Similar Documents at Cook |
---|
Category:Letter
MONTHYEARAEP-NRC-2024-79, Unit 2, Independent Spent Fuel Storage Installation - Registration of Dry Spent Storage Cask2024-09-26026 September 2024 Unit 2, Independent Spent Fuel Storage Installation - Registration of Dry Spent Storage Cask AEP-NRC-2024-78, Reply to a Notice of Violation: EA-24-0472024-09-23023 September 2024 Reply to a Notice of Violation: EA-24-047 05000316/LER-2024-002, Manual Reactor Trip Following Rapid Downpower for Steam Leak2024-09-12012 September 2024 Manual Reactor Trip Following Rapid Downpower for Steam Leak IR 05000315/20244022024-09-10010 September 2024 Security Baseline Inspection Report 05000315/2024402 and 05000316/2024402, Independent Spent Fuel Storage Installation Security Inspection Report 07200072/2024401 AEP-NRC-2024-69, Core Operating Limits Report2024-09-0909 September 2024 Core Operating Limits Report IR 05000315/20243012024-09-0505 September 2024 NRC Initial License Examination Report 05000315/2024301 and 05000316/2024301 ML24225A0022024-09-0303 September 2024 Issuance of Amendment Nos. 363 and 344 Revising Technical Specifications Section 3.8.1, AC Sources-Operating, for a One-Time Extension of a Completion Time IR 05000315/20240112024-08-30030 August 2024 NRC Inspection Report 05000315/2024011 and 05000316/2024011 and Notice of Violation AEP-NRC-2024-51, Annual Report of Loss-Of-Coolant Accident Evaluation Model Changes2024-08-28028 August 2024 Annual Report of Loss-Of-Coolant Accident Evaluation Model Changes AEP-NRC-2024-76, Unit 2 - Supplement to License Amendment Request for One-Time Extension of Completion Time for Inoperable AC Source - Operating2024-08-28028 August 2024 Unit 2 - Supplement to License Amendment Request for One-Time Extension of Completion Time for Inoperable AC Source - Operating 05000316/LER-2024-003, Plant Shutdown Required by Technical Specifications Due to Reactor Coolant System Identified Leakage2024-08-22022 August 2024 Plant Shutdown Required by Technical Specifications Due to Reactor Coolant System Identified Leakage IR 05000315/20240052024-08-21021 August 2024 Updated Inspection Plan for Donald C. Cook Nuclear Plant, Units 1 and 2 (Report 05000315/2024005 and 05000316/2024005) AEP-NRC-2024-61, Unit 2 - Response to Request for Additional Information for Neutron Flux Instrumentation License Amendment Request2024-08-15015 August 2024 Unit 2 - Response to Request for Additional Information for Neutron Flux Instrumentation License Amendment Request ML24221A2702024-08-0808 August 2024 Unit 2 Independent Spent Fuel Storage Installation - Registration of Dry Spent Fuel Storage Cask AEP-NRC-2024-62, Unit 2, Independent Spent Fuel Storage Installation, Registration of Dry Spent Fuel Storage Cask2024-08-0707 August 2024 Unit 2, Independent Spent Fuel Storage Installation, Registration of Dry Spent Fuel Storage Cask ML24256A1482024-08-0202 August 2024 2024 Post Examination Submittal Letter AEP-NRC-2024-47, Form OAR-1, Owners Activity Report2024-07-30030 July 2024 Form OAR-1, Owners Activity Report ML24169A2142024-07-25025 July 2024 Issuance of Amendment No. 362 Regarding Change to Technical Specification 3.4.12, Low Temperature Overpressure Protection System ML24183A0162024-07-25025 July 2024 Review of Reactor Vessel Material Surveillance Program Capsule W Technical Report IR 05000315/20240022024-07-24024 July 2024 Integrated Inspection Report 05000315/2024002 and 05000316/2024002 ML24197A1262024-07-15015 July 2024 Unit 2 - Request for Additional Information (RAI) for License Amendment Request for One-Time Extension of Completion Time for Inoperable AC Source - Operating AEP-NRC-2024-52, Manual Reactor Trip Following Rapid Downpower for Steam Leak2024-07-15015 July 2024 Manual Reactor Trip Following