Similar Documents at Cook |
---|
Category:Letter
MONTHYEAR05000316/LER-2024-004, AB Emergency Diesel Generator Inoperable for Longer than Allowed by Technical Specifications2024-11-11011 November 2024 AB Emergency Diesel Generator Inoperable for Longer than Allowed by Technical Specifications IR 05000315/20240032024-10-31031 October 2024 Integrated Inspection Report 05000315/2024003 05000316/2024003 07200072/2024001 and Exercise of Enforcement Discretion AEP-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-2024-76, 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 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 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 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 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 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 ML24141A2162024-05-20020 May 2024 —Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection 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 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 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 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-2024-24, 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 2024-09-09
[Table view] Category:Licensee Event Report (LER)
MONTHYEAR05000316/LER-2024-004, AB Emergency Diesel Generator Inoperable for Longer than Allowed by Technical Specifications2024-11-11011 November 2024 AB Emergency Diesel Generator Inoperable for Longer than Allowed by Technical Specifications 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 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 05000315/LER-2023-002, Failure of Unit 1 West Auxiliary Feedwater Pump to Restart During Load Sequencer Testing2023-12-12012 December 2023 Failure of Unit 1 West Auxiliary Feedwater Pump to Restart During Load Sequencer Testing 05000315/LER-2023-001, Two Trains of Fuel Handling Area Exhaust Ventilation Inoperable2023-09-28028 September 2023 Two Trains of Fuel Handling Area Exhaust Ventilation Inoperable 05000315/LER-2022-003-01, Automatic Trip on Losss of Flow Due to Reactor Coolant Pump Trip2023-02-22022 February 2023 Automatic Trip on Losss of Flow Due to Reactor Coolant Pump Trip 05000316/LER-2022-001, Automatic Reactor Trip Due to Steam Generator High-High Level2023-01-0404 January 2023 Automatic Reactor Trip Due to Steam Generator High-High Level 05000315/LER-2022-003, Automatic Reactor Trip on Loss of Flow Due to Reactor Coolant Pump Trip2022-10-19019 October 2022 Automatic Reactor Trip on Loss of Flow Due to Reactor Coolant Pump Trip 05000315/LER-2022-002, Ice Condenser Door Inoperable Resulting in a Condition Prohibited by Technical Specifications2022-09-20020 September 2022 Ice Condenser Door Inoperable Resulting in a Condition Prohibited by Technical Specifications 05000315/LER-2022-001, Manual Reactor Trio Following Manual Turbine Trio Due to High Vibrations on Main Turbine2022-07-21021 July 2022 Manual Reactor Trio Following Manual Turbine Trio Due to High Vibrations on Main Turbine 05000316/LER-2021-002, Re Manual Reactor Trip Due to an Unisolable Steam Leak2021-08-18018 August 2021 Re Manual Reactor Trip Due to an Unisolable Steam Leak 05000315/LER-2021-001, Main Steam Safety Valve Setpoints Found Outside Technical Specifications Limits2021-06-10010 June 2021 Main Steam Safety Valve Setpoints Found Outside Technical Specifications Limits 05000316/LER-2020-004-01, Regarding Unit 2 Automatic Reactor Trip on Low-Low 24 Steam Generator Water Level2021-02-25025 February 2021 Regarding Unit 2 Automatic Reactor Trip on Low-Low 24 Steam Generator