Similar Documents at Cook |
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Category:Letter
MONTHYEARAEP-NRC-2024-77, U2C28 Steam Generator Tube Inspection Report2024-10-21021 October 2024 U2C28 Steam Generator Tube Inspection Report AEP-NRC-2024-80, Independent Spent Fuel Storage Installation Registration of Dry Spent Fuel Storage Cask2024-10-15015 October 2024 Independent Spent Fuel Storage Installation Registration of Dry Spent Fuel Storage Cask AEP-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-2024-002-01, 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 ML24183A0162024-07-25025 July 2024 Review of Reactor Vessel Material Surveillance Program Capsule W Technical Report ML24169A2142024-07-25025 July 2024 Issuance of Amendment No. 362 Regarding Change to Technical Specification 3.4.12, Low Temperature Overpressure Protection System IR 05000315/20240022024-07-24024 July 2024 Integrated Inspection Report 05000315/2024002 and 05000316/2024002 05000316/LER-2024-002, Manual Reactor Trip Following Rapid Downpower for Steam Leak2024-07-15015 July 2024 Manual Reactor Trip Following Rapid Downpower for Steam Leak 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 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 ML24159A2522024-05-30030 May 2024 10 CFR 50.71(e) Update and Related Site Change Reports AEP-NRC-2024-23, Core Operating Limits Report2024-05-23023 May 2024 Core Operating Limits Report 05000316/LER-2024-001, 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 ML24141A2162024-05-20020 May 2024 —Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection 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 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 IR 05000315/20244012024-05-14014 May 2024 – Security Baseline Inspection Report 05000315/2024401 and 05000316/2024401 AEP-NRC-2024-24, Form OAR-1, Owners Activity Report2024-05-0707 May 2024 Form OAR-1, Owners Activity Report ML24115A2152024-05-0707 May 2024 LTR: CNP Non-Acceptance with Opportunity TS 3-8-1 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 2024-09-09
[Table view] Category:Licensee Event Report (LER)
MONTHYEAR05000316/LER-2024-002-01, 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 05000316/LER-2024-002, Manual Reactor Trip Following Rapid Downpower for Steam Leak2024-07-15015 July 2024 Manual Reactor Trip Following Rapid Downpower for Steam Leak 05000316/LER-2024-001, 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
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INDIANA & MICHIGANPDYYRR COMPANY DONALD C. COOK NUCLEAR PLANT g
P.O. Box 458, Bridgman, Michigan 49106 March 18, 1976
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(( VNR Mr. J.G. Keppler, Regio a Dip, Office of Inspection an fJfptcemenS i37PP United States Nuclear Re u'tory,,Commissio .
Region III 799 Roosevelt Road Glen Ellyn, IL 60137 Operating License DPR-58 Docket No. 50-315
Dear Mr. Keppler:
Pursuant to the requirements of Appendix A Technical Specifications and the United States Nuclear Regulatory Commission Regulatory Guide 1.16, Revision 3, Section 2.b, the following reports are submitted:
RO 50-315/76-08 RO 50-315/76-09 Sincerely, R.W. J gen n Plant anager
/bab cc: R.ST Hunter J.E. Dolan G.E. Lien R. Kilburn R.J. Vollen BPI R.C. Callen MPSC K.R. Baker RO: III P'.W. Steketee, Esquire RE Walsh, Esquire G. Charnoff, Esquire G. Olson J.M. Hennigan PNSRC 3080 R.S. Keith Dir., IE (30 copies)
Dir., MIPC (3 copies)
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CONTROL 8LOCK:
ICENSEE EVENT REPORT y
(PLEASE PRINT ALL REOUIRED INFQRlRATIDN) 6 UCENSEE i LICENSE EVENT NAME LICENSE NUiVIBEA TYPE M I 0 C C I 0 0 0 0 0 0 '0 0 0 A 1 TYPE.
