Similar Documents at Cook |
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Category:Letter
MONTHYEARIR 05000315/20230042024-01-31031 January 2024 Integrated Inspection Report 05000315/2023004 and 05000316/2023004 ML24004A1582024-01-19019 January 2024 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0039 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) AEP-NRC-2024-01, Emergency Plan Revision 482024-01-0808 January 2024 Emergency Plan Revision 48 AEP-NRC-2023-56, Report Per Technical Specification 5.6.6 for Inoperability of Unit 1 Post Accident Monitoring Reactor Coolant (Loop 3 Cold Leg) Wide Range Temperature Recorder Thermal Sensor2023-12-20020 December 2023 Report Per Technical Specification 5.6.6 for Inoperability of Unit 1 Post Accident Monitoring Reactor Coolant (Loop 3 Cold Leg) Wide Range Temperature Recorder Thermal Sensor ML23352A3502023-12-19019 December 2023 Dc. Cook Nuclear Power Plant, Units 1 Biennial Licensed Operator Requalification Program Inspection and Request for Information ML23338A2642023-12-0505 December 2023 Confirmation of Initial License Examination AEP-NRC-2023-45, Unit 2 - Schedular Exemption for Enhanced Weapons, Firearms, Background Checks, and Security Event Notifications Implementation2023-11-16016 November 2023 Unit 2 - Schedular Exemption for Enhanced Weapons, Firearms, Background Checks, and Security Event Notifications Implementation IR 05000315/20234042023-11-0606 November 2023 Cyber Security Inspection Report 05000315/2023404 and 05000316/2023404 ML23310A1152023-11-0606 November 2023 Notification of the NRC Baseline Inspection and Request for Information, Inspection Report 05000316/2024002 IR 05000315/20234032023-09-19019 September 2023 Security Baseline Inspection Report 05000315/2023403 and 05000316/2023403 IR 05000315/20230112023-08-31031 August 2023 Functional Engineering Inspection - Commercial Grade Dedication Report 05000315/2023011 and 05000316/2023011 ML23242A1832023-08-30030 August 2023 Notification of NRC Baseline Inspection and Request for Information; Inspection Report05000315/2023004 AEP-NRC-2023-40, Annual Report of Loss-of-Coolant Accident Evaluation Model Changes2023-08-29029 August 2023 Annual Report of Loss-of-Coolant Accident Evaluation Model Changes IR 05000315/20234022023-08-11011 August 2023 Security Baseline Inspection Report 05000315/2023402 and 05000316/2023402 AEP-NRC-2023-34, Supplement to Request for Approval of Change Regarding Neutron Flux Instrumentation2023-08-0202 August 2023 Supplement to Request for Approval of Change Regarding Neutron Flux Instrumentation IR 05000315/20230022023-07-24024 July 2023 Integrated Inspection Report 05000315/2023002 and 05000316/2023002 ML23178A2422023-06-28028 June 2023 Reassignment of the U.S. Nuclear Regulatory Commission Branch Chief in the Division of Operating Reactor Licensing for Plant Licensing Branch III IR 05000315/20230122023-06-22022 June 2023 Biennial Problem Identification and Resolution Inspection Report 05000315/2023012 and 05000316/2023012 IR 05000315/20235012023-06-21021 June 2023 Emergency Preparedness Biennial Exercise Inspection Report 05000315/2023501 and 05000316/2023501 AEP-NRC-2023-29, Core Operating Limits Report2023-06-19019 June 2023 Core Operating Limits Report ML23159A0192023-06-13013 June 2023 Information Meeting with a Question and Answer Session to Discuss NRC 2022 End-Of-Cycle Plant Performance Assessment of Donald C. Cook Nuclear Plant, Units 1 and 2 AEP-NRC-2023-32, Response to NRC Regulatory Issue Summary 2023-1 Preparation and Scheduling