Water Level 05000316/LER-2020-004, Automatic Reactor Trip on Low-Low 24 Steam Generator Water Level2020-12-0909 December 2020 Automatic Reactor Trip on Low-Low 24 Steam Generator Water Level 05000315/LER-2020-001, Containment Closure Requirements Not Met During Refueling Operations2020-12-0909 December 2020 Containment Closure Requirements Not Met During Refueling Operations 05000316/LER-2020-003, Manual Reactor Trip and Automatic Safety Injection Due to Failed Open Pressurizer Spray Valve2020-11-0202 November 2020 Manual Reactor Trip and Automatic Safety Injection Due to Failed Open Pressurizer Spray Valve 05000316/LER-2020-002, Plant Shutdown Required by Technical Specifications Due to Reactor Coolant System Leakage2020-06-25025 June 2020 Plant Shutdown Required by Technical Specifications Due to Reactor Coolant System Leakage 05000316/LER-2020-001, Failure of Source Range Nuclear Instrumentation Resulting in a Condition Prohibited by Technical Specifications2020-01-0909 January 2020 Failure of Source Range Nuclear Instrumentation Resulting in a Condition Prohibited by Technical Specifications 05000315/LER-2019-002, Condition Prohibited by Technical Specification Due to an Inoperable Steam Generator Stop Valve Dump Valve2019-11-26026 November 2019 Condition Prohibited by Technical Specification Due to an Inoperable Steam Generator Stop Valve Dump Valve 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) ML18219E1541978-09-12012 September 1978 Submit Licensee Event Report No. RO 78-049/03L-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) 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 2024-09-12
[Table view] |
Text
REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)
DISTRIBUTION FOR INCOMING MATERIAL 50-315 REC: KEPPLER J G ORG: SHALLER D V DOCDATE: 02/06/78 NRC IN 5 MI PWR DATE RCVD: 02/10/78 DOCTYPE: LETTER NOTARIZED: NO COPIES RECEIVED
SUBJECT:
LTR 0 ENCL 1 LICENSEE EVENT REPT (RO 50-315/78-05) ON 01/16/78 CONCERNING NO 2 BORIC ACID TRANSFER PUMP DISCHARGE PRESSURE WAS 4 PSIG LOWER THAN MINIMUM REQUIRED'UE TO LEAKING MECHANICAL SHAFT SEAL.
PLANT NAME: COOK UNIT REVIEWER INITIAL: X JM DISTRIBUTOR INITIAL:
w++ww++++++4+++++ DISTRIBUTION OF THIS MATERIAL IS AS FOLLOWS INCIDENT REPORTS (DISTRIBUTION CODE A002)
FOR ACTION: BRANCH=-CH'I'EF=B S++W/4 ENCL INTERNAL: REG FILE4+W/EN NRC PDR44W/ENCL
- 8. E+'>W72 ENC MIPC++W/3 ENCL SCHROEDER/I PPOL I TO++M/ENCL HOUSTON44W/ENCL NOVAK/CHECK++W/ENCL GR IMES++W/ENCL KNIGHT@4 W/ENCL BUTLER++W/ENCL HANAUER++W/ENCL TEDESCO++W/ENCL EISENHUT4+W/ENCL BAER+4W/ENCL SHAO++W/ENCL VOLLMER/BUNCH++W/ENCL KREGER/J. COLLINS44W/ENCL ROSA44W/ENCL L. CROCKER++W/ENCL K SEYFRIT/IE4+W/ENCL EXTERNAL: LPDR'S ST. JOSEPH) MI4+W/ENCL T I C++W/ENCL NSIC4+W/ENCL ACRS CAT B++W/16 ENCL COPIES NOT SUBifITTED PER REGULATORY GUIDE 10.1 DISTRIBUTION: LTR 46 ENCL 46 CONTROL NBR: 780410038 SIZE: iP+1P THE END
I a ~
I't
~ a k
.-it1a r
t' I H.'a r l 4 r I
'I I
~, I ~ I" 4 ~ II a I
I I
aa P
t 'kkka ( I r a a ~ - l ti" I ~ I r' tt ra a t I4 r II II H ~ It
l P merlcsn D iV ICH f'omma DONALD C. COOK NUCLEAR PLANT C~ofa ~~
P.O. Box 458, Bridgman, Michigan 49106 i'
'"+ +<o++4 ~
February 6, 1978 Mr. J.G. Keppler, Regional Director e Office of Inspection and Enforcement 8 United States Nuclear Regulatory Commission Region III 799 Roosevelt Road Glen Ellyn, IL 60137 Operating Li cense DPR-58 Docket No. 50-315
Dear Mr. Keppl er:
Pursuant to the requirements of Appendix A Technical Specifications and the United States Nuclear Regulatory Cormission Regulatory Guide 1.16, Revision 4, Section 2.b, the following report is submitted:
RO 50-315/78-05.