1 I I ~0332
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7 89 .14 15 25 26 30 31 REPORT REPORT CATEGORY TYPE SOURCE OOCICET NUMBER EVENT DATE REPORT OATS Ioa~] cowv, ~L ~L 0 9 0 0 3 1 5 0 2 2 3 ? 6 0 3 1 8 7 6 7 8 57 '58 59 60 61 68 69 74 75 EVENT DESCRIPTION Qo2 WHILE IN titODE 1 AT 81 PERCENT POWER, THE 150 FOOT WIND SPEED AND THE 80 FOOT WIND 8 9 DIRECTION INDICATIONS FAILED. NO GASEOUS RELEASE WAS IN PROGRESS ~ INVESTIGATION QP3 80 ON 2/23/76 FOUND BOTH INSTRUMENTS ON'HE MICROWAVE TOWER ICED UP. THE'INSTRUMENTS 7 8 9 80 Qo5 WERE THAWED WITH A HEAT GUN AND RETURNED TO SERVICE.
7 8 9 80 7
m89 ( RO-50-315/76-08 )
80
~
PAME SYSTEM CAUSE COMPONENT COMPONENT CODE CODE " COMPONENT CODE SUPPUEA, MANUFACTURER VIOLATCN 7
[oOYI ~rp 8 9 10 c
11 12 I N s T R 0 17 0
43 44 x 9 9 9 47 48 CAUSE OESCRIPTION
~08 THE CAUSE OF THE INSTRUMENT FAILURE WAS A SLEET STORM WHICH CAUSE THE TRANSMITTERS TO 7 aS
~09 BECOME COVERED WITH 'ICE, 'RESTRICTING MOVEMENT 'OF MOVING PARTS.
7 89 80
.7 89 FACILITY ~
METHOD Of.
80 STATUS 99 POWER -
OTHc:A STATUS OISCOVEAY OISCOVERY DESCRIPTION Pi~]
~E ~08 1 .NA 44 B. ROUTINE SURVEILLANCE 80 7 8 9 10 12 13 45 46 Q~g 7 8 FORM OF ACTIVITY RELEAS'EO 9
~Z
. COATENT OF RELEASE
'0 Z 'A11
'MOUNT OF ACTIVITY 44 45 NA LOCATION OF RELEASE 80
,. PERSONNEL EXPOSURES NUMBER TYPE OESCAIPTION Pcs] ~00 0 ~Z NA 7 89 'l1 12 13 80 PERSONNEL INJURIES NUMBEA OESCRIPTION
~)4 89
~00 '
NA 80 7 11 12 PROBAHLTE CONSEQUENCES
~1 5 NONE -- GASEOUS RELEASES WERE'SUSPENDED AS REQUIRED.
7 89 80 LOSS OR OAMAGE TO FACILITY TYPE 'ESCRIPTION Q~g Z NA 7 89 10 80 PUBLICITY NA 7 89 80 AOOITIONAL FACTORS
[118] H [S [N PROORESS TO HEAT TRACE THE STATIONARY PORTION OF THE TRANSMITTERS TO 7 Bs So Q~B P ENT RECURRENCE OF THIS PROBLEM.
7 as 80 G. SWAN PHoNE. 616 465-5901 368)
GPO 88'I ~ 6 87
+1
<<)'pe~-4 IOENBEE EVENT REPORT CONTROL BLOCK: (PLEASE PRINT ALL REaVIREO WFORIVIAVION)
%5 LICENSEE LICENSE EVENT NAME UCENSE NUMBER TYPE TYPE
+01] I4 I 0 C C 1 0 0 0 0 0 0 0 0 0 4 1 1 1 1
~
7 89 14 15 25 26 30 31 32 REPORT REPORT CATEGORY TYPE SOURCE OOCKET NUMBER EVENT OATE AEPOAT OATE
[001I CON'5 0 5 0 0 3 1 5 0 2 2 5 7 6 0 3 1 8 7 6 7 8 57 58 59 60 61 68 69 74 75 80 EVENT DESCRIPTION 7
7 I
Qo2 7 8 9 89 QoO4]
8 9 WHILE IN MODE 1, AT 81 PERCENT POWER, THE 50 FOOT WIND DIRECTION SYSTEM AT THE BLESHOOTING PROCEDURES A NEW TRANSLATOR WAS RECEIVED FROM WEATHERMEASURE CORPORATION IDENTIFIED A FAILED TRANSLATOR.