of Operator Licensing Examinations2023-06-0606 June 2023 Response to NRC Regulatory Issue Summary 2023-1 Preparation and Scheduling of Operator Licensing Examinations AEP-NRC-2023-33, Renewable Operating Permit2023-06-0505 June 2023 Renewable Operating Permit AEP-NRC-2023-30, Follow-Up Notification of Ph Non-Compliance for Turbine Room Sump2023-06-0101 June 2023 Follow-Up Notification of Ph Non-Compliance for Turbine Room Sump AEP-NRC-2023-27, Annual Radiological Environmental Operating Report2023-05-15015 May 2023 Annual Radiological Environmental Operating Report ML23131A3282023-05-11011 May 2023 D.C. Cook Information Request for the Cyber-Security Baseline Inspection, Notification to Perform Inspection 05000315/2023404 and 05000316/2023404 IR 05000315/20230012023-05-0303 May 2023 Integrated Inspection Report 05000315/2023001 and 05000316/2023001 AEP-NRC-2023-19, Annual Radioactive Effluent Release Report2023-04-30030 April 2023 Annual Radioactive Effluent Release Report ML23117A0062023-04-27027 April 2023 Review of the Spring 2022 Steam Generator Tube Inspections Report ML23114A1142023-04-25025 April 2023 Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection AEP-NRC-2023-23, Annual Report of Individual Monitoring for 20222023-04-24024 April 2023 Annual Report of Individual Monitoring for 2022 AEP-NRC-2023-24, Notification of Ph Non-Compliance for Turbine Room Sump2023-04-12012 April 2023 Notification of Ph Non-Compliance for Turbine Room Sump AEP-NRC-2023-20, Annual Report of Property Insurance2023-04-0303 April 2023 Annual Report of Property Insurance AEP-NRC-2023-15, Decommissioning Funding Status Report2023-03-28028 March 2023 Decommissioning Funding Status Report ML23076A0212023-03-20020 March 2023 Request for Information for NRC Commercial Grade Dedication Inspection; Inspection Report 05000315/2023011; 05000316/2023011 IR 05000315/20234012023-03-16016 March 2023 Security Baseline Inspection Report 05000315/2023401 and 05000316/2023401 ML23066A1882023-03-0707 March 2023 Information Request to Support Upcoming Problem Identification and Resolution (Pi&R) Inspection at Donald C. Cook Nuclear Plant IR 05000315/20220062023-03-0101 March 2023 Annual Assessment Letter for Donald C. Cook Nuclear Plant, Units 1 and 2 (Report 05000315/2022006 and 05000316/2022006) IR 05000315/20220042023-02-0101 February 2023 Integrated Inspection Report 05000315/2022004 and 05000316/2022004 and Exercise of Enforcement Discretion AEP-NRC-2023-11, Form OAR-1, Owner'S Activity Report2023-01-31031 January 2023 Form OAR-1, Owner'S Activity Report IR 05000315/20230102023-01-31031 January 2023 Phase 4 Post-Approval License Renewal Inspection Report 05000315/2023010 and 05000316/2023010 AEP-NRC-2023-02, Request for Approval of Change Regarding Neutron Flux Instrumentation2023-01-26026 January 2023 Request for Approval of Change Regarding Neutron Flux Instrumentation ML22363A5622023-01-0404 January 2023 Relief Request ISIR-5-06 Related to ASME Code Case N-729-6 Supplemental Examination Requirements of Reactor Vessel Closure Head Penetration Nozzles AEP-NRC-2022-66, Report Per Technical Specification 5.6.6 for Inoperability of Unit 2 Post Accident Monitoring Neutron Flux Monitoring2022-12-15015 December 2022 Report Per Technical Specification 5.6.6 for Inoperability of Unit 2 Post Accident Monitoring Neutron Flux Monitoring AEP-NRC-2022-46, Notification of Deviation from Electric Power Research Institute (EPRI) Materials Reliability Program 2019-008, Interim Guidance for NEI 03-08 Needed Requirements for Us PWR