Similar Documents at Cook |
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Category:Letter
MONTHYEARIR 05000315/20230042024-01-31031 January 2024 Integrated Inspection Report 05000315/2023004 and 05000316/2023004 ML24004A1582024-01-19019 January 2024 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0039 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) AEP-NRC-2024-01, Emergency Plan Revision 482024-01-0808 January 2024 Emergency Plan Revision 48 AEP-NRC-2023-56, Report Per Technical Specification 5.6.6 for Inoperability of Unit 1 Post Accident Monitoring Reactor Coolant (Loop 3 Cold Leg) Wide Range Temperature Recorder Thermal Sensor2023-12-20020 December 2023 Report Per Technical Specification 5.6.6 for Inoperability of Unit 1 Post Accident Monitoring Reactor Coolant (Loop 3 Cold Leg) Wide Range Temperature Recorder Thermal Sensor ML23352A3502023-12-19019 December 2023 Dc. Cook Nuclear Power Plant, Units 1 Biennial Licensed Operator Requalification Program Inspection and Request for Information ML23338A2642023-12-0505 December 2023 Confirmation of Initial License Examination AEP-NRC-2023-45, Unit 2 - Schedular Exemption for Enhanced Weapons, Firearms, Background Checks, and Security Event Notifications Implementation2023-11-16016 November 2023 Unit 2 - Schedular Exemption for Enhanced Weapons, Firearms, Background Checks, and Security Event Notifications Implementation IR 05000315/20234042023-11-0606 November 2023 Cyber Security Inspection Report 05000315/2023404 and 05000316/2023404 ML23310A1152023-11-0606 November 2023 Notification of the NRC Baseline Inspection and Request for Information, Inspection Report 05000316/2024002 IR 05000315/20234032023-09-19019 September 2023 Security Baseline Inspection Report 05000315/2023403 and 05000316/2023403 IR 05000315/20230112023-08-31031 August 2023 Functional Engineering Inspection - Commercial Grade Dedication Report 05000315/2023011 and 05000316/2023011 ML23242A1832023-08-30030 August 2023 Notification of NRC Baseline Inspection and Request for Information; Inspection Report05000315/2023004 AEP-NRC-2023-40, Annual Report of Loss-of-Coolant Accident Evaluation Model Changes2023-08-29029 August 2023 Annual Report of Loss-of-Coolant Accident Evaluation Model Changes IR 05000315/20234022023-08-11011 August 2023 Security Baseline Inspection Report 05000315/2023402 and 05000316/2023402 AEP-NRC-2023-34, Supplement to Request for Approval of Change Regarding Neutron Flux Instrumentation2023-08-0202 August 2023 Supplement to Request for Approval of Change Regarding Neutron Flux Instrumentation IR 05000315/20230022023-07-24024 July 2023 Integrated Inspection Report 05000315/2023002 and 05000316/2023002 ML23178A2422023-06-28028 June 2023 Reassignment of the U.S. Nuclear Regulatory Commission Branch Chief in the Division of Operating Reactor Licensing for Plant Licensing Branch III IR 05000315/20230122023-06-22022 June 2023 Biennial Problem Identification and Resolution Inspection Report 05000315/2023012 and 05000316/2023012 IR 05000315/20235012023-06-21021 June 2023 Emergency Preparedness Biennial Exercise Inspection Report 05000315/2023501 and 05000316/2023501 AEP-NRC-2023-29, Core Operating Limits Report2023-06-19019 June 2023 Core Operating Limits Report ML23159A0192023-06-13013 June 2023 Information Meeting with a Question and Answer Session to Discuss NRC 2022 End-Of-Cycle Plant Performance Assessment of Donald C. Cook Nuclear Plant, Units 1 and 2 AEP-NRC-2023-32, Response to NRC Regulatory Issue Summary 2023-1 Preparation and Scheduling of Operator Licensing Examinations2023-06-0606 June 2023 Response to NRC Regulatory Issue Summary 2023-1 Preparation and Scheduling of Operator Licensing Examinations AEP-NRC-2023-33, Renewable Operating Permit2023-06-0505 June 2023 Renewable Operating Permit AEP-NRC-2023-30, Follow-Up Notification of Ph Non-Compliance for Turbine Room Sump2023-06-0101 June 2023 Follow-Up Notification of Ph Non-Compliance for Turbine Room Sump AEP-NRC-2023-27, Annual Radiological Environmental Operating Report2023-05-15015 May 2023 Annual Radiological Environmental Operating Report ML23131A3282023-05-11011 May 2023 D.C. Cook Information Request for the Cyber-Security Baseline Inspection, Notification to Perform Inspection 05000315/2023404 and 05000316/2023404 IR 