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
4'REGULATORY DJ.STBj:9UTI ON FOR REC: KEPPLER J G NRC DOCDATE: 06/30/78 DATE RCVD: 07/06/78 I/FORMAT'I'ON'ISTRIBUTION SYSTEM (RIDS')'INCOMING'ATERI'AL
., 50-316'I ORG: SHALLER D V IN 5 MI PWR DOCTYPE: LETTER NOTARIZED:
NG COPIES RECEIVED
SUBJECT:
LTR 1 ENCL 1 FORWARDING LICENSEE EVENT REPT (RO 50-316/78-038)
ON 06/07/7S CONCERNING DURING SURVEILLANCE TEST ON CD PLANT BATTERY.CELL 589 WAS FOUND TO HAVE 8 ECIFIC GRAVITY BELOW 1200 MINIMUM SPECI-IC GRAVITY ALLOWED BY TECH SPECS...Wf ATT LERS78-039'8-040 AND 7g 0+<PLANT NAME: COOK-UNIT 2 REVIEWER INITIAL: X JM DISTRIBUTOR INITIAL:~lt Il<<+<~<<<<<H'<<~HH~<<DISTRIBUTION OF THIS MATFRIAL IS AS FOLLOWS NOTES: SEND 3 COPIES OF ALL MATERIAL TO IS.E ED REEVES-1 CY ALL I'IATERIAL INCIDENT REPORTS (DISTRIBUTION CODE A002)FOR ACTION: INTERNAL: EXTERNAL: BR CHI-LWRN2'C54W/4 ENCL EG..~W/ENCL E+4~W/2 ENCL 8.C SYSTEMS BR4l+W/ENCL NOVAK/CHECK+4FW/
ENCL AD FOR ENG4twM/ENCL HANAUER~~~W/ENCL AD FOR SYS 5 PROJ<<W/ENCL ENGINEERING BR4F4W/ENCL KREGER/J.COLLINSQ+M/ENCL K SEYFRI T/IE~~~~W/ENCL LPDR S ST.JOSEPH'I<<W/ENCL TIC~~~W/ENCL NS I C~~~W/ENCL ACRS CAT B~F+W/16 ENCL NRC PDR<<W/ENCL MIPC<<W/3 ENCL EMERGENCY PLAN BR<<M/ENCL EEB<<I Jf ENCL PLANT SYSTEMS BR<<W/ENCL AD FGR PLANT SYSTEMS+<M/ENCL REACTOR SAFETY BR<<W/ENCL VOLLMER/BUNCH<<W/ENCL POWER SYS BR<<M/ENCL DISTRIBUTION:
LTR 45 S I ZE: 1P+1 P+3P ENCL 45 CONTROL NBR: 781870119<<%0HM 4%%8M<<%9M 4%%%%%0$<<%084%0E%HF0F<<THE FND MASTER ROSTER PUBLICATIONS ISION I----D ISTRIBUT ION CODES 1 LE I------DISTR ABUT ION QTY.Y ST ZIP I----DISTR IBUT ION CODES 18-I-----D I STR.I BUT ION CODES 35-I------DISTR I BUT ION QTY 35-8 17-~17-----I 3~----I RD OF SUPERVISGRS LR IRNOMAN SAN DIEGO CO BD SUP 1'4 DIEGO CA 92101 BRARI AN N D I EGO 1 CA 92101 N DIEGO CA 92101 SN SR SF SE SM SO ST SA SG NB NU 1 1 CL EAR PHARMAC I ST N DIEGO CA 92103 SF SE SM SP ST SO SA SG 1 1 1 1 1 1 1 1 N D IEGO CA 92108 J OLLA CA 9203 7 SN SF SE SM ST SG CH 1 AN DIEGO SN SR SF SE ST SG 1 1 1 1,1 1 CA 92110 AN DIEGO CA 92110 1 1 1 1 1 1 1 li AN DIEGO iM CA 92112 SN SR SF SE SM SP ST SO SA SG CM
~Xi er4oen 7'O'NDIANA
&MICHIGAN POWER COMPANY DONALD C.COOK NUCLEAR PLANT P.O.Box 458, Bridgman, Michigan 49106 June 30, 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 V7 r;j 1~C"3~>cv~7 Kl C/7 c 7 7 f f'7 C"7 Cr~'f'7.4 C iC9 7"7 Cl7 C77 C.M CD CD 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 78-038/03L-0 RO 78-039/03L-0 RO 78-040/03L-0 RO 78-041/03L-O.
Sincerely, D.VS 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.G.Olson J.M.Kennigan PNSRC J.F.Stietzel R.S.Keith Dir., IE (30 copies)Dir., MIPC (3 copies)JUL 03 1978 Y.