Plants for Management of Thermal Fatigue in2022-12-12012 December 2022 Notification of Deviation from Electric Power Research Institute (EPRI) Materials Reliability Program 2019-008, Interim Guidance for NEI 03-08 Needed Requirements for Us PWR Plants for Management of Thermal Fatigue in ML22340A1392022-11-30030 November 2022 Submittal of Revision 31 to Updated Final Safety Analysis Report and 10CFR50.71(e) Updated and Related Site Change Reports IR 05000315/20220112022-11-0404 November 2022 Design Basis Assurance Inspection (Teams) Inspection Report 05000315/2022011 and 05000316/2022011 IR 05000315/20220032022-10-28028 October 2022 Integrated Inspection Report 05000315/2022003 and 05000316/2022003 AEP-NRC-2022-58, U1C31 Steam Generator Tube Inspection Report2022-10-24024 October 2022 U1C31 Steam Generator Tube Inspection Report AEP-NRC-2022-61, Request for Relief Related to American Society of Mechanical Engineers (ASME) Code Case N-729-6 Supplemental Examination Requirements, ISIR-5-062022-10-24024 October 2022 Request for Relief Related to American Society of Mechanical Engineers (ASME) Code Case N-729-6 Supplemental Examination Requirements, ISIR-5-06 2024-01-08
[Table view] Category:Licensee Event Report (LER)
MONTHYEAR05000316/LER-2017-0012017-05-19019 May 2017 1 OF 5, LER 17-001-00 for Cook, Unit 2 re Containment Hydrogen Skimmer Ventilation Fan #1 Inoperable Longer than Allowed by Technical Specifications 05000316/LER-2016-0022017-02-0909 February 2017 Emergency Diesel Generators Declared Inoperable Due to a Manufacturing Design Issue, LER 16-002-00 for Donald C. Cook Nuclear Plant Unit 2 Regarding Emergency Diesel Generators Declared Inoperable Due to a Manufacturing Design Issue 05000316/LER-2016-0012016-08-31031 August 2016 Manual Reactor Trip Due To Moisture Separator Heater Expansion Joint Failure, LER 16-001-00 for Donald C. Cook Nuclear Plant, Unit 2 Regarding Manual Reactor Trip Due To Moisture Separator Heater Expansion Joint Failure ML16193A3902016-07-15015 July 2016 Donald C. Cook Nuclear Plant Unit 2 - A Loss of Main Condenser Event Occurred Due to a Storm-Induced Debris Damage of the Circulating Water System Pumps in the Forebay (LER-316-2014-003-00) 05000315/LER-2015-0022016-01-18018 January 2016 -Technical Specification Violation due to Inoperable Residual. Heat Removal Pump, LER 15-002-01 for D.C. Cook, Unit 1, Regarding Technical Specification Violation Due to Inoperable Residual Heat Removal Pump 05000316/LER-2015-0012016-01-15015 January 2016 Manual Reactor Trip Due To A Secondary Plant Transient, LER 15-001-01 for D.C. Cook, Unit 2, Regarding Manual Reactor Trip Due to a Secondary Plant Transient ML0528703602005-10-0505 October 2005 Special Report for D. C. Cook Unit 2 Re Unit 2 Reactor Coolant Inventory Tracking System ML0508903452005-03-22022 March 2005 LER 99-001-01 Donald C. Cook Nuclear Plant Unit 2, Regarding Supplemental LER for Degraded Component Cooling Water Flow to Containment Main Steam Line Penetrations ML0210601432002-04-12012 April 2002 LER 02-02-00, Donald C. Cook Nuclear Plant Unit 2, Technical Specification 3.9.4.c Was Violated During Core Alteration ML0209205342002-03-15015 March 2002 LER 99-012-01 for Cook Nuclear Plant, Unit 1 Re Auxiliary Building ESF Ventilation System May Not Be Capable of Maintaining ESF Room Temperature Post-Accident ML9936300511999-12-20020 December 1999 LER 99-S004-00, Intentionally Falsifying Documentation Results in Unauthorized Unescorted Access, on 11/18/99. with Letter Dated 12/20/99 ML9934002411999-11-29029 November 