Rapid Downpower for Steam Leak ML24191A0692024-07-0909 July 2024 Operator Licensing Examination Approval - Donald C. Cook Nuclear Power Plant, July 2024 AEP-NRC-2024-56, Unit 2, Independent Spent Fuel Storage Installation, Registration of Dry Spent Fuel Storage Cask2024-07-0808 July 2024 Unit 2, Independent Spent Fuel Storage Installation, Registration of Dry Spent Fuel Storage Cask AEP-NRC-2024-48, Response to Request for Additional Information (RAI) for License Amendment Request for One-Time Extension of Completion Time for Inoperable AC Source - Operating2024-07-0202 July 2024 Response to Request for Additional Information (RAI) for License Amendment Request for One-Time Extension of Completion Time for Inoperable AC Source - Operating ML24176A1012024-06-21021 June 2024 57143-EN 57143 - Paragon Energy Solutions - Update 1 (Final) - 10CFR Part 21 Final Notification: P21-05242024-FN, Rev. 0 AEP-NRC-2024-45, Report Per Technical Specification 5.6.6 for Inoperability of Post Accident Monitoring Neutron Flux Monitoring2024-06-13013 June 2024 Report Per Technical Specification 5.6.6 for Inoperability of Post Accident Monitoring Neutron Flux Monitoring ML24163A0132024-06-12012 June 2024 Request for Information for the NRC Age-Related Degradation Inspection: Inspection Report 05000315/2024012 and 05000316/2024012 AEP-NRC-2024-23, Core Operating Limits Report2024-05-23023 May 2024 Core Operating Limits Report ML24141A2162024-05-20020 May 2024 —Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection AEP-NRC-2024-30, Reactor Trip Due to Main Turbine Trip from a High-High Thrust Bearing Position Trip2024-05-20020 May 2024 Reactor Trip Due to Main Turbine Trip from a High-High Thrust Bearing Position Trip AEP-NRC-2024-40, Unit 2 - Supplement to License Amendment Request for One-Time Extension of Completion Time for Inoperable AC Source - Operating2024-05-16016 May 2024 Unit 2 - Supplement to License Amendment Request for One-Time Extension of Completion Time for Inoperable AC Source - Operating AEP-NRC-2024-41, Annual Radiological Environmental Operating Report2024-05-15015 May 2024 Annual Radiological Environmental Operating Report IR 05000315/20240012024-05-14014 May 2024 Integrated Inspection Report 05000315/2024001 and 05000316/2024001 AEP-NRC-2024-07, Unit 2 - Transmittal of Report of Changes to the Emergency Plan2024-05-14014 May 2024 Unit 2 - Transmittal of Report of Changes to the Emergency Plan IR 05000315/20244012024-05-14014 May 2024 – Security Baseline Inspection Report 05000315/2024401 and 05000316/2024401 AEP-NRC-2024-26, Transmittal of Donald C. Cook Nuclear Plant, Emergency Plan Revision 492024-05-14014 May 2024 Transmittal of Donald C. Cook Nuclear Plant, Emergency Plan Revision 49 ML24115A2152024-05-0707 May 2024 LTR: CNP Non-Acceptance with Opportunity TS 3-8-1 AEP-NRC-2024-24, Form OAR-1, Owners Activity Report2024-05-0707 May 2024 Form OAR-1, Owners Activity Report ML24256A1472024-05-0606 May 2024 DC Cook 2024 NRC Examination Submittal Letter: Submittal ML24116A0002024-05-0202 May 2024 – Regulatory Audit in Support of Review of the Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors AEP-NRC-2024-35, Response to NRC Regulatory Issue Summary 2024-01 Preparation and Scheduling of Operator Licensing Examinations2024-04-30030 April 2024 Response to NRC Regulatory Issue Summary 2024-01 Preparation and Scheduling of Operator Licensing Examinations AEP-NRC-2024-28, 2023 Annual Radioactive Effluent Release Report2024-04-29029 April 2024 2023 Annual Radioactive Effluent Release Report AEP-NRC-2024-31, Annual Report of Individual Monitoring2024-04-24024 April 2024 Annual Report of Individual Monitoring AEP-NRC-2024-02, Unit 2 License Amendment Request for One-Time Extension of Completion Time for Inoperable