05000315/20230012023-05-0303 May 2023 Integrated Inspection Report 05000315/2023001 and 05000316/2023001 AEP-NRC-2023-19, Annual Radioactive Effluent Release Report2023-04-30030 April 2023 Annual Radioactive Effluent Release Report ML23117A0062023-04-27027 April 2023 Review of the Spring 2022 Steam Generator Tube Inspections Report ML23114A1142023-04-25025 April 2023 Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection AEP-NRC-2023-23, Annual Report of Individual Monitoring for 20222023-04-24024 April 2023 Annual Report of Individual Monitoring for 2022 AEP-NRC-2023-24, Notification of Ph Non-Compliance for Turbine Room Sump2023-04-12012 April 2023 Notification of Ph Non-Compliance for Turbine Room Sump AEP-NRC-2023-20, Annual Report of Property Insurance2023-04-0303 April 2023 Annual Report of Property Insurance AEP-NRC-2023-15, Decommissioning Funding Status Report2023-03-28028 March 2023 Decommissioning Funding Status Report ML23076A0212023-03-20020 March 2023 Request for Information for NRC Commercial Grade Dedication Inspection; Inspection Report 05000315/2023011; 05000316/2023011 IR 05000315/20234012023-03-16016 March 2023 Security Baseline Inspection Report 05000315/2023401 and 05000316/2023401 ML23066A1882023-03-0707 March 2023 Information Request to Support Upcoming Problem Identification and Resolution (Pi&R) Inspection at Donald C. Cook Nuclear Plant IR 05000315/20220062023-03-0101 March 2023 Annual Assessment Letter for Donald C. Cook Nuclear Plant, Units 1 and 2 (Report 05000315/2022006 and 05000316/2022006) IR 05000315/20220042023-02-0101 February 2023 Integrated Inspection Report 05000315/2022004 and 05000316/2022004 and Exercise of Enforcement Discretion AEP-NRC-2023-11, Form OAR-1, Owner'S Activity Report2023-01-31031 January 2023 Form OAR-1, Owner'S Activity Report IR 05000315/20230102023-01-31031 January 2023 Phase 4 Post-Approval License Renewal Inspection Report 05000315/2023010 and 05000316/2023010 AEP-NRC-2023-02, Request for Approval of Change Regarding Neutron Flux Instrumentation2023-01-26026 January 2023 Request for Approval of Change Regarding Neutron Flux Instrumentation ML22363A5622023-01-0404 January 2023 Relief Request ISIR-5-06 Related to ASME Code Case N-729-6 Supplemental Examination Requirements of Reactor Vessel Closure Head Penetration Nozzles AEP-NRC-2022-66, Report Per Technical Specification 5.6.6 for Inoperability of Unit 2 Post Accident Monitoring Neutron Flux Monitoring2022-12-15015 December 2022 Report Per Technical Specification 5.6.6 for Inoperability of Unit 2 Post Accident Monitoring Neutron Flux Monitoring AEP-NRC-2022-46, Notification of Deviation from Electric Power Research Institute (EPRI) Materials Reliability Program 2019-008, Interim Guidance for NEI 03-08 Needed Requirements for Us PWR Plants for Management of Thermal Fatigue in2022-12-12012 December 2022 Notification of Deviation from Electric Power Research Institute (EPRI) Materials Reliability Program 2019-008, Interim Guidance for NEI 03-08 Needed Requirements for Us PWR Plants for Management of Thermal Fatigue in ML22340A1392022-11-30030 November 2022 Submittal of Revision 31 to Updated Final Safety Analysis Report and 10CFR50.71(e) Updated and Related Site Change Reports IR 05000315/20220112022-11-0404 November 2022 Design Basis Assurance Inspection (Teams) Inspection Report 05000315/2022011 and 05000316/2022011 IR 05000315/20220032022-10-28028 October 2022 Integrated Inspection Report 05000315/2022003 and 05000316/2022003 AEP-NRC-2022-58, U1C31 Steam Generator Tube Inspection Report2022-10-24024 October 2022 U1C31 Steam Generator Tube Inspection Report AEP-NRC-2022-61, Request for Relief Related to American Society of Mechanical Engineers (ASME) Code Case N-729-6 Supplemental Examination Requirements, ISIR-5-062022-10-24024 October 2022 Request for Relief Related to American Society of Mechanical Engineers (ASME) Code Case N-729-6 Supplemental Examination Requirements, ISIR-5-06 2024-01-08
[Table view] Category:Licensee Event Report (LER)