1999 LER 315/99-027-00, Underrated Fuses Used in 250 Vdc System Could Result in Lack of Protective Coordination ML18219B5201978-09-27027 September 1978 09/27/1978 Letter Enclosure of Licensee Event Report ML18219E1521978-09-27027 September 1978 Submit Licensee Event Report Nos. RO 78-051/03L-0 & RO 78-052/03L-0 ML18219B5211978-09-19019 September 1978 09/19/1978 Letter Enclosure of Licensee Event Report ML18219E1531978-09-18018 September 1978 Submit Licensee Event Report No. RO 78-050/03L-0 ML18219B5541978-09-18018 September 1978 Letter from Indiana & Michigan Power Co to NRC Submitting Licensee Event Report (RO 78-062/03L-0) ML18219B5551978-09-12012 September 1978 Letter from Indiana & Michigan Power Co to NRC Submitting Licensee Event Reports (RO 78-56/03L-1 and RO 78-061/03L-0) ML18219E1541978-09-12012 September 1978 Submit Licensee Event Report No. RO 78-049/03L-0 ML18219B5561978-09-0808 September 1978 Letter from Indiana & Michigan Power Co to NRC Submitting Licensee Event Reports (RO 78-059/03L-1 and RO 78-060/03L-0) ML18219E1551978-09-0808 September 1978 Submit Licensee Event Report No. RO 78-048/03L-0 ML18219B5571978-09-0505 September 1978 Letter from Indiana & Michigan Power Co to NRC Submitting License Event Report RO 78-059/03L-0 ML18219B5581978-08-30030 August 1978 Letter from Indiana & Michigan Power Co to NRC Submitting Licensee Event Report RO 78-058/03L-0 ML18219B5621978-08-22022 August 1978 Letter from Indiana & Michigan Power Co to NRC Submitting Licensee Event Reports (RO 78-056/03L-0 and RO 78-057/03L-0) ML18219B5611978-08-18018 August 1978 Letter from Indiana & Michigan Power Co to NRC Submitting Licensee Event Reports (RO 78-052/03L-0, RO 78-053/03L-0, RO 78-054-03L-0 and RO 78-055/03L-0) ML18219E1561978-08-15015 August 1978 Submit Licensee Event Report No. RO 78-047/03L-0 ML18219E1571978-08-14014 August 1978 Submit Licensee Event Report Nos. RO 78-045/03L-0 & RO 78-046/03L-0 ML18219E1581978-08-14014 August 1978 Submit Licensee Event Report Nos. RO 78-043/03L-1 & RO 78-044/03L-1 ML18219E1601978-08-11011 August 1978 Submit Licensee Event Report Nos. 1978-043-03L & 1978-044-03L ML18219B5641978-08-10010 August 1978 Letter from Indiana & Michigan Power Co to NRC Submitting Licensee Event Report (RO 78-051/03L-0) ML18219B5651978-08-0909 August 1978 Letter from Indiana & Michigan Power Co to NRC Submitting Licensee Event Report (RO 78-049/03L-1) ML18219B5661978-08-0808 August 1978 Letter from Indiana & Michigan Power Co to NRC Submitting Licensee Event Report (RO 78-050/03L-0) ML18219B5671978-08-0404 August 1978 Letter from Indiana & Michigan Power Co to NRC Submitting Licensee Event Report (RO 78-049/03L-0) ML18219B5681978-08-0202 August 1978 Letter from Indiana & Michigan Power Co to NRC Submitting Licensee Event Reports (RO 78-029/03L-1 and RO 78-048/03L-0) ML18219B5691978-07-21021 July 1978 Letter from Indiana & Michigan Power Co to NRC Submitting Licensee Event Reports (RO 78-019/03L-1 and RO 78-023/03L-1) ML18219B5701978-07-18018 July 1978 Letter from Indiana & Michigan Power Co to NRC Submitting Licensee Event Report (RO 78-047/03L-0) ML18219B5711978-07-11011 July 1978 Letter from Indiana & Michigan Power Co to NRC Submitting Licensee Event Report (RO 78-043/03L-0), Submitted Late Due to a Paper Defect ML18219B5721978-07-11011 July 1978 Letter from Indiana & Michigan Power Co to NRC Submitting Licensee Event Reports (RO 78-034/03L-1, RO 78-044/03L-0, RO 78-045/03L-0, RO 78-046/03L-0) ML18219B5731978-07-0505 July 1978 Letter from Indiana & Michigan Power Co to NRC Submitting