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] |
Text
DONALD C. COOK NUCLEAR PLANT P.O. Box 458, Bridgman, Michigan 49106 Ob August 18, 1978 f~
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Mr. J.G. Keppler, Regional Director A
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Office of Inspection and Enforcement tg United States Nuclear Regulatory Commission Region III CA 799 Roosevelt Road Glen El lyn, 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 78-052/03L-0 RO 78-053/03L-0 RO 78-054/03L-0 RO 78-055/03L-O.
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.
J.M. Kennigan G. Olson ] JG 911978 PNSRC J.F. Stietzel R.S. Keith T.P. Beilman/JUL. Rischling Dir., IE (30 copies)
Dir., MIPC (3 copies)
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NP)P FORhfiy6 ~S. NUCLEAR REGULATORY COMMISSION I7L7>
LlCENSEE EVENT REPORT CONTROL BLOCK: Q1 {PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION)
I 8 7 8 9 1 0 C C LICENSEE CODE 2
14 Q2 15 0 0 0 0 0 0 0 LICENSE NUMBER 0 0 0 0 Q34 26 1 1 LICENSE TYPE 1 1 30 ps~ps 57 CAT 58 CON'T
~ooff ioooos ~LL Qs 0 5 0 0 0 3 1 6 Q10 7 1 9 7 8 Qs0 8 1 8 7 8 Qs 8 68 69 EVENT DATE '74 75 REPORT DATE 6O 61 DOCKET NUMBER EVENT DESCRIPTION AND PROBABLE CONSEQUENCES Q10
~o2 UNIT IN NODE 1 CONDUCTING SCHEDULED SURVEILLANCE TESTS. RHR PUHP SUCTION VALVE IHO-320 CYCLE TIt'1E EXCEEDED tlAXIHUN STROKE TINE OF 2 MIN. IN VIOLATION OF APP. A 4 TECH SPEC CRITERIA ESTABLISH IN 4.0.5. THE VALVE ttAS RETESTED AND OPERATED AT THE NORMAL TItlE CYCLE DETERMINED FROt1 PREVIOUS TESTS. THIS IS FIRST OCCURRENCE OF THIS
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~os TYPE. THIS EVENT HAD NO EFFECT ON THE HEALTH AND SAFETY OF THE PUBLIC.
~OS 80 7 8 9 SYSTEM CAUSE CAUSE If COMP. VALVE.
CODE CODE SUBCODE COMPONENT CODE SUBCODE SUBCODE
~Os ~CF Q11 X Q12 ~Z Q13 V A L V E X Q14 ~Epis ~0 Qs 7 8 9 10 12 13 18 19 20 SEQUENTIAL OCCURRENCE REPORT REVISION EVENT YEAR REPORT NO. CODE TYPE NO.
Q12 LF RJRO osfoo2 ~78 21 22 Q
23
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~03 28 29 QL 30 Q
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[JO 32 ACTION FUTURE EF FECT SHUTDOWN ATTACHMENT NPRD4 PRIME COMP. COMPONENT TAKEN ACTION ON PLANT METHOD HOURS 022 SUBMITTED FORM SUB. SUPPLIER MANUFACTURER
~XQ13 ~X Qfs ~Z Q20 ~Z Q21 0 0 0 0 N Q23 ~N Q24 ~H Q23 Qs 33 34 35 36 37 40 41 42 43 44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS Q27 o Ilvt0-320 ltAS BEING TESTED PER ESTABLISH TEST PROCEDURE. THE REASOt< FOR EXCEEDING THE 1 TMO tlINUTE t1AXIHUt'1 LIMIT COULD NOT BE FOUND. RETEST VERIFIED VALVE CYCLED AT 2 PREVIOUSLY ESTABLISHED NORMAL TIt1E. CYCLING FRE(jUENCY ~JAS REDUCED TO ONCE PER MONTH FOR NEXT THREE MONTHS TO MONITOR CYCLItlG TI51E.
