Similar Documents at Cook |
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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] |
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REGULATORY INFORMATION DISTRIBUTIQN SYSTEM (RIDS)
DISTRIBUTION FOR INCOMING MATERIAL 50-316 REC: KEPPLER J G ORG: SHALLER D V DQCDATE: 07/21/78 NRC IN 5 MI PWR DATE RCVD: 07/26/78 DQCTYPE: LETTER NOTARIZED: NO COPIES RECEIVED
SUBJECT:
LTR 1 ENCL 1 FORWARDING LICENSEE EVENT REPT (RO 50-316/78-019) ON 04/04/78 CONCERNING DURING NORMAL OPERATIONS ACCUMULATOR 0 is 2 AND 3 WERE FILLED... SAMPLING SURVEILLANCE REQUIREMENTS OF TECH SPEC 4. 5. 1 WERE NOT MET WITHIN THE 6 HOUR TIME LIMIT... W/ATT LER 78-023.
REVIEWER INITIAL: X JM DISTRIBUTOR INITIAL: ~
<<'<<<<<<<<+<<<<<<<<<<<<<<<<<<+<<DISTRIBUTION GF THIS MATERIAL IS AS FOLLOWS <<<<<<<<<<<<<<<<<<<<<<%<<<<<<<<<<<<
NOTES:
- l. SEND 3 COPIES OF ALL MATERIAL TO IhE ED REEVFS-1 CY ALL MATERIAL INCIDENT REPORTS (DISTRIBUTION CODE A002)
FGR ACTION: B~U ORBSi BC<<<<W/4 ENCL INTERNAL: REG FILk<<<<W NCL NRC PDR<<<<W/ENCL
-NCL MIPC<<<<W/3 ENCL I 5 C SYSTEMS BR<<<<W/ENCL EMERGENCY PLAN BR<<<<M/ENCL NOVAK/CHECK<<<<W/ENCL EEB<<<<W/ENCL AD FOR ENG<<<<W/ENCL PLANT SYSTEMS BR<<<<M/ENCL HANAUER<<<<W/ENCL AD FOR PLANT SYSTEMS<<<<W/ENCL AD FOR SYS 8( PROJ<<<<W/ENCL REACTOR SAFETY BR<<<<W/ENCL ENGINEERING BR<<<<W/ENCL VOLLMER/BUNCH<<+W/ENCL KREGER/J. COLLINS<<<<M/ENCL POWER SYS BR<<<<W/ENCL K SEYFR IT/IE<<<<W/ENCL EXTERNAL: LPDR'8 ST. JOSEPH'I <<<<W/ENCL TICI LIZ CARTER<<<<W/ENCL NSI C<<<<W/ENCL ACRS CAT B<<<<W/16 ENCL DISTRIBUTION: LTR 45 ENCL 45 CONTROL NBR: 7820101 3 SI ZE: iP+1 P+2P THE END g
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Op C ericen yzpp INDIANA &'I/IICIIIGANPDNER COII/IPANY DONALD C. COOK NUCLEAR PLANT P.O. Box 458, Bridgman, Michigan 49106 July 21, 1978 rcpt tg LFI
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";,","~c> C,.'M Ql Mr. J.G. Keppler, Regional Director Office of Inspection and Enforcement V7 CD United States Nuclear Regulatory Coranission Region III 799 Roosevel t Road Glen Ellyn, IL 60137 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 78-019/03L-1 RO 78-023/03L-1.