AC Source - Operating2024-04-0303 April 2024 Unit 2 License Amendment Request for One-Time Extension of Completion Time for Inoperable AC Source - Operating AEP-NRC-2024-29, (CNP) Unit 2 - Request for Relief Related to American Society of Mechanical Engineers (ASME) Code Case N-729-6 Supplemental Examination Requirements, ISIR-5-072024-04-0303 April 2024 (CNP) Unit 2 - Request for Relief Related to American Society of Mechanical Engineers (ASME) Code Case N-729-6 Supplemental Examination Requirements, ISIR-5-07 AEP-NRC-2024-19, Annual Report of Property Insurance2024-04-0101 April 2024 Annual Report of Property Insurance AEP-NRC-2024-04, License Amendment Request Regarding a Change to Unit 1 Technical Specification 3.4.12, Low Temperature Overpressure Protection (LTOP) System2024-03-0606 March 2024 License Amendment Request Regarding a Change to Unit 1 Technical Specification 3.4.12, Low Temperature Overpressure Protection (LTOP) System ML24073A2342024-03-0606 March 2024 Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors IR 05000315/20230062024-02-28028 February 2024 Annual Assessment Letter for Donald C. Cook Nuclear Plant, Units 1 and 2 (Report 05000315/2023006 and 05000316/2023006) 2024-09-09
[Table view] Category:Licensee Event Report (LER)
MONTHYEAR05000316/LER-2024-002, Manual Reactor Trip Following Rapid Downpower for Steam Leak2024-09-12012 September 2024 Manual Reactor Trip Following Rapid Downpower for Steam Leak 05000316/LER-2024-003, Plant Shutdown Required by Technical Specifications Due to Reactor Coolant System Identified Leakage2024-08-22022 August 2024 Plant Shutdown Required by Technical Specifications Due to Reactor Coolant System Identified Leakage AEP-NRC-2024-52, Manual Reactor Trip Following Rapid Downpower for Steam Leak2024-07-15015 July 2024 Manual Reactor Trip Following Rapid Downpower for Steam Leak AEP-NRC-2024-30, Reactor Trip Due to Main Turbine Trip from a High-High Thrust Bearing Position Trip2024-05-20020 May 2024 Reactor Trip Due to Main Turbine Trip from a High-High Thrust Bearing Position Trip 05000316/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 05000315/LER-1999-027, LER 315/99-027-00, Underrated Fuses Used in 250 Vdc System Could Result in Lack of Protective Coordination1999-11-29029 November 1999 LER 315/99-027-00, Underrated Fuses Used in 250 Vdc System Could Result in Lack of Protective Coordination ML18219E1521978-09-27027 September 1978 Submit Licensee Event Report Nos. RO 78-051/03L-0 & RO 78-052/03L-0 ML18219B5201978-09-27027 September 1978 09/27/1978 Letter Enclosure of Licensee Event Report 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 ML18219E1551978-09-0808 September 1978 Submit Licensee Event Report No. RO 78-048/03L-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) 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 ML18219E1581978-08-14014 August 1978 Submit Licensee Event Report Nos. RO 78-043/03L-1 & RO 78-044/03L-1 ML18219E1571978-08-14014 August 1978 Submit Licensee Event Report Nos. RO 78-045/03L-0 & RO 78-046/03L-0 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 ML18219B5781978-06-19019 June 1978 D.C. Cook - Submit Licensee Event Report RO 50-316/78-034/03L-0 for Unit 2 IR 05000316/19780341978-06-19019 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 2024-09-12
[Table view] |
Text
g4'g/0 Og REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)DISTRIBUTION FOR INCOMING MATERIAL 50-316 REC: KEPPLER J G NRC ORG: SHALLER D V IN Cc MI PWR DOCDATE: 09/12/78 DATE RCVD: 09/15/78 DOCTYPE: LETTER NOTARIZED:
NO COPIES RECEIVED
SUBJECT:
LTR 1 ENCL 1 FORWARDING LICENSEE EVENT REPT (RO 50-316/78-056)
ON 07/28/78 CONCERNING SURVEILLANCE TEST ON 2AB DIESEL-GENERATOR RESULTED IN AN OVERSPEED TRIP AS GENERATOR WAS UNLOADED...
