|
---|
Category:Letter
MONTHYEARML24289A0312024-11-0808 November 2024 – Issuance of Amendments Related to the Removal of License Condition 2.F as Part of the Consolidated Line-Item Improvement Process (CLIIP) IR 05000416/20240032024-11-0606 November 2024 Integrated Inspection Report 05000416/2024003 IR 05000416/20240112024-10-16016 October 2024 – Fire Protection Team Inspection Report 05000416/2024011 ML24263A2712024-09-19019 September 2024 Application to Revise Technical Specifications to Adopt TSTF-592, Revise Automatic Depressurization System (ADS) Instrumentation Requirements IR 05000416/20240122024-09-17017 September 2024 License Renewal Post Approval Phase 2 Inspection Report 05000416/2024012 ML24257A0172024-09-17017 September 2024 Request for Withholding Information from Public Disclosure Unit 1 ML24254A3602024-09-10010 September 2024 Pre-Submittal Slides for License Amendment Request, Criticality Safety Analysis, Technical Specification 4.3.1, Criticality and Technical Specification 5.5.14, Spent Fuel Storage Rack Neutron Absorber Monitoring Program IR 05000416/20244022024-09-0909 September 2024 Security Baseline Inspection Report 05000416/2024402 05000416/LER-2024-003, Feedwater Inlet Check Valve Incorrectly Determined Operable2024-08-26026 August 2024 Feedwater Inlet Check Valve Incorrectly Determined Operable ML24235A0832024-08-22022 August 2024 Evaluations Performed in Accordance with 10 CFR 50.54(q) for Changes to Emergency Planning Documents IR 05000416/20240052024-08-21021 August 2024 Updated Inspection Plan for Grand Gulf Nuclear Station (Report 05000416/2024005) ML24220A2642024-08-20020 August 2024 Entergy Operations, Inc. - Entergy Fleet Project Manager Assignment ML24185A1522024-08-13013 August 2024 Issuance of Amendment Nos. 334, 235, and 215, Respectively, to Revise TSs to Adopt TSTF-205 IR 05000416/20240022024-07-29029 July 2024 Integrated Inspection Report 05000416/2024002 ML24176A1202024-07-29029 July 2024 Issuance of Amendment 234 Revision to Technical Specifications to Adopt TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times – RITSTF Initiative 4b ML24172A2502024-07-29029 July 2024 – Issuance of Amendment No. 233 Adoption of 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors ML24204A2432024-07-23023 July 2024 Notification of Cyber Security Baseline Inspection and Request for Information (05000416/2024403) ML24191A2432024-07-0909 July 2024 Completion of License Renewal Activities Prior to Entering the Period of Extended Operations IR 05000416/20240102024-06-27027 June 2024 Biennial Problem Identification and Resolution Inspection Report 05000416/2024010 ML24156A1762024-06-24024 June 2024 Regulatory Audit Summary in Support of License Amendment Requests to Adopt TSTF-505, Revision 2 and 10 CFR 50.69 (Epids L-2023-LLA-0081 and L-2023-LLA-0080) ML24165A1512024-06-13013 June 2024 Second Supplement to License Amendment Request to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times – RITSTF Initiative 4b and Application to Adopt 10 CFR 50.69, Risk-Informe ML24163A2652024-06-11011 June 2024 Inservice Inspection Summary Report ML24060A2192024-05-30030 May 2024 Authorization of Alternative to Use EN-RR-01 Concerning Proposed Alternative to Adopt Code Case N-752 05000416/LER-2024-002, Automatic Actuation of Reactor Protection System2024-05-28028 May 2024 Automatic Actuation of Reactor Protection System ML24130A0912024-05-0909 May 2024 Request for Information Letter License Renewal Phase 2 Inspection ML24128A1512024-05-0909 May 2024 Project Manager Assignment ML24128A0422024-05-0707 May 2024 License Amendment Request to Remove Obsolete License Conditions IR 05000416/20240012024-05-0202 May 2024 Integrated Inspection Report 05000416 2024001 ML24122C6112024-05-0101 May 2024 Supplement to License Amendment Request to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - Ritstf. ML24116A0372024-04-25025 