Licensee Event Report (RO 78-042/03L-0) ML18219B5751978-06-29029 June 1978 Letter from Indiana & Michigan Power Co to NRC Submitting Licensee Event Report (RO 50-316/78-037), Stating Corrective Actions Taken IR 05000316/19780371978-06-29029 June 1978 Letter from Indiana & Michigan Power Co to NRC Submitting Licensee Event Report (RO 50-316/78-037), Stating Corrective Actions Taken ML18219B5771978-06-22022 June 1978 D.C. Cook - Submit Licensee Event Report RO 78-036/03L-0 for Unit 2 ML18219B5761978-06-21021 June 1978 Letter from Indiana & Michigan Power Co to NRC Submitting Licensee Event Report (RO 78-035/03L-0), a Resubmittal of LER 78-034/03L-0 Dated 6/19/1978 IR 05000316/19780341978-06-19019 June 1978 D.C. Cook - Submit Licensee Event Report RO 50-316/78-034/03L-0 for Unit 2 ML18219B5781978-06-19019 June 1978 D.C. Cook - Submit Licensee Event Report RO 50-316/78-034/03L-0 for Unit 2 ML18219B5221978-06-0606 June 1978 06/06/1978 Letter Licensee Event Report ML18219B5741978-06-0303 June 1978 Letter from Indiana & Michigan Power Co to NRC Submitting Licensee Event Reports (RO 78-038/03L-0, RO 78-039/03L-0, RO 78-040/03L-0, RO 78-041/03L-0) ML18219B5241978-06-0202 June 1978 06/02/1978 Letter Licensee Event Report ML18219B5231978-06-0202 June 1978 06/02/1978 Letter Licensee Event Report ML18219B5251978-05-25025 May 1978 05/25/1978 Letter Licensee Event Report 2017-05-19
[Table view] |
Inspection Report - Cook - 1978034 |
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REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)DISTRIBUTION FOR INCOMING MATERIAL 50-316 REC: KEPPLER J G NRC ORG: SHALLER D V IN 5 MI PWR DOCDATE: 06fi9/78 DATE RCVD: 06/23/76 DOCTYPE: LETTER NOTARIZED:
NO COPIES RECEIVED SUBJECT: LTR 1 ENCL 1 FORWARDING LICENSEE EVENT REPT (RO 50-316/78-034)
ON 05/19/78 CONCERNING WHILE IN MODE 1 OPERATION REACTOR COOLANT SYSTEM UNIDENTIFIED LEAKAGE EXCEEDED TECH SPEC 3.4.6.2.8 LIMIT...W/ATT.PLANT NAME: COOK-UNIT 2 REVIEWER INITIAL: X JM DISTRIBUTOR INITIAL:~DISTRIBUTION OF THIS MATERIAL IS AS FOLLOWS NOTES: 1.SEND 3 COPIES OF ALL MATERIAL TO ISE'D REEVES-1 CY ALL MATERIAL INCIDENT REPORTS (DISTRIBUTION CODE A002>FOR ACTION: INTERNAL: EXTERNAL: BR LWRN2 BC4~W/4 ENCL/ENCL I 5 E~~W/~ENCL I 0 C SYSTEMS BR++W/ENCL NOVAK/CHECK44W/ENCL AD FOR ENG++W/ENCL HANAUER~~W/ENCL AD FOR SYS 5 PROJ++W/ENCL ENGINEERING BR4+W/ENCL KREGER/J.COLLINS++Wf ENCL K SEYFRIT/IE+4W/ENCL LPDR'S ST.JOSEPH'I++Wf ENCL TI C~~W/ENCL NSIC++Wf ENCL ACRS CAT 8++W/16 ENCL NRC PDR++W/ENCL MIPC44W/3 ENCL EMERGENCY PLAN BR>~W/ENCL EEB++W/ENCL PLANT SYSTEMS BR>+W/ENCL AD FOR PLANT SYSTEMS++W/ENCL REACTOR SAFETY BR++W/ENCL VOLLMER/BUNCII44W/ENCL POWER SYS BR+>W/ENCL DISTRIBUTION:
LTR 45 ENCL 45 SIZE: 1P+1P+1P CONTROL NBR: 781770010 PDR SPECIAL WEEKLY LIS FILE.l t.Vt Lb~IN-bu-b~O NE.~i ENGLAND POWER COMPANY NE.P Ai 50 06/07/IQ ACCE:SSION NBRo 77301-0153 a'~o~C" DOCUAENT SIdi: 1P LOCKE:T DATE,: RECP: VASSALLO D ORe: TE:DFSCO R TASK NB NOTARIZ LPDR: RE.CP ORS A SUBJECT: R4V.1 TO THE DRAFT SAFLTY E;V
~j.Op IHII.QIIW Igg pZ y f IIV DIA IVA 8 MICHIGA IV PO 8'ER COMPA IV V DONALD C.COOK NUCLEAR PLANT P.O.Box 458, Bridgman, Michigan 49106 June 19, 1978 (tn f%.a" C'll M CD f'n~CA~C, KI CD Hr.J.G.Keppler, Regional Director Office of Inspection and Enforcement United States Nuclear Regulatory Commission Region III 799 Roosevelt Road Glen Ellyn, IL 60137 i Operating License DPR-74 Docket No.50-316
Dear Hr.Keppler:
Pursuant to the requirements of the Appendix A Technical Specifications the following report is submitted:
RO 78-034/03L-O.