TRIP CAUSED BY LINKAGE CAP SCREW BREAKING IN THE GOVERNOR LINKAGE...W/ATT LER 78"69-.PLANT NAME: COOK-UNIT 2 REVIEWER INI Tl AL: X JM ,DISTRIBUTOR INITIAL: QM'ISTRIBUTION OF THIS MATERIAL IS AS FOLLOWS 4++++++<<<+<<<<<++
NOTES: i.SEND 3 COP IE OF Al L MATERlAL TO ISE INCIDENT REPORTS (DISTRIBUTION CODE A002)FOR ACTION: BR CI'%RBel BC++W/4 ENCL INTERNAL: REG FILE+/ENCL ENCL I 8(C SYSTEMS BR++W/ENCL NOVAK/CHECK>kW/ENCL AD FOR ENGx+W/ENCL HANAUER>+W/ENCL AD FOR SYS 5 PROJ+4W/ENCL ENGINEERING BR<.<W/ENCL KREGER/J.COLLINS'~+A/ENCL K SEYFRIT/IE4+W/ENCL NRC PDR+4W/ENCL MIPC+4W/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/BUNCEI>4W/ENCL POWER SYS BR><W/ENCL EXTERNAL: LPDR S ST.JOSEPI'3i MI+<W/ENCL NS I C++W/ENCL ACRS CAT B>+W/16 ENCL DlSTRIBUTION:
LTR 44 ENCL 44 SI ZE: 1P iiP+2P CONTROL NBR: 780870 P9 THE END
~.A I 4 k 1 Il ih NEIL ORY DOCKET RLE COPY 1 pe DONALD'C.COOK NUCLEAR PLAilT P.O.Box 458, Bridgman, Michigan 49106 September 12, 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 I o>o~f+Pf1 cl R g-1g)S Operating License DPR-74 Docket No.50-316
Dear Mr.Keppler:
Pursuant to the requirements of the Appendix A Technical Specifications the following reports are submitted:
RO 78-056/03L-1 RO 78-061/03L-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.R.Walsh, Esq.G.Charnoff, Esq.J.M.Mennigan G.01 son PNSRC J.F.Sti etzel R.S.Keith T.P.Beilman/J.L.