MONTHYEAR05000316/LER-2017-0012017-05-19019 May 2017 1 OF 5, LER 17-001-00 for Cook, Unit 2 re Containment Hydrogen Skimmer Ventilation Fan #1 Inoperable Longer than Allowed by Technical Specifications 05000316/LER-2016-0022017-02-0909 February 2017 Emergency Diesel Generators Declared Inoperable Due to a Manufacturing Design Issue, LER 16-002-00 for Donald C. Cook Nuclear Plant Unit 2 Regarding Emergency Diesel Generators Declared Inoperable Due to a Manufacturing Design Issue 05000316/LER-2016-0012016-08-31031 August 2016 Manual Reactor Trip Due To Moisture Separator Heater Expansion Joint Failure, LER 16-001-00 for Donald C. Cook Nuclear Plant, Unit 2 Regarding Manual Reactor Trip Due To Moisture Separator Heater Expansion Joint Failure ML16193A3902016-07-15015 July 2016 Donald C. Cook Nuclear Plant Unit 2 - A Loss of Main Condenser Event Occurred Due to a Storm-Induced Debris Damage of the Circulating Water System Pumps in the Forebay (LER-316-2014-003-00) 05000315/LER-2015-0022016-01-18018 January 2016 -Technical Specification Violation due to Inoperable Residual. Heat Removal Pump, LER 15-002-01 for D.C. Cook, Unit 1, Regarding Technical Specification Violation Due to Inoperable Residual Heat Removal Pump 05000316/LER-2015-0012016-01-15015 January 2016 Manual Reactor Trip Due To A Secondary Plant Transient, LER 15-001-01 for D.C. Cook, Unit 2, Regarding Manual Reactor Trip Due to a Secondary Plant Transient ML0528703602005-10-0505 October 2005 Special Report for D. C. Cook Unit 2 Re Unit 2 Reactor Coolant Inventory Tracking System ML0508903452005-03-22022 March 2005 LER 99-001-01 Donald C. Cook Nuclear Plant Unit 2, Regarding Supplemental LER for Degraded Component Cooling Water Flow to Containment Main Steam Line Penetrations ML0210601432002-04-12012 April 2002 LER 02-02-00, Donald C. Cook Nuclear Plant Unit 2, Technical Specification 3.9.4.c Was Violated During Core Alteration ML0209205342002-03-15015 March 2002 LER 99-012-01 for Cook Nuclear Plant, Unit 1 Re Auxiliary Building ESF Ventilation System May Not Be Capable of Maintaining ESF Room Temperature Post-Accident ML9936300511999-12-20020 December 1999 LER 99-S004-00, Intentionally Falsifying Documentation Results in Unauthorized Unescorted Access, on 11/18/99. with Letter Dated 12/20/99 ML9934002411999-11-29029 November 1999 LER 315/99-027-00, Underrated Fuses Used in 250 Vdc System Could Result in Lack of Protective Coordination ML18219B5201978-09-27027 September 1978 09/27/1978 Letter Enclosure of Licensee Event Report ML18219E1521978-09-27027 September 1978 Submit Licensee Event Report Nos. RO 78-051/03L-0 & RO 78-052/03L-0 ML18219B5211978-09-19019 September 1978 09/19/1978 Letter Enclosure of Licensee Event Report ML18219E1531978-09-18018 September 1978 Submit Licensee Event Report No. RO 78-050/03L-0 ML18219B5541978-09-18018 September 1978 Letter from Indiana & Michigan Power Co to NRC Submitting Licensee Event Report (RO 78-062/03L-0) ML18219B5551978-09-12012 September 1978 Letter from Indiana & Michigan Power Co to NRC Submitting Licensee Event Reports (RO 78-56/03L-1 and RO 78-061/03L-0) ML18219E1541978-09-12012 September 1978 Submit Licensee Event Report No. RO 78-049/03L-0 ML18219B5561978-09-0808 September 1978 Letter from Indiana & Michigan Power Co to NRC Submitting Licensee Event Reports (RO 78-059/03L-1 and RO 78-060/03L-0) ML18219E1551978-09-0808 September 1978 Submit Licensee Event Report No. RO 78-048/03L-0 ML18219B5571978-09-0505 September 1978 Letter from Indiana & Michigan Power Co to NRC Submitting License Event Report RO 78-059/03L-0 ML18219B5581978-08-30030 August 1978 Letter from Indiana & Michigan Power Co to NRC Submitting Licensee Event Report RO 78-058/03L-0 ML18219B5621978-08-22022 August 1978 Letter from Indiana & Michigan Power Co to NRC Submitting Licensee Event Reports (RO 78-056/03L-0 and RO 78-057/03L-0) ML18219B5611978-08-18018 August 1978 Letter from Indiana & Michigan Power Co to NRC Submitting Licensee Event Reports (RO 78-052/03L-0, RO 78-053/03L-0, RO 78-054-03L-0 and RO 78-055/03L-0) ML18219E1561978-08-15015 August 1978 Submit Licensee Event Report No. RO 78-047/03L-0 ML18219E1571978-08-14014 August 1978 Submit Licensee Event Report Nos. RO 78-045/03L-0 & RO 78-046/03L-0 ML18219E1581978-08-14014 August 1978 Submit Licensee Event Report Nos. RO 78-043/03L-1 & RO 78-044/03L-1 ML18219E1601978-08-11011 August 1978 Submit Licensee Event Report Nos. 1978-043-03L & 1978-044-03L ML18219B5641978-08-10010 August 1978 Letter from Indiana & Michigan Power Co to NRC Submitting Licensee Event Report (RO 