Sincerely, D.V. Shaller Plant Manager
/bab cc: J.E. Dolan R.W. Jurgensen R.F. Kroeger R. Ki lburn 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. Hennigan PNSRC J.F. Stietzel JUL 8 I 1S78 R.S. Keith Dir., IE (30 copies)
Dir., IE (3 copies)
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NRC FORM 366 (7.77) "UPDATE REP T - PREVIOUS REPORT DATE 5/3/78 EVENT REPORT 'ICENSEE CONTROL BLOCK:
I 6 0
'1 (PLEASE PRINT OR TYPE ALI. REQUIRED INFORMATION)
~0 M I D C C 2 Q20 0 0 0 0 0'0 0 0 0 0Q34 1 1.1 1QE~QE 7 8 9 LICENSEE CODE 14 15 LICENSE NUMBER 25 26 LICENSE TYPE 30 57 CAT 58 CON'T
~01 7 8 RE'QRT
~LQB 0 60 61 5 0 0 0 DPCKET NVMBFR 3 1 6 68 QO 69 4 0 4 EVENT DATE 7 8 74 Qs0 75 7 2 1 REPORT DATE 7 8 80 Q
EVENT DESCRIPTION AND PROBABLE CONSEQUENCES ~10 DURING NORIIAL OPERATION, ACCUMULATOR7 1, 2 AND 3 WERE FILLED. THE SAflPLING
~03 SURVEILLANCE REQUIREI'lENTS OF T. S. 4.5.1. b WERE NOT MET WITHIN THE 6 HOUR TIME
~04 LIMIT. ON APRIL 5, 1978 IT WAS REALIZED THAT THE ACCUMULATOR SAMPLES WERE MISSED,
~OS THESE WERE OBTAINED AND ANALYZED AT THAT TIME:
~07
~os 80 7 8 SYSTEM CAUSE CAUSE COMP VALVE ~
CODE CODE SUBCODE COMPONENT CODE SUBCODE SVBCODE 9
~SF Q>> A QT2 ~XQTR Z Z Z Z Z Z Q14 ~ZQTE ~Z 20 QT.
7 8 10 11 12 13 18 19 QTT LERIRP REPoRT ACTION FUTURE TAKEN ACTION EVENT YEAR L278J 21 22 EFFECT ON PLANT Q
23 SHUTDOWN METHOD
~01 24 SEQUENTIAL REPORT NO.
9 26 HOURS O22 U~
27 M
OCCURRENCE 28 ATTACHMENT SUBMITTED CODE 29 NPRDQ FORM SUB.
REPORT TYPE UL 30 PRIME COMP.
SUPPLIER U U 31 REVISION NO.
32 COMPONENT MANUFACTURER
~ZGR ~ZQER ~ZQET 0 0 0 ~NQ33 ~NQ34 2 QEE Z 9 9 9 Qss QTR 33 34 35 36 37 40 41 42 43 44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS Q27 3 INVESTIGATION REVEALED THAT THE CHEMICAL LAB HAD BEEN NOTIFIED. A CHEMICAL SUPERVISOR HAD ASSIGNED THE SAMPLING TO AN INDIVIDUAL. DUE TO TIME PROBLEMS THE SAMPLE WAS NOT OBTAINED AND WAS NOT RE-ASSIGNED BY THE SUPERVISOR. TO PREVENT RECURRENCE, ALL 3
CHEMICAL PERSONNEL WERE RETRAINED IN THE ACCUMULATOR SAMPLING REQUIREMENTS.
~14 7,8 9 80 FACILITY STATUS 99 POWER OTHER STATUS Q 'ZQRT
~30 METHOD OF DISCOVERY DISCOVERY DESCRIPTION Q32 E Q>> ~03 0 Qs NA NA 7 8 9 10 12 13 44 45 46 80 ACTIVITY Z Q33 CONTENT RELEASED OF RELEASE
~ZQ34 AMOUNT OF ACTIVITY NA
~ NA LOCATION OF RELEASE Q3 7 8 9 10 11 44 45 80 PERSONNEL EXPOSURES NUMBER TYPE DESCRIPTION Q39 7 ~00 0 Q ZQss NA 80 7 8 9 11 12 13 PERSONNEL INJURIES NUMBER DESCRIPTIONQ41
[ll~] ~00 7 8 9 0
11 Q40 12 NA 80 LOSS OF OR DAMAGE TO FACILITY TYPE DESCRIPTION Q43 9 Z Q42 NA
'7 8 9 10 80 PUBLICITY O
ISSUED
~ZQ44 DESCRIPTION Q NA NRC USE ONI Y OE O
7 8 9 10 68 69 80 Ts JaCk RiSChling 1 6 465 5901 0 NAME OF PREPARER PHDNE6
P 7'RC FORM 366 (7-74> 7
' "UPDATE~PORT - PREVIOUS REPORT DATE 5/~8" 3
LICENSEE EVENT REPORT CONTROL BLOCK: Q1 (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION) 7 8 9 N I 0 LICENSEE CODE 0
I 0 2 14 000 15 o o '
6 LICENSE NUMBER
' ' Q' 25 26 LICENSE TYPE 30 Q~S 57 CAT 58 CON'T o 0 0 0 3 1 6 Q70 4 0 8 7 8QBO 7 2 ] 7 8 7 8
~Q6 60 61 DOCKET NUMBER 68 69 EVENT DATE 74 75 REPORT DATE 80 Qg EVENT DESCRIPTION AND PROBABLE CONSEQUENCES +10 DURING STARTUP AND POWER ASCENSION PROGRAM THE STEAM PRESSURE BISTABLES, PB-51 6A, 526A, 536A and 546A ( LOlJ PRESSURE-STEAN LINE ISOLATION) WERE NOT
~p4 FUNCTIONALLY TESTED PER T.S. TABLE 4. 3-2 P4. e.