LP ll U.S.NUCLEAR REGULATORY COMMISSION Qi (PLEASE PRINT OR TYPE ALL REOUIRED INFORMATION) 6 0-0 0 0 0-p 0 Qs 4 1 1 1 1 QE~QE 25 26 LICENSE TYPE 30 57 CAT 58 LICENSE NUMBER NRC FORM 366 (7.77)LICE NT REPORT CONTROL BLOCK: I[os)M I D D C 2 Q2 0 7 8 9 LICENSEE CODE 14 15 CON'T~o1"'~LQB 0 5'0 0 0 3 1 6 Q7 0 6 0" 7 8 QB 0 6 3 0 7 8 ee 7 8 60 61 DOCKET NUMBER 68 69 EVENT DATE 74 75 REPORT DATE 80 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES Q10 During survei 11 ance test on CD Plant Battery, cel 1)I 89 was found to have a~O3~O4~OS~OB~O7~OB 7 8 specif ic gravi ty of 1~195 whi ch is below the 1~200 minimum speci f ic gravity allowed per T.S.4.8.2.3.2a, 2, which.-constituted an inoperable battery.AB battery was operable.DC loads were shifted to AB battery for a period of 1 6 mi nutes whi-1 e cell 889 was jumpered.CD battery was returned to service a f ter being inoperable for 80 minutes.This event had no,effect upon public health and safety.80~og i s being developed to attempt to restore the cell.Also, a repl acement cell has SYSTEM CAUSE CAUSE COMP.VALVE CODE CODE SUBCODE COMPONENT CODE SUBCODE SUBCODE~EC Q>>E Q LAJQ73 8 A.T T R Y 8 LZJQEE L2J Q 7 8 9 10 11 12 13 18 19 20 SEQUENTIAL OCCURRENCE REPORT REVISION LF R(RO EVENT YEAR REPORT NO.CODE TYPE NO.Q17 REPoRT~78 U L0038 I L~J LLJ UL Q 0 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 LXJQER LCJQ>>LZJQ23 LZJQ>>O O O O~NQ23~YQ24~AQEE E 3 5 5 Q23 33 34 35 36 37 40 41 42 43 44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS Q27 The exact cause of the 1 ow speci f i c ravi t could not be determi ned~A rocedure 3 been ordered incase restorati on is not possible.Remaining cel 1 s in CD battery show no similar problems~OTHER STATUS QBO NA METHOD OF DISCOVERY~BQ31 NA 46 44 45 NA 45 44 NAMF oF PREPARER Dave Wizner 4 7 8 9 FACILITY STATUS~%POWER~BQ23~pg p Qs 7 8 9 10 12 13 ACTIVITY CONTENT RELEASED OF RELEASE AMOUNT OF ACTIVITY Q~Z Q33 Z Q34 NA 7 8 9 10 11 PERSONNEL EXPOSURES NUMBER TYPE DESCRIPTION Q39 Q37 MZQ33 NA 7 8 9 11 12 13 PERSONNEL INJURIES 7 8 9 11 12 LOSS OF OR DAMAGE TO FACILITY 43 TYPE DESCRIPTION g Z Q42 NA 7 8 9 10 PUBLICITY ISSUED DESCRIPTION Q~Ze NA 7 8 9 10 DISCOVERY DESCRIPTION Q32 80 LOCATION OF RELEASE Q 80 80 ((ygg5'.80 80 NRC USE ONLY 80 o 2 68 69 BOP g PHONE
NRC FORM 366 U.S.NUCI.EAR REGULATORY COMMISSION 1, LICENSEE EVENT REPORT CONTROL BLOCK: QI{PLEASE PRINT OR TYPE ALL.REQUIRED INFORMATION)
I 6~oi N I 0 C C ZJOO 0-0 0 0 0 0 0 DQ 1 1 1 1Q~00 , 7 8 9 LICENSEE'ODE 14 15 LICENSE NUMBER 25 26 LICENSE TYPE 30 57 CAT 58 CON'T~01 soosos LUQs 0 5 0 0 0 3 1 6 Q 0 6 1 5 7 8 Qs0 6 3 0 7 8 Q 60 61 DOCKET NUMBER 68 69 EVENT DATE 74 75 REPORT DATE 80 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES Q10 During survei 1 1 ance test on AB Pl ant Battery, cell 835 was found to have a~O3~p4~OS~ps~O7', specificJgravity of 1.197 which is below the 1.200 minimum specific gravity allowed per T.S.4.8.2.3.2a, 2 which constituted an inoperable battery.CD battery was operable.DC loads were shifted to CD battery for a period of 13 minutes while cell 7II35 was jumpered.AB battery was returned to service after being inoperable for 29 minutes.This event had no effect on:publ.ic I health and safety.Reference similar LER No.78-038/03L-O.