Sincerely, D.V.Shaller Plant Manager/bah CC: J.E.Dolan R.W.Jurgensen R.f.Kroeger R.Kilburn R.J.Vollen BPI K.R.Baker RO:III R.C.Callen MPSC P.W.Steketee, Esq.G.Charnoff, Esq.R.Walsh, Esq.G.Olson J.M.Hennigan PNSRC J.F.Stietzel Dir., IE (30 copies)Dir., MIPC (3 copies)781770010 U.S.NUCLEAR REGULATORY COMMISSION NRC FORM 366 LICENSEE EVENT REPORT 4 CONTROL BLOCK: tPLEASE PRINT OR TYPE ALL REQUIRED INFORMATION)
1 6 M 1 D C C 2 QE 0 0 0 0 0 0 0 0 0 0 OQE4 1 1 1 104~00 7 8 9 LICENSEE CODE 14 15 LICENSE NUMBER 25 26 LICENSE TYPE 30 57 CAT 58 CON'T Q Qs 0 6 I 9 Qe 7 8 60 61 DOCKET NUMBER 68 69 EVENT DATE'74 75 REPORT DATE 80 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES Qlo~O2 WHILE IN MODE I OPERATION REACTOR COOLANT SYSTEM UNIDENTIFIED LEAKAGE EX CEEDED TECH.SPEC.3.4.6.2.b LIMIT.UNIT WAS STARTED DOWN 4>HOURS AFTER~O4 DISCOVERY BUT WAS RETURNED TO ORIGINAL LOADING WHEN LEAKAGE INDICATED WI~Os THIN LIMITS.LEAKAGE EXCEEDED LIMITS THE SECOND TIME.THE UNIT WA'S STARTED~OB DOWN 4 HOURS AFTER DISCOVERY AND R M R~O7 REACTOR WAS COOLED DOWN TO M DE 5 IN THE T 17 HOURS.~OS 7 8 80~oe 7 8 SYSTEM CAUSE CAUSE COMP.VALVE.CODE CODE SUBCODE COMPONENT CODE SUBCODE SUBCODE~CE QT E Q>>~XQ>>V A L V E X Q74~EQEE~D QEE 9 10 11 12 13 18 19 20 SEQUENTIAL OCCURRENCE REPORT REVISION LERIRP EVENT YEAR REPORT NO.CODE TYPE NO.QTT REPORT Q++~03 4 21 22 23 24 26 27 28 29 30 31 32 ACTION FUTURE EFFECT SHUTDOWN ATTACHMENT NPRDC PRIME COMP.COMPONENT TAKEN ACTION ON PLANT METHOD HOURS~22 SUBMITTED FORM SUB.SUPPLIER h'IANUFACTURER
~AQIB~ZQle~AQ2O~AQ21~Y Q23~YQ24 MNQ>>A 5 A 5 QS 33 34 35 36 37 40 41 42 43 44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS Q27 o IS LATIO AND PACKING LEAKAGE.VALV P 3[NED TO OPERATING PRESS.AND TEMP, A AKA VALVE ON FAILED FUEL DET.C R F 4 D AND LEAKAGE WAS R D 80 80 80 45 80 80 80 NRC USE ONLY 00 O 80 Es 0 a PHONE: NAME Qf PRFPARFR'7 8 9 FACILITY~3P METHOD OF STATUS'YE POWER OTHER STATUS~DISCOVERY DISCOVERY DESCRIPTION Q32 s E Qss~08 0 QEE NA~BQ31 ROUTINE SURVEILLANCE 7 8 9 10 12 13 44 45 46 ACTIVITY CONTENT RELEASED OF RELEASE AMOUNT OF ACTIVITY~LOCATION OF RELEASE Q 6~Z Q33~ZQ34 NA 7 8 9 10 44 PERSONNEL EXPOSURES NUMBER TYPE DESCRIPTION Q3e~00 OJ0~'ss A 7 8 9 11 12 13 PERSONNEL INJURIES NUMBER DESCRIPTIONQ41 040 A 7 8 9 11 12 LOSS OF OR DAMAGE TO FACILITY Q43 TYPE DESCRIPTION e Z Q42 NA 7 8 9 10 PUBLICITY ISSUED DESCRIPTION Q~2O~NQ NA 7 8 9 10 68 69 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS INITIAL INSPECTION FOUND EXCESSIVE LEAKAGE FROM THE PACKING OF THE ISOLATION VALVE BETWEEN-THE REACTOR COOLANT SYSTEM AND THE RESIDUAL HEAT REMOVAL SYSTEM.THE PACKING BOX OF THIS VALVE WAS ALSO E(UIPPED WITH A STEAM LEAKOFF PIPED TO THE REACTOR COOLANT DRAIN, TANK.THIS VALVE IS A 14" TWIN DISK GATE MANUFACTURED BY COPES VULCAN WITH A'500 PSIG RATING.THE VAI VE,WAS REPACKED AND THE STEAM LEAKOFF WAS DISCONNECTED AND TERMINATED IN BOTH DIRECTIONS.