April 2024 Report of Technical Specification Bases Changes ML24113A0972024-04-22022 April 2024 Annual Report of Individual Monitoring - NRC Form 5 for 2023 Per 1 0 CFR 20.2206 ML24113A0952024-04-22022 April 2024 Annual Radioactive Effluent Release Report for 2023 ML24107B0402024-04-16016 April 2024 Notification by Entergy Operations, Inc., of Proposed Economic Performance Incentive and Reliance on Post-Event Improvements in Plant Procedures And/Or Methods of Operation in FERC ML24107A8872024-04-16016 April 2024 2023 Annual Radiological Environmental Operating Report (AREOR) ML24101A3882024-04-10010 April 2024 Response to Request for Confirmation of Information by the Office of Nuclear Reactor Regulation Proposed Alternative Request EN-RR-22-001 Risk-Informed Categorization and Treatment for Repair ML24100A0692024-04-0909 April 2024 Report of Changes or Errors to 10 CFR 50.46 Analysis ML24094A0992024-04-0303 April 2024 (GGNS) Core Operating Limits Report (COLR) Cycle 25, Revision O ML24089A2262024-03-29029 March 2024 Entergy Response to Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Exams 05000416/LER-2024-001, High Pressure Core Spray Inoperable Due to Minimum Flow Valve Failure to Close2024-03-27027 March 2024 High Pressure Core Spray Inoperable Due to Minimum Flow Valve Failure to Close IR 05000416/20220042024-03-19019 March 2024 – Amended Integrated Inspection Report 05000416/2022004 and Exercise of Enforcement Discretion ML24075A1712024-03-15015 March 2024 Nuclear Onsite Property Damage Insurance (10 CFR 50.54(w)(3)) ML24074A2892024-03-14014 March 2024 Proof of Financial Protection (10 CFR 140.15) IR 05000416/20230062024-02-28028 February 2024 Annual Assessment Letter for Grand Gulf Nuclear Station - Report 05000416/2023006 ML24058A3512024-02-28028 February 2024 Notification of Biennial Problem Identification and Resolution Inspection and Request for Information IR 05000416/20233012024-02-26026 February 2024 NRC Examination Report 05000416-2023301 05000416/LER-2023-002, Reactor Scram Due to Generator Stator Fault to Ground2024-02-13013 February 2024 Reactor Scram Due to Generator Stator Fault to Ground ML24043A1892024-02-12012 February 2024 Spent Fuel Storage Radioactive Effluent Release Report for 2023 ML24012A1422024-01-31031 January 2024 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0051 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) ML24043A0732024-01-29029 January 2024 2024-01 Post Examination Comments IR 05000416/20230042024-01-25025 January 2024 Integrated Inspection Report 5000416/2023004 2024-09-09
[Table view] Category:Licensee Event Report (LER)
MONTHYEAR05000416/LER-2024-003, Feedwater Inlet Check Valve Incorrectly Determined Operable2024-08-26026 August 2024 Feedwater Inlet Check Valve Incorrectly Determined Operable 05000416/LER-2024-002, Automatic Actuation of Reactor Protection System2024-05-28028 May 2024 Automatic Actuation of Reactor Protection System 05000416/LER-2024-001, High Pressure Core Spray Inoperable Due to Minimum Flow Valve Failure to Close2024-03-27027 March 2024 High Pressure Core Spray Inoperable Due to Minimum Flow Valve Failure to Close 05000416/LER-2023-002, Reactor Scram Due to Generator Stator Fault to Ground2024-02-13013 February 2024 Reactor Scram Due to Generator Stator Fault to Ground 05000416/LER-2023-001-01, Valve Closure Test Failure Resulting in Condition Prohibited by Technical Specification2023-11-30030 November 2023 Valve Closure Test Failure Resulting in Condition Prohibited by Technical Specification 05000416/LER-2023-001, Valve Closure Test Failure Resulting in Condition Prohibited by Technical Specification2023-08-0303 August 2023 Valve Closure Test Failure Resulting in Condition Prohibited by Technical Specification 05000416/LER-2022-003, Manual Reactor Scram Due to Trip of the a Reactor Feedwater Pump2023-02-16016 February 2023 Manual Reactor