~OS
~ps
~O7
~OB 80 7 8 9 SYSTEM CAUSE CAUSE COMP. VALVE ~
CODE CODE SUBCODE COMPONENT CODE SUBCODE SUBCODE
~OB 7 8
~IB 9 10 Q11 11 A Q>> ~CQ>>
12 13 I N 3 T R 0 18 Q4 ~Q>>
19.
~ZQ16 20 SEQUENTIAL OCCURRENCE REPORT. REVISION Q>>
LERIRp
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ACTION FUTURE EVENT YEAR
~78 21 22 EFFECT
+
23 SHUTDOWN
~02 24 REPORT NO.
3 26 Qa 27
~03 28 ATTACHMENT CODE 29 NPRDQ
+L 30 TYPE PRIME COMP.
[J 31 Ql NO.
32 COMPONENT TAKEN ACTION ON PLANT ~
METHOD HOURS +22 SUBMITTED FORM SUB. SUPPLIER MANUFACTURER
~GQ18 ~ZQ19 ~~Q20 ~~8 0 0 0 II I Q23 ~~Q24 ~NQ26 W I 2 Q26 33 34 4 35 36 37 40 41 42 43 44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS Q27 o DESIGN CHANGE l'JAS COMPLETED REMOVING THESE BISTA 1
IV., AND INSTALLING THEM IN SETS I AND II. TEMP ADDING THESE BISTABLES TO THE APPROPRI'AT
E. PROCEDURE
S. 'THESE TEMPORARY CHANGE SHEETS WERE 3 I SPLACE0 AND NOT PLACED I NTO EFFECT ~ CONSEQUENTLY, THE B I STABLES WERE NOT FUN CT I ON-LLY TESTED IN FEBRUARY AND MARCH (SEE ATTACHED SUPPLEMENT) 7 8 9 80 1, FACILITY STATUS GQ ~UA0 Q
% POWER OTHERSTATUS "A
~
~3p METHOD OF DISCOVERY LJQ" DISCOVERY DESCRIPTION Q32 ROUTINE REVIEW 7 8 9 10 12 13 44 45 46 80 ACTIVITY CONTENT RELEASED OF RELEASE Q33 Z Q34 AMOUNTQF ACTIVITY NA
~ NA LOCATION OF RELEASE Q 7 8 9 10 II 44 45 80 PERSONNEL EXPOSURES NUMBER TYPE DESCRIPTION Q39 7 ~00 0 Q37 Z Q38 NA 7 8 9 11 12 13 80 PERSONNEL INJURIES .
7 8 9 11 12 80 LOSS OF OR DAMAGE TO FACILITY ~43
'g-g TYPE z Q42 DESCRIPTION NA 80 7 8 9 10 PUBLICITY ISSUED DESCRIPTION Q NRC USE ONLY 07
'~2O 7 8
~ZO 9 10 N
68 69 80 O
49 0
NAME DF PREPARFR Jack ischl in 616-465-5901 a
I tq
ATTACHMENT TO LICENSEE EVENT REPORT g 7B O~3/O3L I Cause Description E
THESE HAVE BEEN ADDED TO THE APPROPRIATE PROCEDURES AND i
FUNCTIONALLY TESTED. TO PREVENT,. RECURRENCE, ADMINISTRATIVE CONTROLS HAVE BEEN ESTABLISHED TO INSURE TEMPORARY CHANGES ARE APPROVED AND INCORPORATED INTO THE APPLICABLE PROCEDURES.