78-051/03L-0) ML18219B5651978-08-0909 August 1978 Letter from Indiana & Michigan Power Co to NRC Submitting Licensee Event Report (RO 78-049/03L-1) ML18219B5661978-08-0808 August 1978 Letter from Indiana & Michigan Power Co to NRC Submitting Licensee Event Report (RO 78-050/03L-0) ML18219B5671978-08-0404 August 1978 Letter from Indiana & Michigan Power Co to NRC Submitting Licensee Event Report (RO 78-049/03L-0) ML18219B5681978-08-0202 August 1978 Letter from Indiana & Michigan Power Co to NRC Submitting Licensee Event Reports (RO 78-029/03L-1 and RO 78-048/03L-0) ML18219B5691978-07-21021 July 1978 Letter from Indiana & Michigan Power Co to NRC Submitting Licensee Event Reports (RO 78-019/03L-1 and RO 78-023/03L-1) ML18219B5701978-07-18018 July 1978 Letter from Indiana & Michigan Power Co to NRC Submitting Licensee Event Report (RO 78-047/03L-0) ML18219B5711978-07-11011 July 1978 Letter from Indiana & Michigan Power Co to NRC Submitting Licensee Event Report (RO 78-043/03L-0), Submitted Late Due to a Paper Defect ML18219B5721978-07-11011 July 1978 Letter from Indiana & Michigan Power Co to NRC Submitting Licensee Event Reports (RO 78-034/03L-1, RO 78-044/03L-0, RO 78-045/03L-0, RO 78-046/03L-0) ML18219B5731978-07-0505 July 1978 Letter from Indiana & Michigan Power Co to NRC Submitting Licensee Event Report (RO 78-042/03L-0) ML18219B5751978-06-29029 June 1978 Letter from Indiana & Michigan Power Co to NRC Submitting Licensee Event Report (RO 50-316/78-037), Stating Corrective Actions Taken IR 05000316/19780371978-06-29029 June 1978 Letter from Indiana & Michigan Power Co to NRC Submitting Licensee Event Report (RO 50-316/78-037), Stating Corrective Actions Taken ML18219B5771978-06-22022 June 1978 D.C. Cook - Submit Licensee Event Report RO 78-036/03L-0 for Unit 2 ML18219B5761978-06-21021 June 1978 Letter from Indiana & Michigan Power Co to NRC Submitting Licensee Event Report (RO 78-035/03L-0), a Resubmittal of LER 78-034/03L-0 Dated 6/19/1978 IR 05000316/19780341978-06-19019 June 1978 D.C. Cook - Submit Licensee Event Report RO 50-316/78-034/03L-0 for Unit 2 ML18219B5781978-06-19019 June 1978 D.C. Cook - Submit Licensee Event Report RO 50-316/78-034/03L-0 for Unit 2 ML18219B5221978-06-0606 June 1978 06/06/1978 Letter Licensee Event Report ML18219B5741978-06-0303 June 1978 Letter from Indiana & Michigan Power Co to NRC Submitting Licensee Event Reports (RO 78-038/03L-0, RO 78-039/03L-0, RO 78-040/03L-0, RO 78-041/03L-0) ML18219B5241978-06-0202 June 1978 06/02/1978 Letter Licensee Event Report ML18219B5231978-06-0202 June 1978 06/02/1978 Letter Licensee Event Report ML18219B5251978-05-25025 May 1978 05/25/1978 Letter Licensee Event Report 2017-05-19
[Table view] |
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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LlCENSEE EVENT REPORT CONTROL BLOCK: Q1 {PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION)
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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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CODE CODE SUBCODE COMPONENT CODE SUBCODE SUBCODE
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~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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2 7 8 9 10 68 69 BO o 465-5901 0 NAME OF PREPARER R. S. Keith (616)
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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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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
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'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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~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
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DISCOVERY DISCOVERY DESCRIPTION Q2 7
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NAMC OF PREPARER . ~ LEASE PHDNE, 61 6 465 5901 43
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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
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~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
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NAME OF PREPARER R. S. KEITH 0
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