7 8 9 80 FACILITY STATUS 56 POWER OTHER STATUS Q METHOD OF DISCOVERY DISCOVERY DESCRIPTION Q32
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~BQ31 45 46 CONDUCTING SURVEILLANCE: TEST 80 7 8 ACTIVITY
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Q33 CONTENT RELEASED OF RELEASE
~ZQ34 10 PERSONNEL EXPOSURES 11
'A AMOUNT OF ACTIVITY ~
44 45 I'lA LOCATION OF RELEASE Q 80 NUMBER TYPE DESCRIPTION Q39
~00 0 QZpss NA 7 8 9 11 12 13 80 PERSONNEL INJURIES NUMBER DESCRIPTIONQ4 LOOOOJQ43 NA 7 8 9 11 12 80 LOSS OF OR DAMAGE TO FACILITY TYPE DESCRIPTION Q43 Z Q42 NA 7 8 9 10 80 KZ ISSUED PUBLICITY LHJQ44 DESCRIPTION ~ NRC USE ONLY is o
2 7 8 9 10 68 69 BO o 465-5901 0 NAME OF PREPARER R. S. Keith (616)
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I 6 N I 0 C C 2 Q20 0 0 0 0 0 0 0 0 0 0 Q24 1 1 1 1 QE~QR I
7 8 9 I.ICENSEE CODE 14 15 LICENSE NUMBER 25 26 LICENSE TYPE 30 57 CAT 58 CON'T 7 8 soUROE LUQB 60 61 0 5 0 0 0 POCKF'T NUMBER 3 1 6 68 Q 69 0 7 2 EVENT DATE 1 7 8 74 Q 75 0 8 1 REPORT DATE 8
80 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES ~10 DURING A PLAf'JNED UNIT SHUTDOlJN llITH TAE REACTOR IN OPERATIONAL MODE 2 THE AVERAGE COOLANT TEMP. DECREASED BELOW 541 QF TLJICE AND lJAS RECOVERED EACH TIffE. ONCE
'EACTOR 4 FOR A PERIOD OF 10 MIN. AND THE SECOND TIME FOR A PERIOD OF 9 MIN. THE I fINIMUM TEMP.
OF BOTH TRANSIENTS WAS 540.2 F. RECOVERY FROM EACH TRANSIENT lJAS WITHIN THE 15 MIN.
~o 6 ALLOWED BY TECH'PEC ~
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~OB 7 8 9 80 SYSTEM CAUSE CAUSE COMP. VALVE.
CODE CODE SUBCODE COMPONENT CODE SUBCODE SUBCODE
~ZZ A Q72 ~AQER Z Z Z Z Z Z Q74 ~ZQEE ~Z 7 8 9 10 QEE 11, 12,13 SEQUENTIAL OCCURRENCE 18 19 REPORT 20 QER REVISION
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Q17 REPQRT ~75 21 22 23
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ACTION FUTURE EFFECT SHUTDOWN ATTACHMENT NPRDP PRIME COMP. COMPONENT TAKEN ACTION ON PLANT METHOD HOURS O22 SUBMITTED FORM SUB. SUPPLIER MANUFACTURER L~JQER ~NQER ~ZQER ~ZQEE 0 0 0 TI N Q22 ~NQ24 ~ZQ25 Z 9 9 9 Q24 33 34 35 36 37 46 42 43 44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS &27 UNIT WAS UNLOADED FROM ~57K BY BORAQION TO STAY 'lJITHIN THE AXIAL FLUX TARGET BAND AND THEN HELD AT 4X FOR 53 HIN.'OR COOLING OF TURBINE METAL. CONTROL RODS klAD BEEN MAINTAINED TOO FAR OUT OF THE CORE TO COMPENSATE FOR THE XENON TRANSIENT ON POWER 3 REDUCTION.DURING FUTURE SHUTDOltNSCONTROL RODS W ILL BEDR I YEN FURTHER IN THE CORE 4 TO ASSURE REACTOR CONTROL 7,8 9 80 FACILITY STATUS