3-1-76. THE SYSTEM 80 80 80
[oaf WAS CALIBRATED RETURNED TO SERVICE, AND DECLARED OPERABLE 3-3-76.
7 8 9 80
[oO~] R 3 5 6-09 7 8 9 PA95IE F
80
'SYSTEM CAUSE COMPONENT COMPONENT COBE COOE 'OMPONENT CODE SUPPUER MANUFACTURER
[005I ~IE E I 0 S Y R 0 0 X 9 9 9 ~Y 7 8 9 10 11 12 17 43 44 47 48 CAUSE DESCRIPTION Q~g CAUSE WAS FAILURE OF THE TRANSLATOR DUE TO NORI'lAL USAGE. CAUSE OF VIOLATION WAS 7 8 9 80 Qol FAILURE OF THE OH HAND SPARE TRANSLATOR TO BEOPERATIONALAT THE TIME OF THE SYSTEM 7 8 9 80
~10 FAI LURE.
7 89 OTHER STATUS OISCOVEAY OESCRIPTION ROUTINE SURVEILLANCE 7 8 9 10 12 13 44 45 46 80 FORM OF ACTIVITY COATENT RELEASEO OF RELEASE AMOUNT OF ACTIVITY LOCATION OF RELEASE Qig ~Z Z NA NA 7 8 9 10 11 44 45 80 PERSONNEL. EXPOSURES 7 89 11 12 13 Bo PERSONNEL INJURIES NUMBER OESCAIPTION
~l4 ~00 '0 NA 7 89 11 12 80 PROBABLE CONSEQUENCES Q1 g NOI'IE -- GASEOUS RELEASES WERE SUSPENDED AS REQUIRED.
7 89 80 LOSS OR DAMAGE TO FACILITY TYPE OESCRIPTION 7 8 9'02 PUBLICITY NA 80 NA 7 89 80 ADDITIONAL FACTORS Q18 THE TWO INOPERABLE TRANSLATORS HAVE BEEN RETURNED TO THE MANUFACTURER FOR REPAIRS 7 8 9 80
.Q~ 9 OR REPLACEMENT.
7 89 80 NAME: PHDNE (616)465 5901 (368)
GPO 881 667
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U.S. NUCLEAR REGULATORY COI 'SSION DOCKET NUMBER NRC FORM 195 (2-76) 50-FILE NUMBER gy NRC DISTRISUTION FaR PART 50 DOCKET MATERIAL INCIDENT REPORT TO FRDM: Indiana 8 Michigan Power DATE OF DOCUMENT J.G. Keppler Michigan Co.'ridgman, 3-R.W. Jurgensen DATE RECEIVED 3 26-76 OLETTER 0 NOTOR IZE D PROP INPUT FORM NUMBER OF COPIES RECEIVED I7IOR IG INAL SUN C LASS IF I E D QCOP Y DESCRIPTION ENCLOSV RE Ltr. trans the following....... RO¹~'76-08, on 2-23-76, Concerning Instrument Failure.......
RO¹ 76-09, on 2-25-76, Concerning Failure of Translator due to Normal Usage...... 'he (1 Cy. Received)
PLANT NAME: Cook ¹ 1 NOTE: IF PERSONNEL EXPOSURE IS INVOLVED SEND DIRECTLY TO KREGER/J. COLLINS SAFETY FOR ACTION/INFORMATION ENVIRO 76 BRANCH CHIEF: nie W 3 CYS FOR ACTION LIC ASST: e ice W/ CYS ACRS CYS HOLDING/ ENT TO LA INTERNAL D IST RI BUTION NRC PDR ICE 2 SCHROEDER/IPPOLITO O
NOVAK CjiECK R MES ~
B' TEDESCO MACCA E E BAER SHAO VOLLMER BUNCH KRE ER J COLL NS EXTERNAL DISTRIBUTION CONTROL NUMBER LpDR: . osep , ic an TIC NSIC 3090 NRC FORM 196 (2-76)
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