Scram Due to Trip of the a Reactor Feedwater Pump 05000416/LER-2022-002, Loss of Secondary Containment During Standby Gas Treatment System Testing Due to Boundary Leakage2022-12-19019 December 2022 Loss of Secondary Containment During Standby Gas Treatment System Testing Due to Boundary Leakage 05000416/LER-2021-001-01, Primary Containment Outer Airlock Door Inoperable Due to Unacceptable Leak Rate2022-11-30030 November 2022 Primary Containment Outer Airlock Door Inoperable Due to Unacceptable Leak Rate 05000416/LER-2022-001, For Grand Gulf Nuclear Station, Unit 1, Manual Reactor Trip Due to the Loss of Balance of Plant Transformer 232022-08-29029 August 2022 For Grand Gulf Nuclear Station, Unit 1, Manual Reactor Trip Due to the Loss of Balance of Plant Transformer 23 05000416/LER-2021-005, Oscillation Power Range Monitors (Oprms) Technical Specification Noncompliance2022-02-0202 February 2022 Oscillation Power Range Monitors (Oprms) Technical Specification Noncompliance 05000416/LER-2021-004, Procedure Inadequacy Resulted in Core Monitoring System Miscalibration and Violation of Technical Specification2022-01-19019 January 2022 Procedure Inadequacy Resulted in Core Monitoring System Miscalibration and Violation of Technical Specification 05000416/LER-2021-003, High Pressure Core Spray Declared Inoperable2021-11-0404 November 2021 High Pressure Core Spray Declared Inoperable 05000416/LER-2016-0082017-08-16016 August 2017 Entry into Mode of Applicability with the Alternate Decay Heat Removal System Inoperable, LER 16-008-001 for Grand Gulf, Unit 1, Regarding Entry into Mode of Applicability with the Alternate Decay Heat Removal System Inoperable 05000416/LER-2016-0092017-08-16016 August 2017 Entry into Mode of Applicability with the Oscillation Power Range Monitor Upscale Settings Incorrectly Set, LER 16-009-01 for Grand Gulf, Unit 1, Regarding Entry into Mode of Applicability with the OPRM Upscale Settings Incorrectly Set 05000416/LER-2017-0012017-03-28028 March 2017 High Pressure Core Spray (HPCS) Jockey Pump Trip, LER 17-001-00 for Grand Gulf, Unit 1, Regarding High Pressure Core Spray Jockey Pump Trip 05000416/LER-2016-0012016-05-16016 May 2016 Valid Engineered Safety Feature Actuation and Temporary Loss of Residual Heat Removal, LER 16-001-00 for Grand Gulf, Unit 1, Regarding Valid Engineered Safety Feature Actuation and Temporary Loss of Residual Heat Removal GNRO-2014/00049, Report Pursuant to 10 CFR 71.95 (a)(3) and (B) of Seven Potential Instances of Noncompliance with Certificate of Compliance No. 9233 for TN-RAM Package, Revision 112014-07-31031 July 2014 Report Pursuant to 10 CFR 71.95 (a)(3) and (B) of Seven Potential Instances of Noncompliance with Certificate of Compliance No. 9233 for TN-RAM Package, Revision 11 ML12157A1822012-05-23023 May 2012 Attachment 9 to GNRO-2012/00039 - Entergy Nuclear Grand Gulf Nuclear Station License Renewal Environmental Audit - Hydrology Patton - Attachment L Labeled Reporting Documentation - Unit 2 Sumps. ML0627100452005-08-22022 August 2005 Final Precursor Analysis - Grand Gulf, Unit 1 2024-08-26
[Table view] |
Text
GNRO-2016/00044 August29,2016 U.S.Nuclear Regulatory Commission Attn: DocumentControlDesk Washington,DC20555-0001 Entergy Operations, Inc.P.o.Box 756PortGibson,MS 39150JamesNadeauManager,Regulatory AssuranceGrandGulfNuclearStation Tel.(601)437-2103
SUBJECT:
LicenseeEventReport(LER) 2016-006-00,MultipleValid Engineered Safety Feature Actuations Grand Gulf NuclearStation,Unit1DocketNo.50-416LicenseNo.NPF-29
DearSirorMadam:
AttachedisLicenseeEventReport(LER) 2016-006-00,whichwillbe supplemented uponcompletionofthe in-progressrootcauseevaluation.Thisreportis submitted in accordance withTitle10CodeofFederal Regulations 50.73(a)(2)(iv)(A).Thislettercontainsnonew Regulatory Commitments.Ifyouhaveany questionsorrequireadditional information,pleasecontactJamesNadeauat601-437-2103.
