDT,28'Fforweldsand17'Fforbasemetal[a>neednotexceed1/2timesARTNDTsurface]ThevalueofARTwillbeassumedtobetheRTPTSvalueforusewiththePTSrule.23DETERMINATION OFRTpTS.VALUESFORALLBELTLINEREGIONMATERIALS FortheRTPTScalculation, thebestestimatecopperandnickelchemicalcomposition ofthereactorvesselbeltlinematerialisnecessary.
Thebeltlineregionisde'finedbytheRule]tobe"theregionofthereactorvessel(shellmaterialincluding welds,heataffectedzones,andplatesorforgings) thatdirectlysurrounds theeffective heightoftheactivecoreandadjacentregionsofthereactorvesselthatarepredicted to~~~~~~~~~~~~~~~~~~~~experience sufficient neutronirradiation damagetobeconsidered intheselection ofthemostlimitingmaterialwithregardtoradiation damage."Figure2-1identifies thelocationofallbeltlineregionmaterials forthereactorvessel.t1I1s/all200:l02-5 Asummaryofthepertinent chemicalandmechanical properties ofthebeltlineregionplateandweldmaterials andtheinitialRTNDTvaluesoftheCookUnit1reactorvesselarereproduced inTable2-1(Reference 4,TableA-l).Alsoasummaryoffluence(E>1.0MeV)valuesusedfortheevaluation ofRTPTSisprovidedinTable2-2(Reference 4,Table6-14).Usingthemethodology prescribed beforeandthematerialproperties
'discussed inthissection,theRTPTSvaluesforD.C.CookUnitLcanbedetermined.
24STATUSOFREACTORVESSELINTEGRITY INTERMSOFRTpTSVERSUSFLUENCERESULTSUsingtheprescribed PTSRulemethodology, RTPTSvaluesweregenerated forallbeltlineregionmaterials oftheD.C.CookUnit1reactorvesselasafunctionofpertinent vessellifetimes.
Thetabulated resultsfromthis~~~evaluation arepresented inTable2-3and2-4forallbeltlineregionmaterials.
Figures2-2and2-3presenttheRTPTSversusfluenceforthebeltline.materialoftheCookUnit1vesselusingPTSruleandRegulatory Guide1.99,Revision2,respectively, ThecurvesinthesefigurescanbeusedtoprovideguidancetoevaluatefuelreloadoptionsinrelationtotheNRCRTPTSScreening Criterion forPTS,ifthiswouldeverbecomenecessary.
Thatis,RTPTSvaluescanbereadilyprojected foranyoptionsunderconsideration, providedthatfluenceisknown.il11@/031290:10 2-6
~0LlflCIDNIT1GIE1NTEfSKD1ATE SHELL0CL5IDID~eClh~Qlnao~0n0lQ0CLCI0wohrt'X7IDOh0CXl5IDOlCllIDIDIDu30~ooCACl TABLE2-1~~D.C.UNIT1REACTORVESSELBELTLINEREGIONMATERIALPROPERTIES PlateCuNiInitialComponent No.(Wtl.)(Wtl.)RTNDT('F)
Intermediate ShellPlate84406-1.12.52Intermediate ShellPlateB4406-2.15.5033Intermediate ShellPlateB4406-3,15.4940LowerShellPlate84407-1.14.5528LowerShel1PlateB4407-2.12.59-12LowerShellPlateB4407-3.14.5038Longitudinal fields.28.74-56Circumferential fields.28.74-56il11s/0311SO;10 2-8 TABLE2-2~~SUMMARYOFFLUENCE(E>1.0MeV)VALUESUSEDFORTHEEVALUATION OFRTPTSComponent 23EFPY32EFPYIntermediate ShellPlate,84406-11,051.41Intermediate ShellPlate,84406-2Intermediate ShellPlate,84406-31.051.051.411.41LowerShellPlate,84407-11.051.41LowerShellPlate,84407-21.051.41LowerShellPlate,84407-31.051.41Longitudinal Weld0.7140.95Circumferential Weld1.051.41Fluencesarein10n/cm(E>1.0MeV)194131s/032790:10 2-9 TABLE2-3RTpTSVALUESPERPTSRULEFOR0~C~COOKUNIT1RTPTSValues('F)LocationVesselMaterial23EFPYSCREENING 32EFPYCRITERIAIntermediate shellplateB4406-11221282702Intermediate shellplateB4406-21691762703Intermediate shellplateB4406-3175183270LowershellplateB4407-1160167270LowershellplateB4407-21081142706LowershellplateB4407-31671742707MostLimitingLongitudinal weld180195270Circumferential weld20030041IIsx001700:
TO2-10 TABLE2-4RTPTSVALUESPERREGULATORY GUIDE199REVISION2FORD.C.COOKUNIT1RTPTSValues('F)LocationVesselMaterial23EFPYSCREENING 32EFPYCRITEREA1Intermediate shellplate84406-1,1211282702Intermediate shellplateB4406-2173182270Intermediate shellplateB4406-31791882704Lowershellplate84407-11611692705LowershellplateB4407-21061132706Lowershellplate84407-3169177270MostLimitingLongitudinal weld1992152708Circumferential weld2212383004111slO'322SO:10 280270260250240230220210200190180170160a15014013012011010090sa70Q10305Q7091113151719Fluence(x10E19)n/cm2TELOS+84406-3~+84406-2
~84407-384407-1<84406-1484407-2ilIls/07llQO.IO Figure2-2.RTPTSvs.FluenceperPTSRule-CookUnit1 28027026025024023022021Q20Q19a18017016015014013Q12Q11Q10090807QalQ30507091113151719Fluence(x10619)n/cm2TELOS84406-384406-284407-384407-10-84406-1
~84407-24111s/031290 10Figure2-3.RTpT>vs.FluenceperRegulatory Guide1.99,Revision2-CookUnit1 SECTION3REFERENCES
[1]"Analysis ofPotential Pressurized ThermalShockEvents,"10CFRpart50,FinalRule,July23,1985.[2]Regulatory Guide1.99,Revision2,"Radiation Embrittlement ofReactorVesselMaterials,"
U.S.NuclearRegulatory Commission, May,1988.[3]NRCGenericletter88-11,"NRCPositiononRadiation Embrittlement ofReactorVesselMaterials anditsImpactonPlantOperations",
July12,1988.[4]E.Terek,S,L.Anderson, L.Albertin, N.K.Ray,"Analysis ofCapsuleUfromtheAmericanElectricPowerCompanyD.C.CookUnit1ReactorVesselRadiation Surveillance Program."
~1~i<llis/031290:l0 3-1 a'~\QeSECTION3REFERENCES
[1]"Analysis ofPotential Pressurized ThermalShockEvents,"10CFRpart50,FinalRule,July23,1985.[2]Regulatory Guide1.99,Revision2,"Radiation Embrittlement ofReactorVesselHaterials,"
U.S.NuclearRegulatory Commission, May,1988.[3]NRCGenericletter88-11,"NRCPositiononRadiation Embrittlement ofReactorVesselMaterials anditsImpactonPlantOperations",
July12,1988.[4]E.Terek,S.L.Anderson, L.Albertin, N.K.Ray,"Analysis ofCapsuleUfromtheAmericanElectricPowerCompanyD.C.CookUnit1ReactorVesselRadiation Surveillance Program."
i)ills/03l290:10 3-1