~00 95 POWER OTHER STATUS ~'AQEE
~3P METHOD OF DISCOVERY DISCOVERY DESCRIPTION EIG 7 8 LDJQ22 9 10 4
12 Qs 13 NA 44 45 46 OPERATIONAL OBSERVATION ANO RLARN 80 6
ACTIVITY CONTENT RELEASED OF RELEASE
~Z Q33 ~ZQ34 AMOUNT OF ACTIVITY NA
~ NA LOCATION OF RELEASE Q 7 8 9 IO, 44 45 80 PERSONNEL EXPOSURES NUMBER TYPE DESCRIPTION Q39
~l7 ~00 0 Q27 Z Qss NA 80 7 8 9 11 12 13 PERSONNEL INJURIES NUMBER DESCRIPTION 41
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NAME OF PREPARER R. S ~ LEASE PHONE. 61 6 465-5901 a
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7 8 9 M I D LICENSEE CODE C C 2Q20 14 15 LICENSE NUMBER 25 Q3 26 LICENSE TYPE 30 57 CAT 58 CON'T 5 3 6 Qs 0 8 1 8 7 8 QB
~O soURcE L~JQB O O O O 1 Q7
'75 7 8 60 61 DOCKET NUMBER 68 69 EVENT DATE 74 REPORT DATE EVENT DESCRIPTION AND PROBABLE CONSEQUENCES Q10 WITH THE REACTOR IN MODE 4 CONTAINMENT ISOLATION MANUAL VALVES DW211 AND
~O3 WERE OPENED IN VIOLATION OF TECH. SPEC. 3.6.1.1. THESE VALVES WERE OPENED TWO SEPARATE TIMES. REACTOR COOLANT SYSTEM TEMP. WAS 225'F AND PRES. OF 375 PSIG.
MAXIMUM OPEN TIME WAS 7 HOURS. TECH. SPEC. ACTION REQUIRES BEING IN MODE 3 WITHIN
~OB TOTAL OF 7 HOURS. UNIT WAS IN MODE 4 THROUGHOUT THIS EVENT.
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~OB 80 7 8 SYSTEM CAUSE CAUSE COMP., VALVE.
CODE CODE SUBCODE COMPONENT CODE SUBCODE SUBCODE
'OS ~ZZ Q>> A Q73 ~AQ>> Z Z Z Z Z Z Q4 ~ZQ78 ~Z Q78 7 8 '9 10 11 12 13 18 19 20 SEQUENTIAL OCCURRENCE REPORT REVISION Q77 LE+RP REPORT ACTION FUTURE EVENT YEAR
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~05 4 26 Q~
27
~03 28 ATTACHMENT CODE 29 NPRDA TYPE
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31 PRIME COMP.
NO.
32 0
COMPONENT TAKEN ACTION ON PLANT METHOD HOURS &22 SUBMITTED FORM SUB. SUPPLIER MANUFACTURER 33 Q1B ~Q 34
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~Q2 36 37
+
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+N 41 Q23 ~NQ24 42
~Z 43 Q25 44 Z 9 9 9 47 Q26 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS Q27 o THE VALVES WERE OPENED UNDER ADMINISTRATIVE CONTROL FOR DECON. 'LEANIN WIT T ASSUMPTION THAT THIS WAS ALLOWED BY TECH. SPEC. 'AS S AND THE PERSON HAS BEEN CORRECTED, "A~ETECH. SPEC..REVISION. WILL BE REQUESTED TO ALLOW OPENING OF THESE VALVES UNDER ADMINISTRATIVE CONTROL SO DECON. WATER NEED NOT BE 4 TRANSPORTED BY BUCKET.