JJN/sas
Attachment:
LicenseeEventReport(LER) 2016-006-00cc:(SeeNextPage)
GNRO-20 16/00044Page2of2cc:U.S.Nuclear Regulatory CommissionATTN:Mr.JimKim, NRR/DORL (w/2)MailStop OWFN8B1Rockville,MD 20852-2738 U.S.Nuclear Regulatory CommissionATTN:Mr.KrissM.
Kennedy (w/2)Regional Administrator,RegionIV1600EastLamar BoulevardArlington,TX76011-4511Mr.B.J.Smith(w/2)Director,Divisionof Radiological HealthMississippiState DepartmentofHealthDivisionof Radiological Health3150Lawson Street Jackson,MS39213 NRC Senior Resident InspectorGrandGulf Nuclear StationPortGibson,MS39150 AttachmenttoGNRO 2016/00044LicenseeEventReport(LER) 2016-006-00 NRCFORM366 U.S.NUCLEAR REGULATORY COMMISSIONAPPROVEDBYOMB:NO.3150-0104EXPIRES:10/31/2018 (11-2015)Estimatedburdenperresponsetocomplywiththismandatorycollection V'-R REGO(request:80hours.Reportedlessonslearnedareincorporatedintothe
.::;v" ,,/" LICENSEEEVENTREPORT(LER)licensingprocessandfedbacktoindustry.Sendcommentsregardingburden......(Seereverseforrequired number ofestimatetothe FOINPrivacySection(T-5F53),U.S.NuclearRegulatory
- !('lCommission,Washington,DC20555-0001,orbyinternete-mailto
..: 0<digits/charactersforeachblock)infocollects.resource@nrc.gov,andtotheDeskOfficer,OfficeofInformation
...Y:andRegulatoryAffairs,NEOB-10202,(3150-0104),OfficeofManagement o" i.?andBudget,Washington,DC20503.Ifameansusedtoimposean
....,."'?informationcollectiondoesnotdisplayacurrentlyvalidOMBcontrolnumber,"'....theNRCmaynotconductorsponsor,andapersonisnotrequiredtorespondto,theinformationcollection.
1.FACILITY NAME 2.DOCKET NUMBER 13.PAGEGrandGulfNuclearStation,Unit1 050004161OF34.TITLEMultipleValidEngineeredSafetyFeatureActuations5.EVENTDATE6.LER NUMBER7.REPORTDATE8.OTHER FACILITIES INVOLVED YEAR I SEQUENTIAL I REV MONTHFACILITYNAMEDOCKETNUMBER MONTH DAY YEARNUMBERNO.DAYYEAR N/A05000N/AJune302016 2016-006-00 08 29 2016FACILITYNAMEDOCKETNUMBER N/A05000N/A 9.OPERATINGMODE11.THISREPORTIS SUBMITTED PURSUANTTOTHE REQUIREMENTSOF10CFR§: (Checkallthat apply)4 o20.2201(b) o 20.2203(a)(3)(i) o 50.73(a)(2)(i)(C) o 50.73(a)(2)(vii) o20.2201(d) o 20.2203(a)(3)(ii) o 50.73(a)(2)(ii)(A) o 50.73(a)(2)(viii)(A) o 20.2203(a)(1) o 20.2203(a)(4) o 50.73(a)(2)(ii)(B) o 50.73(a)(2)(viii)(B) o 20.2203(a)(2)(i) o50.36(c)(1)(i)(A) o 50.73(a)(2)(iii) o 50.73(a)(2)(ix)(A)10.POWER LEVEL o 20.2203(a)(2)(ii) o50.36(c)(1)(ii)(A)50.73(a)(2)(iv)(A) o 50.73(a)(2)(x) 0 o 20.2203(a)(2)(iii) o 50.36(c)(2) o 50.73(a)(2)(v)(A) o73.71(a)(4) o 20.2203(a)(2)(iv) o 50.46(a)(3)(ii) o 50.73(a)(2)(v)(B) o73.71(a)(5) o 20.2203(a)(2)(v) o 50.73(a)(2)(i)(A) o 50.73(a)(2)(v)(C) o OTHER o 20.2203(a)(2)(vi) o 50.73(a)(2)(i)(B) o 50.73(a)(2)(v)(D)SpecifyinAbstractbeloworinNRCForm366A 12.LICENSEE CONTACTFORTHISLERFACILITYNAME I TELEPHONE NUMBER(IncludeAreaCode)JamesNadeau/Manager,Regulatory Assurance (601)437-2103 13.COMPLETEONELINEFOREACH COMPONENT