~08 80 7 8 9 4 7 8 SYSTEM CAUSE CAUSE COMP.VALVE CODE CODE SUBCODE COMPONENT CODE SUBCODE SUBCODE~OS C Q11~ZQ12~AQ13 8 A T T 8 Y Q4~ZQ15~Z Qs 9 10 11 12 13 18 19 20 SEQUENTIAL OCCURRENCE REPORT REVISION LF R(RO EVENT YEAR REPORT NO.CODE TYPE NO.Q>>ssso>>[zan++~03 9+w~03~L-0 21 22 23 24 26 27 28 29 30 31 32 ACTION FUTURE EFFECT SHUTDOWN ATTACHMENT NPRDR PRIME COMP.COMPONENT TAKEN ACTION ON PLANT METHOD HOURS Q22 SUBMITTED FORM SUB.SUPPLIER MANUFACTURER Q15~CQ13~ZQ25~ZQ>>0 0 0 0~NQ23~YQ24 A Q25 5 3 5 5 Qss 33 34 35 36 37 40 41 42 43 44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS Q27 p The exact cause of the low s ecific ravit could not be determined.
A procedure is being developed to attempt to restore the cell.Also, a replacement cell has been ordered in case restoration is not possible.Remaining cells in 3 AB battery show no similar problems.OTHER STATUS QSO NA NAME OF PREPARER 4 7 8 9 FACILITY STATUS 51 POWER 5~8 Q25~05 0 Q25 7 8 9 10 , 12 13 ACTIVITY CONTENT RELEASED OF RELEASE AMOUNT OF ACTIVITY Q 6~Z Q33~ZQ34 NA 7 8 9 10 PERSONNEL EXPOSURES NUMBER TYPE DESCRIPTION Q39~00 0 Q31 Z Qss 7 8 9 11 12 13 PERSONNEL INJURIES NUMBER DESCRIPTION Q41~15~OO O Q45 NA 7 8 9 11 12 LOSS OF OR DAMAGE TO FACILITY 43 TYPE DESCRIPTION z Q4.NA 8 9 10 PUBLICITY ISSUED DESCRIPTION Q~2O~ZQ4 NA 8 9 10 METHOD OF DISCOVERY~BQ" NA 44 45 46 NA 45 44 DISCOVERY DESCRIPTION Q32 LOCATION OF RELEASE Q 80 80 80 80 80 NRC USE ONLY 80 PHONE 2 68 69 80~45 616 465 5901 3 EXT 4 398 NRC FORM 366 U.S.NUCLEAR REGULATORY COMMISSION
{7.77).LtCENSEE EVENT REPORT CONTROL BLOCK: Ql (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION)
I 6[os)[D C C 2 Q o o o 0 0 0 0 0 o Q 4 I I I QE~QE 8 9 LICENSEE CODE 14 15 LICENSE NUMBER 25 26 LICENSE T)[PE 30 57 CAT 58 CON'T ULQE 0 6 0 0 0 3 1 6Q70 6 0 3 7 8QE 0 6 3 0 7 8 7 8 60 61 DOCKET NUMBER 68 69 EVENT DATE 74 75 REPORT DATE 5 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES Q10~O2 AFTER THREE REACTOR TRI'PS ON JUNE 3 9 13 1978 ROD BOTTOM POSI'TIO INDICATION
~O3~O4 FOR CONTROL ROD H-8 DID NOT INDICATE THAT H-8 WAS FULLY INSERTED.THE ACTION RE(UIREMENT OF T.S.3.1.1.1 WAS FULFILLED BY EMERGENCY BORATING FOR 5 MINUTES.~O6~O7~OB 80 7'9 SYSTEM CAUSE CAUSE CODE CODE SUBCODE 0 Q UxQ UxQ 9 10 11 12 13 SEQUENTIAL LF RIRP EVENT YEAR REPORT NO.Q17 REPoRT I778J U~04 0 21 22 23 24 ACTION FUTURE EFFECT SHUTDOWN TAKEN ACTION ONPLANT-METHOD HOURS Ql!I Ux Qlg Uz Q20 Uz Q21 0 0 0 33 34'5 36 37 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS Q27 o NA COMPONENT CODE 7.8 COMP.VALVE.SUBCODE SUBCODE Q14 U[Q15~Z Q16 18 19 20 OCCURRENCE REPORT REVISION CODE TYPE NO.U~M>UL-laJ 27 28 29 30 31 32 Q ATTACHMENT NPRDQ PRIME COMP.COMPONENT 22 SUBMITTED FORM SUB.SUPPLIER MANUFACTURER 0 N Q23~Q24 L[LI Q25 I I I 2 0 Q25 40 41 42 43 44 47 3 4 7 8 