Rischling Dir., IE (30 copies)Dir., MIPC (3 copies)78087030<
NRC FORM 266 I7 77)1~NUCLEAR REGULATORY COMMISSION"UPDATE ePORT-PREVIOUS REPORT DATE 8/El+88 LlCENSEE EVENT REPORT[OO~]7 8 CON'T~01 7 8 CONTROL BLOCK: I M I D C C 2 Q2 0 9 LICENSEE CODE 14 15 QI (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATIONI 6 0 0 0 0 0 0 0 0 OQ3 4 I i 1 iQ4~QE 25 26 LICENSE TYPE Jo 57 CAT 58 LICENSE NUMBER REPQRT~L~B 0 5 0 0 0 3 1 6 7 0 7 2 8 7 8 QB 9 1 2 7 8 Q SOURCE 60 61 DOCKET NUMBER 68 69 EVENT DATE 74 75 REPORT DATE 80 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES Q10~D3 AS THE DIESEL GENERATOR HAS UND4IADED THIS FEXCEEDED T S 3 8 1 1 P THE APPILICABZZ 4 ACTICN HEQUI HEMENI'S N83E FUZZILLED PHEVIOUS OCCURRENCES OF A SIMILAR NATUHE INCLUDE 050 315/78 Ol g 09 AND 77 42.~OB~OB 7 8 9 80~OS 7 8 SYSTEM CAUSE CAUSE CGA IP.VALVE CODE CODE SUBCODE COMPONENT CODE SUBCOOE SUBCOOE E Q>>~+Q12~8 Q13 G I N E Q14~ZQIB~Z Q16 9 10 11 12 13 18 19 20 SEQUENTIAL OCCURRENCE REPORT R EV IS I ON LERIRP EVENT YEAR REPORT NO.COOE TYPE NO.QTT REPORT~78+~05 6 Q~~0 21 22 23 24 26 27 28 29 30 31 32 ACTION FUTURE.EFFECT SHUTDOWN ATTACHMENT NPROA PRIME COMP.COMPONENT TAKEN ACTION ON PLANT METHOD HOURS Q22 SUBMITTED FORM SUB.SUPPLIER MANUFACTURER QIB~XQIB~~Q2O~~Q21 0 0 0 0~Y Q23~NQ24~~Q26 W 2 9 0 (DB 33 34 35 36 37 4O 41 42 43 44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS Q27 o INVESTIGATICN HEVEAUK)THAT THE OVEHSPEED TRIP WAS CAUSED BY A LINKAGE CAP SCHEN BHEAKING IN THE GOVEHNOR LINKAGE.AN EXAMINATION OF THE GOVERNOR LINKAGE FAILED TO RI:VF451L OIK&SIRENS OF NEAR.THE OTHER DIIDELS WERE ALSO INSPECTED.
THIS LINKAGE'AP SCHEW HAS REPLACED ON.EACH.A DESIGN CHANGE HAS BEEN INITIATED (HFC-12-1618) 80 DISCOVERY DESCRIPTION Q32 13 44 AMOUNT OF ACTIVITY Q LOCATION OF RELEASE Q 80 80 80 80 80 NRC USE ONLY o 2 80 o 0 0 68 69 PHONE.616 465 5901 Jack Rischlin NAME OF PREPARER 4 TO INSTALL OIIZIZ BUSHINGS ON THESE LEVERS.(SEE SUPPUMRZ 7 8 9 FACILITY~3P METHOD OF STATUS 56 POWER OTHER STATUS~DISCOVERY 5~Q26~~Q29 LaJQ" 7 8 9 10 12 45 46 ACTIVITY CONTENT RELEASED OF RELEASE EZ.hJ Q>>~Q>" 7 8 9 10 11 44 45 PERSONNEL EXPOSURES NUMBER TYPE DESCRIPTION QSB LOOOOJO>>Z Q>>7 8 9 11 12 13 PERSONNEL INJURIES NUMBER OESCRIPTIONQ41 B~~Q4O 7 8 9 11 12 LOSS OF OR DAMAGE TO FACILITY Q43 TYPE DESCRIPTION NA 7&9 10 PUBLICITY ISSUED DESCRIPTION
~KRI LmJe 8 9 IO SUPPLZt.~TO IZa.578-056/03L-1 CAUSE DESCRIPTION SUPPL1M2K UNTIL THIS RFC IS INS~D, THE MAINTENACE DEPARIHEÃZ WILL BE INSPECTING THE GOVERNOR LINKAGE ON THE DIESIS QUASH!PLY FOR SIGNS OF NEAR.