FAILURE DESCRIBEDINTHISREPORTCAUSESYSTEM COMPONENTMANU-REPORTABLECAUSESYSTEM COMPONENT MANU-REPORTABLEFACTURERTOEPIX FACTURERTOEPIX N/A N/A N/A N/A N/AN/AN/AN/A N/A N/A 14.SUPPLEMENTAL REPORT EXPECTED 15.EXPECTED MONTHDAYYEAR SUBMISSION 11 17 2016[8J YES(Ifyes, complete 15.EXPECTED SUBMISSION DA TE)DNO DATE ABSTRACT(Limitto1400spaces,i.e., approximately 15 single-spacedtypewrittenlines)OnJune30,2016at1715CDT,GrandGulfNuclearStation(GGNS) experiencedanelectricalpowersupplylossfrom Service Transformer21whichresultedinpowersupplybeinglosttoDivision2(16ABBus)andDivision3(17ACBus)ESFbuses.ThisresultedinavalidactuationofDivision2andDivision3Diesel Generatorsonbusundervoltage.They both automaticallystartedandenergizedtheirrespectiveESFbusesasdesigned.Duringthisevent,thelossofpowertotheDivision2(16ABBus)resultedinaDivision2RPSbuspowerloss,whichactuatedaDivision2RPShalfSCRAM signal.Thepowerlossalsoresultedinalossofthe InstrumentAirpressureresultinginsomeControlRodScramValvestodriftopen.ThisinturncausedtheScramDischargeVolumetofilltothepointwhereaDivision1RPShalfSCRAMsignalwasinitiatedfromScramDischargeVolumelevelhighonChannel'A'.ThisresultedinavalidfullRPSReactorSCRAMwhilenotcritical.InstrumentAirpressurewasrestoredandtheSCRAMsignalwasresetat1733CDT.
Appropriateoffnormaleventprocedureswereenteredtomitigatethetransient.Allsafety systemsperformedasexpected.ThedirectcausewasafaultedCphase34.5kVService TransformerpowersupplycabletotheBOP23Transformer.Atemporarythreephaseoverheadlinewasinstalledtobypassthefaulted34.5kVcablesection.
APPROVEDBYOMB:NO.
3150-0104EXPIRES:10/31/2018Estimatedburdenperresponsetocomplywiththismandatorycollectionrequest:80hours.Reportedlessonslearnedare incorporatedintothelicensingprocessandfedbacktoindustry.SendcommentsregardingburdenestimatetotheFOIA,PrivacyandInformationCollectionsBranch (l-5F53),U.S.NuclearRegulatoryCommission,Washington,DC20555-0001,orbyinternete-mailto Infocoliects.Resource@nrc.gov,andtotheDeskOfficer,OfficeofInformationandRegulatoryAffairs,NEOB-10202,(3150-0104),OfficeofManagementandBudget,Washington,DC20503.IfameansusedtoimposeaninformationcollectiondoesnotdisplayacurrentlyvalidOMBcontrolnumber,theNRCmaynotconductorsponsor,andapersonisnotrequiredtorespondto,theinformationNRCFORM (11-2015)366AU.S.NUCLEAR REGULATORY COMMISSION LICENSEE EVENT REPORT (LER)CONTINUATION SHEET collection.Page2of3 1.FACILITY NAMEGrandGulf NuclearStation,Unit1 NARRATIVE 2.DOCKET 05000416 YEAR I3.LER NUMBER SEQUENTIAL NUMBER 2016-006-00 I REV.NO.PLANT CONDITIONSPRIORTOTHEEVENTAtthetimeoftheevent,GrandGulfNuclearStation(GGNS)Unit1wasinMode4,ColdShutdown,withMainSteamIsolationValves(MSIVs)[SB]closed.Reactor WaterLevelwas maintainedinthenormalwaterlevelbandbytheControlRodDriveSystem(CRDS)[AA].ResidualHeatRemoval(RHR)A[BO]wasmaintainedinShutdownCoolingoperationanditwasnotaffectedbythisevent.