WHEN THE REACTOR COOLANT SYSTEM WAS RETURNED TO OPERATING PRESSURE AND TEMPERATURE THE LEAKAGE RATE WAS STILL IN EXCESS OF ALLOWABLE LIMITS.A 75 PSIG SET SAfETY VALVE IN THE FAILED FUEL DETECTOR SYSTEM WAS FOUND TO BE LEAKING THROUGH.THIS FINDING WAS 4 3/4 HOURS AFTER THE LEAK RATE BECAME KNOWN.THE SAFETY VAL'VE WAS ISOLATED AND THE LEAKAGE RATE REDUCED TO NORMAL.THIS SAFETY VALVE IS A 1/2" INLINE MANUFACTURED BY NUPROCO.MODEL 8 4A SS 8 CPA2-50.IT WAS REPLACED BY A DUPLICATE.
THE FAILED VALVE WAS NOT DISASSEMBLED TO DETERMINE FAILURE DUE TO HIGH CONTAMINA-INDIANA&MICHIGAN POS'EH COMPANY DONALD C.COOK NUCLEAR PLANT P.O.Box 458, Bridgman, Michigan 49106 June 19, 1978 Mr.J.G.Keppler, Regional Director Office of Inspection and Enforcement United States Nuclear Regulatory Commission.
Region III 799 Roosevelt Road Glen Ellyn, IL 60137 Operating~cense DPR-74 Docket.50-316
Dear Mr.Keppler:
Pursuant to the requirements of the Appendix A Technical Specifications the following report is submitted:
RO 78-034/03L-O.,
Sincerely, D.V.Shaller Plant Manager/bab cc: J.E.Dolan R.W.Jurgensen R.F.Kroeger R.Kilburn R.J.Vollen BPI K.R.Baker RO:III R.C.Callen MPSC P.W.Steketee, Esq.G~Charnoff, Esq.R.Walsh, Esq.G.Olson J.M.Hennigan PNSRC J.F.Stietzel Dir., IE (30 copies)Dir., MIPC (3 copies)JUi~j g I)978
~~e 4 U.S.NUCLEAR REGULATORY COMMISSION NRC FOI3%l 366 I7 7Y)~P~wW QB 0 6 I 9 7 Q9 EVENT DATE I4 75 REPORT DATE 80 LICENSEE EVENT REPORT CONTROL BLOCK: Qi{PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION)
I 6~o>N 1 0 C C 2 Q2 0 0 0 0 0 0 0 0 0 0 0 Qo 4 1 1 1 1 QE~QE 7 8 9 LICENSEE CODE 14 15 LICENSE NUMBER 25 26 LICENSE TYPE 30 57 CAT 58 CON'T~97 REPRRT 0 60 61 DOCKETNUMBER 68 69 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES Q10~02 WHILE IN MODE 1 OPERATION REACTOR COOLANT SYSTEM UNIDENTIFIED LEAKAGE EX~03 CEEDED TECH.SPEC.3.4.6.2.b LIMIT.UNIT WAS STARTED DOWN 4>HOURS AFTER~04 DISCOVERY BUT WAS RETURNED TO ORIGINAL LOADING WHEN LEAKAGE INDICATED WI~os THIN LIMITS.LEAKAGE EXCEEDED LIMITS THE SECOND TIME.THE UNIT".WA'5"STA'RTEI3