9 FACILITY~3P METHOD OF STATUS 39 POWER OTHER STATUS~=DISCOVERY 5 UD Q25~OG 0 Q29 NA L[LJ Q31 7*8 9 10 12 13 44 45 46 ACTIVITY CONTENT~RELEASED OF RELEASE AMOUNT OF ACTIVITY~QQQ~Z Q3 Z Q3 NA 7 8 9 10 11 44 45 PERSONNEL EXPOSURES NUMBER TYPE DESCRIPTION Q39 7~<<0 Q37 2 Q35 NA 7 8 9'1 12 13 PERSONNEL INJURIES NUMBER DESCRIPTION Q[ii~j~00 0 Q49 NA 7 8 9 511 12 LOSS OF OR DAMAGE TO FACILITY Q43~IB~<Q42 NA 7 8 9 10 PUBLICITY ISSUED DESCRIPTION Q o~NQ44 N 7 8 9 10 NAME OF PREPARER JaCk RlsChlln I 80 LOCATION OF RELEASE Q 80 80 80 80 PHONE: 68 69 80 NRC USE ONLY 44 o 80 o 0 DISCOVERY DESCRIPTION Q32 I'RC FORM 366 I7.77),, LICENSEE EVENT REPORT 7 8 CON'T 7 8~O3~O4~OS CONTROL BLOCK: QI 1 6 M I D C C 2 Q2 0 0 0 0 0 0 0 0 0 0 Q34 9 LICENSEE CODE 14 15 LICENSE NUMBER 25 26 (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION) 1 1 1 1 Q4~QE LICENSE TYPE 30 57 CAT 58 S IMILAR NATURE INCLUDE: RO-050/316-78-31,22,08,07'.~,'RO-050/315-78-.07,04.
77-34,33,28,27,76-54,44,13.
"'""'LJQBO 5 0 0 0 3 I 6 Q70 6 0 2 7 8 QB 0 6 3 0 7 8'0 61 DOCKET NUMBER 68 69 EVENT DATE 74 75 REPORT DATE 80 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES Q10 DURING NORMAL OPERATION, ROD POSITION INDICATION FOR CONTRO D-MEF1 THE+12 STEP LIMIT OF T.S.3.1.3.2.PREVIOUS OCCURRENCES OF A~O6~O7~Os 80 7 8 9 SYSTEM CAUSE CAUSE COMP.VALVE.CODE CODE SUBCODE COMPONENT CODE SUBCODE SUBCODE~IE Qll E Q12~ZQ13 I N 5 T R 0 Q4~IQ19~Z QTE 7 8 9 10 11 12 13 18 19 20 SEQUENTIAL OCCURRENCE REPORT LF R IRO EVENT YEAR REPORT NO.CODE TYPE Q11 REPORT[77J~O<I~~~OS 21 22 23 24 26 27 28 29 30 31 ACTION FUTURE EFFECT SHUTDOWN ATTACHMENT NPRDR PRIME COMP.TAKEN ACTION ON PLANT METHOD HOURS Q22 SUBMITTED FORM SUB.SUPPLIER~EQTE~Z QEE~Z Q20~Z Q 0 0 0~N Q23 LE)Q24 IJL)QEE 33 34 35 36 37 40 41 42 43 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS Q27~1O INVESTIGATION REVEALED THAT THE SIGNAL CONDITIONING MODULE OUTPUT VOLTAG REVISION+o COMPONENT MANUFACTURER 47 44 AFTER THE ROD'S SECONDARY COIL VOLTAGE WAS MEASURED TO VERIFY THA QE 3 THE CORRECT POSITION, THE SIGNAL CONDITIONING MODULE WAS RECALIBRATED AND PLACED BACK IN SERVICE RETURNING RPI TO WITHIN THE 12 STEP LIMIT 4 NA 7,8 9 FACILITY~3PMf THDD OF STATUS%POWER OTHER STATUS~<<DISCOVERY DISCOVERY DESCRIPTION Q32~lE~E Q29~06 5 Q29 NA~AQ31 OPERATOR OBSERVATION 7 8 9 10 12 13 44 45 46 ACTIVITY CONTENT RELEASED OF RELEASE AMOUNT OF ACTIVITY~LOCATION OF RELEASE Q Q33 Z Q34 NA 7 8 9 10 11 44 45 PERSONNEI.
EXPOSURES NUMBER TYPE DESCRIPTION Q39 1~00 0 QET Z Q39 NA 7 8 9 11 12 13 PERSONNEL INJURIES NUMBER DESCRIPTION 41 9~00 0 Q49 QIIA 80 80 80 80 7 8 7 8 O 9 11 12 LOSS OF OR DAMAGE TO FACILITY Q43 TYPE DESCRIPTION Z Q4, NA.9 10 PUBLICITY ISSUED DESCRIPTION~
LNJQ4" 7 8 9 10 Jack Risch]ing NAME OF PREPARER 80 68 69 616-465-5901 80 NRC USE ONLY 44 O 80 g 0