DESCRIPTIONOnJune30,2016at17:15,GrandGulfNuclearStation experiencedanelectricalpowersupplylossfromService Transformer21(ST21)[XFMR]whichresultedin powersupplybeinglosttoDivision2(16ABBus)andDivision3(17ACBus)EngineeredSafetyFeature(ESF)buses[BU].ThisresultedinavalidactuationofDivision2andDivision3StandbyDiesel Generators(SDGs)[EK]onunder-voltage.BothSDGs automaticallystartedandenergizedtheirrespectiveESFbusesasdesigned.Duringthisevent,thelossofpowertotheDivision2(16ABbus)resultedinaDivision2ReactorProtectionSystem(RPS)[JE]buspowerloss,whichactuatedaDivision2RPShalfSCRAMsignal.TheDivision2powerlossalsoresultedinalossofInstrumentAirpressureresultinginsomeControlRodScramValvestodriftopen.ThisinturncausedtheScramDischargeVolumetofilltothepointwhereaDivision1RPShalfSCRAMsignalwasinitiatedfromScramDischargeVolumelevelhighonChannelA.ThisresultedinavalidfullRPSReactorSCRAMwhilenotcritical.
InstrumentAirpressurewasrestoredandtheSCRAMsignalwasresetat1733hrs.Appropriateoffnormaleventprocedureswereenteredtomitigatethetransient.NoECCS[BM]initiationsignalswerereached.Allsafetysystemsperformedasexpected.
REPORTABILITYEventNotificationNo.52057wasmadetotheNRC OperationsCenter.ThisLERisbeingsubmittedpursuanttoTitle10CodeofFederalRegulations10CFR 50.73(a)(2)(iv)(A)fortheactuationofEngineeredSafetyFeatures.TelephonicnotificationwasmadetotheU.S.
Nuclear Regulatory Commission (NRC)Emergency NotificationSystemonJune30,2016,within8hoursoftheevent,pursuantto10CFR 50.72(b)(3)(iv)formultiplevalidspecifiedsystemactuations.
CAUSEDirectCause:AfaultedCphase34.5kVService Transformer21powersupplycabletotheBOP23 Transformerresultinginthelossofpowertothe21Rbus.ApparentCause:InvestigationoftheApparentCauseispngoing.A supplementalreporttothisLERwillbeprovidedupon completionoftheApparentCause investigation APPROVEDBYOMB:NO.3150-0104EXPIRES:10/31/2018Estimatedburdenperresponsetocomplywiththismandatorycollectionrequest:80hours.Reportedlessonslearnedareincorporatedintothelicensingprocessandfedbacktoindustry.SendcommentsregardingburdenestimatetotheFOIA,PrivacyandInformationCollectionsBranch(T-5F53),U.S.NuclearRegulatoryCommission,Washington,DC20555-0001,orbyinternete-mailto Infocoliects.Resource@nrc.gov,andtotheDeskOfficer,OfficeofInformationandRegulatoryAffairs,NEOB-10202,(3150-0104),OfficeofManagementandBudget,Washington,DC20503.IfameansusedtoimposeaninformationcollectiondoesnotdisplayacurrentlyvalidOMBcontrolnumber,theNRCmaynotconductorsponsor,andapersonisnotrequiredtorespondto,theinformationNRCFORM (11-2015)366AU.S.NUCLEAR REGULATORY COMMISSION LICENSEE EVENT REPORT (LER)CONTINUATION SHEET collection.Page3of3 1.FACILITY NAMEGrandGulf NuclearStation,Unit1 NARRATIVECORRECTIVEACTIONS 2.DOCKET 05000416 YEAR I3.LER NUMBER SEQUENTIAL NUMBER 2016-006-00 I REV.NO.Temporarilyinstalledathreephaseoverheadline,tobypassthefaulted34.5kVcablesection.
SAFETY SIGNIFICANCETheeventposednothreattothehealthandsafetyofthegeneralpublicorto nuclearsafetyassystemsperformedasdesigned.No Technical Specificationsafetylimitswereviolated.Industrialsafetywasnotchallenged,andtherewasnopotentialoractualradiologicalreleaseduringtheevent.PREVIOUSSIMILAREVENTSPrevioussimilareventswillbe discussedinthe supplementalreportuponcompletionoftheApparentCause investigation.