NPS FORA)I'366 I7-77).NUCLEAR REGULATORY COMMISSION LICENSEE EVENT REPORT~01 7 8 CON'T~O 7 8~O4 CONTROL BLOCK: QI IPLEASE PRINT OR TYPE ALL REQUIRED INFORMATION)
I 6 Q0 0 0 0 0 0 0 0 0 0 0Q4 LICENSEE CODE 14 15 LICENSE NUMBER 25 26 3 Q4~(g LICENSE TYPE JO 57 CAT 58 Qe ABOVE'P-ll, PRESSURIZER LEVEL INDICATICN CHANNIK III (NLP-153)WAS FOUND TO BE I SIGNIFICANTLY DIFFERENT FEGM THE CIXHER CHANNELS.THIS WAS NON~ERVATIVE IN RESPECT K)T.S.TABLE 3.3-3.ITEM 1.d.THE APPK)PRIATE ACTIONHEQUIREMENTS WERE REPOR~LQ 0 0 3 1 6Q0 8 Qs 0 9 1 2 60 61 DOCKETNUMBER 68 69 EVENT DATE 74 75 REPORT DATE 80 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES Q10 DURING A WORK ORDER REVIEW ON AUGUST 14 IT WAS DISCOVERED THAT WHILE IN HVZ STANDBY~OB FULI.ILLED.PREVIOUS OCCURRENCES INCXi3DE: 050-315/78-41, 10, 77-41 316 78-44 6.~O7~OB 7 8 80 44 SYSTEM CAUSE CAUSE COMP.VALVE CODE CODE'UBCODE COMPONENT CODE SUBCODE SUBCODE~oe R Q11.B 0>2~AQ>3 T N 6 T R 0 Q4~TQ>5~Z 016 7 8 9 10 11 12 13 18 19 20 SEQUENTIAL OCCURRENCE REPORT REVISION LERIRP EVENT YEAR REPORT NO.CODE TYPE'NO, Q7~>>0>>~78+~06 I QA~03+L-QO 21 22 23 24 26 27 28 29 30 31 32 ACTION, FUTURE EFFECT SHUTDOWN ATTACHMENT NPRDA PRIME COMP.COMPONENT TAKEN'ACTION ON PLANT METHOD HOURS Q22 SUBMITTED FORM SUB.SUPPLIER MANUFACTURER
~FQ16 LuQ>>~zQ2o HzQ2'mJQ23 mQ24 WQ26 Q" 33 34 35 36 37 40 41 42 43 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS Q27 I INVESTIGATION REVEALING)
THAT A GAS POCKE1'AS'IN,THE SENSING LINE.THE SENSING LINE WAS RI~LLIK)TO REMOVE THE GASES.UPCN RETURNING THE CHANNIK TO SERVICE ALL CHANNELS AGRIC.A,DESIGN CHANGE (12-1598)HAS BEEN NITIATED TO STUDY THE PIPING FOR'IHE SENSING LINES AND MKE GHE NECESSARY CHANGES.4 7 8 9 FACIUTY STATUS%POWER OTHER STATUS Q 5 D Q2II~00 0 Q29 NR'i7 6 9 10 12 13 44 ACTIVITY CONTENT RELEASED OF RELEASE AMOUNT OF ACTIVITY Q 6~z Q33 z Q34 NA 8 9 10 44 PERSONNEL EXPOSURES NUMBCR TYPE DESCRIPTION QSB~l7~00 0 0>>z 0%NR 7 8 9 11 12 13 PERSONNEL INJURIES NUMBER DESCRIPTIONQ41 ZZ~00 00 NA METHOD OF DISCOVERY DISCOVERY DESCRIPTION Q32~BQSI OPERATOR OBSERVATI 45 46 LOCATION OF RELEASE Q 45 80 80 80 80 7 8 9'I1 12 LOSS OF OR DAMAGE TO FACILITY Q43 TYPE DESCRIPTION
~IB~zQ42 7 8 9 10 PUBLICITY ISSUED DESCRIPTION
~4 HH LmrQ44 8 9 10 NAME OF PREPARER 68 69 PHONE'0 80 NRC USE ONLY 80 g 0