Sincerely, D.V. Shaller Plant Manager
/bab cc: J.E. Dolan R.W. Jurgensen G.E. Lien R. Kilburn R.J. Vollen BPI R.C. Callen MPSC K.R. Baker RO:III P.W. Steketee, Esq.
R. Walsh, Esq.
G. Charnoff, Esq.
G. Olson PNSRC 78OP$ 0038 J.F. Stietzel Dir., IE (30 copies)
Dir., MIPC (3 copies)
]Bog, s N/I
l V
J
Farm No. 4494 LICENSEE EVENT REPORT 14 'ONTROL BLOCK: (PLEASE PAINT ALL AEOUIAEO IMFOAMATION) 1 6 LICENSEE LLCENSE EVENT NAME LICENSE NUMBER TYPC TYPF K1 N I D C C 1 0 0 0 0 0 0 0 0 0 4 1 1 1 1 ~03
~
7 89 14 15 85 30 31 38 REPORT REPORT CATEGORY TYPE SOURCE OOCKET NUMBER EVENI OATF AI PORT OAII
[OD1]rosrt L L 0 5 0 0 3 1 5 0 1 1 5 7 8 7 8 57 58 59 80 81 88 69 74 75 00 EVENT DESCRIPTiON joOa] Durin surveillance test k'2 Boric Acid Transfer Pum dischar e ressure was 4 si 7 8 9 80
[0D3] lower than the minimum re uired. The pump mechanical seal was leaking and was re-7 89 80
[ouai L placed. The um was retested satisfactorily. The dl pump was operable. This con-7 8 9 80
[oOs] dition did not re resent a substantial safety hazard. (RO 50-315/78-05) 7 8 9 80 Jog 7 6 9 PRM E 80 SYSTEM CAUSE COMPONENT COMPONENT
~or 7 8 9 COBE Lppi 10
~
COOE 11 18 P
COMPONENT COOE 0 M P X X 17 SUPPUER L~I 43 44 G
MANUFACTURER 2 0 0 47 VN3IATCN N
48 CAUSE DESCRIPTION
[oaf The cause of the low dischar e ressure was a leakin mechanical shaft seal. The 7 8 9 80
[ouei L seal failure was attributed to normal wear.
7 8 9 80 Qo]
7 89 FACAII Y METHOO OF 80 STAIIIS POWER OTHER STATUS OISCOVERY DISCOVERY OESCRIPTION 7 8 9 5 ~l0 10 0
18 13 NA 44 b
45 46 NA 80 FORM OF ACTIVITY COAT ENT RELE*SEO OF RELEASE AMOUNT OF ACTIVITY LOCATION OF RELEASE Qg Z ~Z NA 44 NA 7 8 9 10 11 45 80 PERSONNEL EXPOSURES NUMBER TYPE OCSCRIPTION
~00 0 X NA 7 89 11 12 13 80 PERSONNEL INJURIES NUMBER OESCRIPTION
~<4 69
~00 0 NA 7 11 12 80 OFFSITE CONSEQUENCES Jig NA 7 8 9 80 LOSS OR DAMAGE TO FACILITY TYPE OESCRlPTIOP7P/
Q~g Z NA 7 89 10 80 PUBLICITY NA 7 89 80 ADDITIONAL FACTORS Q~g NA 7 89 80 7 89 80 NAME; Da G. Wi zner PHDNE. 61 6 465 5901 CiPO 88 I ~ 88T
HOHV88 ssolnuss voiina~uxsio sew's'n 6C l Nd 6 83d8J-6l MS3Q 10ULH03
<Nsvgaoo aanaosg
Mmeman DJjg@ & G G N PDWER D~DIPUUIZI DONALD C. COOK NUCLEAR PLANT P.O. Box 458, Bridgman, Michigan 49106 February 6, 1978 Mr. J.G. Keppler, Regional Director Office of Inspect i on and Enforcement United States Nuclear Regulatory Commission 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 Comnissi,on Regulatory Guide 1. 16, Revision 4, Section 2.b, the following report is submitted:
RO 50-315/78-05.