~06 DOWN 4 HOURS AFTER DISCOVERY A D RE D~0 7 REACTOR WAS COOLED DOWN TO MODE 5 IN THE EXT 1 HOURS.~OB 7 8 9 80~09 7 8 SYSTEM CAUSE CAUSE COMP.VALVE.CODE CODE SUBCODE COMPONENT CODE SUBCODE SUBCODE~CE Q11 E Q>>~XO V A C V E X Q4 LUQPE LJ Q>>9 10 11 12 13 18 19 20 SEQUENTIAL OCCURRENCE REPORT REVISION LF RIRO EVENT YEAR REPORT NO.CODE TYPE NO.Q17 REPORT~LI+~03 4 Q~LDJM LLj U L(J 21 22 23 24 26 27 28 29 30 31 32 ACTION FUTURE EFFECT SHUTDOWN ATTACHMENT NPRDP PRIME COMP.COMPONENT TAKEN ACTION ON PLANT METHOD HOURS Q22 SUBMITTED FORM SUB.SUPPLIER MANUFACTURER
~AO1B~z Q19~AQ20~AO2'VQ23 LYJQ24 LNJQ25 A 5 A 0 QE 33 34 35 36 37 40 41 42 43 44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS 027 o IS LATIO AND PACKING LEAKAGE.VALV R P PNN PN PPNPA NN AN~AN P.A A 3 VALVE ON FAILED FUEL DETEC F U D i F 4 D AND LEAKAGE WAS R D 45 7 8 9 7 8 9 11 12 LOSS OF OR DAMAGE TO FACILITY Q43 TYPE DESCRIPTION Z Q42 NA 7 8 9 FACILITY~30 METHOD OF STATUS%POWER OTHER STATUS~" DISCOVERY DISCOVERY DESCRIPTION Q32 5 E Q28~08 0 Q29 NA~BQ31 ROUTINE SURVEILLANCE 8 9 10 12 13 44 45 46 ACTIVITY CONTENT RELEASED OF RELEASE AMOUNT OF ACTIVITY~LOCATION OF RELEASE Q~z Q~ZO34 7 8 9 10 44 PERSONNEL EXPOSURES NUMBER TYPE DESCRIPTION Q39 7 L0¹0 0j Q3 7 Q3 8 7 8 9 11 12 13 PERSONNEL INJURIES NUMBER DESCRIPTIONQ 8~pp p Q4o 80 80 80 80 80 o 9 10 PUBLICITY ISSUED DESCRIPTION
~S L~IO44 NA 7 8 9" P 10 NAMEOF PREPARFR R.S.Keith PHONE: 80 NRC USE ONI.Y CE 0 80 0 0 Pp I i I L\
CAUSE DESCRIPTION AND CORRECTIVE ACTIONS INITIAL INSPECTION FOUND EXCESSIVE LEAKAGE FROM THE PACKING OF THE ISOLATION VALVE BETWEEN THE REACTOR COOLANT SYSTEM AND THE RESIDUAL HEAT REMOVAL SYSTEM.THE PACKING BOX OF THIS VALVE WAS ALSO EQUIPPED WITH A STEAM LEAKOFF PIPED TO THE REACTOR COOLANT DRAIN TANK.THIS VALVE IS A 14" TWIN DISK GATE MANUFACTURED BY COPES VULCAN WITH A 2500 PSIG RATING.THE VALVE WAS REPACKED AND THE STEAM LEAKOFF WAS DISCONNECTED AND TERMINATED IN BOTH DIRECTIONS.
WHEN THE REACTOR COOLANT SYSTEM WAS RETURNED TO OPERATING PRESSURE AND TEMPERATURE THE LEAKAGE RATE WAS STILL IN EXCESS OF ALLOWABLE LIMITS.A 75 PSIG SET SAFETY VALVE IN THE FAILED FUEL DETECTOR SYSTEM WAS FOUND TO BE LEAKING THROUGH.THIS FINDING WAS 4 3/4 HOURS AFTER THE LEAK RATE BECAME KNOWN.'THE SAFETY VAL>VE WAS ISOLATED AND THE LEAKAGE RATE REDUCED TO NORMAL.THIS SAFETY VALVE IS A 1/2" INLINE MANUFACTURED BY NUPROCO.MODEL 8 4A SS 8 CPA2-50.IT WAS REPLACED BY A DUPLICATE.
THE FAILED VALVE WAS NOT DISASSEMBLED TO DETERMINE FAILURE DUE TO HIGH CONTAMINA-
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