8 9 80
~
7 FACILITY ~3P METHOD OF STATUS 55 POWER OTHER STATUS -
DISCOVERY DISCOVERY DESCRIPTION Q2 7
8 8 9 0 QEE ~00 10 0
12 QEE 13 NA 44
'aJQ31 45 46 80 ACTIVITY CONTENT RELEASED OF RELEASE Q33 gJQ34 AMOUNT OF ACTIVITY ~ NA LOCATION OF RELEASE Q 7 8 9 10 44 45 80 PERSONNEL EXPOSURES NUMBER TYPE DESCRIPTION Q39 7 ~00 Q37 Z Q38 NA 80 7 8 9 11 12 13 PERSONNEL INJURIES NUMBER DESCRIPTIONQ1 8 ~00 0 Q48 NA 7 8 9 11 12 80 LOSS OF OR DAMAGE TO FACILITY TYPE DESCRIPTION Q43 B Z 042 NA 7 8 9 10 80 PUBLICITY
~2o ISSUED
~Q<<NA DESCRIPTION Q NRC USE ONLY
8 9 ]0 68 69 80 48 0
NAMC OF PREPARER . ~ LEASE PHDNE, 61 6 465 5901 43
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I'RI FORM 496 ~. NUCLEAR REGULATORY COMMISSION L(CENSEE EVENT REPORT CONTROL BLOCK Ql {PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION)
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~0 7 8 9 DCC2Q200 LICENSEE CODE 14 15 0 0 0 0 LICENSE NUMBER 0 0 0 0 OQD 25 26 4 1 1 LICENSE TYPE 1 1Q4~QD 60 57 CAT 58 4
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~01 7 8 soUROE ~LOB 60
'0 61 5000 DOCKETNUMBER 3 16 68 07 69 0 7 2 EVENT DATE 6 7 8 74 Qs 75 0 8 1., 8~
REPORT DATE 7 8 80 QB EVENT DESCRIPTION AND PROBABLE CONSEQUENCES Q10 IT SHUT DOWN FOR SCHEDULED OUTAGE. A TEMPORARY CHANGE SHEET WRITTEN FOR
~03 20HP4030STP017 ON JULY~!7,1'1978 WAS NOT REVIEWED BY PNSRC AND APPROVED BY
~04 PLANT MANAGER WITHIN 14 DAYS IN VIOLATION OF APPENDIX A TECH SPEC 6.8.3.C.
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VIOLATION DISCOVERED BY OPER. SUPT. ON JULY 26, 1978 AND TEMPORARY CHANGE
~oe PRESENTED TO PNSRC AND APPROVED BY PLANT MANAGER JULY 27, 1978 IDENTICAL
~0 7 OCCURENCES REPORTED IN LER 50-316/78-02 AND 78-034/L. NO ADVERSE EFFECTS
~0 s .ON HEALTH AND SAFETY OF THE PUBLIC.
7 8 9 80 SYSTEM CAUSE CAUSE COMP. VALVE.
CODE CODE SUBCODE COMPONENT CODE SUBCODE SUBCODE 7 8
~ZZ 9 10 Qll 11 A Q12 ~BQ12 12 13 Z Z Z Z Z Z Q4 18
~ZQID 19
~Z 20 Qs SEQUENTIAL OCCURRENCE REPORT REVISION 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
~HQID ~Z Q19 ~Z Q29 ~Z Q2'I 0 0 0 0 ~N Q22 ~NQ24 ~Z Q25 Z 0 Q28 33 34 35 36 37 49 41 42 43 44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS Q27 o +F A GE OVER OF CLERICAL HELP IN .OPERATIONS DEPARTMENT RESULTED P E E TRAINING (IN METHOD"",'OF.
INSURE THEY ARE PRESENTED TO PNSRC AND PLANT MANAGER IN RE UIRED.TIME FRAME.
3 TEMPORARY EMPLOYEES REPLACED BY TWO PERMANENT EMPLOYEES AND REQUIRED TRAINING 4 OF NEW EMPLOYEES WAS CONDUCTED.
8 9 80 FACILITY METHOD OF STATUS % POWER OTHER STATUS Q30 DISCOVERY DISCOVERY DESCRIPTION Q32
~ls E Q28 ~09 7 Q29 NA ~AQ31 OPER. SUPT. RECORD REVIEW 8 9 10 12 13 44 45 46 80 ACTIVITY CONTENT
~ Q 7 8
~Z 9 '0 RELEASED OF RELEASE Q33 ~ZQ34 PERSONNEL EXPOSURES NUMBER TYPE NA AMOUNTOF ACTIVITY DESCRIPTION Q39 44 45 NA LOCATION OF RELEASE 80 7 '"
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0 11 Q~ZQ28 12 13 NA 80 PERSONNEL INJURIES 7 8
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NUMBER 11 Q4o DESCRIPTIONQ41 12 NA 80 LOSS OF OR DAMAGE TO FACILITY TYPE DESCRIPTION Q43 Z O. NA 7 8 9 10 80 O
ISSUED LNl044 PUBLICITY DESCRIPTION ~ NRC USE ONI.Y 94 45 2
I 8 9 10 BO o 0
NAME OF PREPARER R. S. KEITH 0
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