Sincerely, D.V. Shaller Plant Manager
/bab cc: J.E. Dolan R.W. Jurgensen G.E. Lien R. Kilburn R.J. Vollen BPI R.C. Callen MPSC K.R. Baker RO: III P.W. Steketee, Esq.
R. Walsh, Esq.
G. Charnoff, Esq.
G. Olson PNSRC J.F. Stietzel F~ 8 91978 Dir., IE (30 copies)
Dir., MIPC (3 copies)
ri> s
>~
Form No. 4494 OLICENBEE EVENT REPORT CONTROL BLOCK: fPLEABE PAINT ALL REQUIRED INFDRIVIATIDM) 1 LICENSEE
~ Qr Ill I lrl p +Ul LICENS EVENT NAME LICENSE NUMBER TYPF
~o~ II I O C C 0 0 0 0 0 0 0 0 0 4 1 1 1 1 L0003~J 89
~
7 14 15 25 26 30 31 32 AEPORT REPORT
( f'g E.'/ G~~
g CATEGORY TYPE SOURCE DOCKET NUMBER FVENI OATF RII>OAT OATr:
IQD1Icorrr L L 0 5 0 0 3 1 5 0 1 1 6 7 8 0 2 0 6 7 8 7 8 57 58 59 60 61 JB 69'ra.4. (;.IJ 74 75 00 odOIYflMl<OITUQlfli8fo EVENT DESCRIPTION tQilARO Qo 2 Durin surveillance test ¹2 Boric Acid Transfer Pum dischar e ressure was 4 si 7 89 80
[0D3] lower than the minimum re uired. The pump mechanical seal was leaking and was re-7 8 9 80
[oa4I LJrlaced. The um was retested satisfactorily. The ¹I pump was operable. This con-7 8 9 80
[os dition did not re resent a substantial safety hazard. (RO 50-315/78-05) 7 8 9 80 QOQ 7 8 9 PRME 80 SYSTEM CAUSE COMPONENT COMPONENT
~07 7 8 8 10 p '~
CODE
~
CODE 11 12 P
COMPONENT COOE U M P X X 17 SUPPUER N
43 44 G
MANUFACTURER 2 0 0 47 VIOLATION 48 CAUSE DESCRIPTION
[oOs] The cause of the low dischar e ressur e was a leakin mechanical shaft seal. The 7 8 9 80
[QD9j 7 8 L seal failure was attributed to normal wear.
9 80 Qo]
7 89 METHOO OF 80 FACILITY STATUS POWER OTHER STATUS OISCOVERY OISCOVERY OESCRIPTION Irrrj 7 8 9
~~ ~io 10 o
12 13 44 b
45 46 NA 80 FORM OF ACTIVITY COATENT AMOUNT OF ACTIVITY LOCATION OF AELEASE NA 7 8 9 10 11 44 45 80 PERSONNEL EXPOSURES NUMBER TYPE OESCRIPTIO Qg LoaooJ z 7 89 11 12 13 80 PERSONNEL INJURIES NUMBER OESCAIPTION IrDaI LoaooJ IIA 7 89 11 12 80 OFFSITE CONSEQUENCES Qg NA 7 8 9 80 LOSS OR DAMAGE TO FACILITY TYPE OESCRIPTION
~16 Z NA 7 89 10 80 PUBLICITY NA 7 89 80 ADDITIONAL FACTORS Qjs] NA 7 89 80 Q~g 7 89 80 NAMEI Da G. Wizner PHONE. 616-465-5901 GPO 88T
RECDVEQ OOCUHENT CONTROl. OESK 3978FEB l5 PM 2 22 U.S. NRC OISTRlBUTION SERVlCES BRANCH