Similar Documents at Cook |
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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
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4
'REGULATORY I/FORMAT'I'ON'ISTRIBUTION SYSTEM (RIDS')'
DJ.STBj:9UTI ON FOR INCOMING'ATERI'AL 50-316
'I REC: KEPPLER J G ORG: SHALLER D V DOCDATE: 06/30/78 NRC IN 5 MI PWR DATE RCVD: 07/06/78 DOCTYPE: LETTER NOTARIZED: NG COPIES RECEIVED
SUBJECT:
LTR 1 ENCL 1 FORWARDING LICENSEE EVENT REPT (RO 50-316/78-038) ON 06/07/7S CONCERNING DURING SURVEILLANCE TEST ON CD PLANT BATTERY . CELL 589 WAS FOUND TO HAVE 8 ECIFIC GRAVITY BELOW 1200 MINIMUM SPECI -IC GRAVITY ALLOWED BY TECH SPECS... WfATT LERS78-039'8-040 AND 7g 0+ <
PLANT NAME: COOK UNIT 2 REVIEWER INITIAL: X JM lt DISTRIBUTOR Il INITIAL:~
<<+<~<<<<<H'<<~HH~<<DISTRIBUTION OF THIS MATFRIAL IS AS FOLLOWS NOTES:
SEND 3 COPIES OF ALL MATERIAL TO IS.E ED REEVES-1 CY ALL I'IATERIAL INCIDENT REPORTS (DISTRIBUTION CODE A002)
FOR ACTION: BR CHI - LWRN2'C54W/4 ENCL INTERNAL: EG . .~W/ENCL NRC PDR<<W/ENCL E+4~W/ 2 ENCL MIPC<<W/3 ENCL
- 8. C SYSTEMS BR4l+W/ENCL EMERGENCY PLAN BR<<M/ENCL NOVAK/CHECK+4FW/ ENCL EEB<<I Jf ENCL AD FOR ENG4twM/ENCL PLANT SYSTEMS BR<<W/ENCL HANAUER~~~W/ENCL AD FGR PLANT SYSTEMS+<M/ENCL AD FOR SYS 5 PROJ<<W/ENCL REACTOR SAFETY BR<<W/ENCL ENGINEERING BR4F4W/ENCL VOLLMER/BUNCH<<W/ENCL KREGER/J. COLLINSQ+M/ENCL POWER SYS BR<<M/ENCL K SEYFRI T/ IE~~~~W/ ENCL EXTERNAL: LPDR S ST. JOSEPH' I <<W/ENCL TIC~~~W/ENCL NS I C~~~W/ENCL ACRS CAT B~F+W/16 ENCL DISTRIBUTION: LTR 45 ENCL 45 CONTROL NBR: 781870119 S I ZE: 1P+ 1 P+3P
<<%0HM 4 %%8M <<%9M 4 %%%%%0$ <<%084 %0E%HF0F<<THE FND
8 ISION LE MASTER ROSTER PUBLICATIONS I
I DISTR D ISTRIBUT ION DISTR IBUT ION ABUT CODES QTY.
1 17 17 18 3~
~
--II Y ST ZIP I
I I
DISTR D I STR.I I
BUT BUT ION ION ION CODES CODES QTY 35 35 RD OF SUPERVISGRS LR IRNOMAN SAN DIEGO CO BD SUP 1
'4 DIEGO CA 92101 BRARI AN 1 N I D EGO CA 92101 SN SR SF SE SM SO ST SA SG N DIEGO CA 92101 NB NU 1 1 SF SE SM SP ST SO SA SG CL EAR PHARMAC I ST 1 1 1 1 1 1 1 1 N DIEGO CA 92103 N D IEGO CA 92108 SN SF SE SM ST SG J OLLA CA 9203 7 CH 1
SN SR SF SE ST SG 92110 1 1 1 1,1 1 AN DIEGO CA 1 1 1 1 1 1 1 li AN DIEGO CA 92110 SN SR SF SE SM SP ST SO SA SG CM AN DIEGO CA 92112 iM
~Xi er4oen 7'O'NDIANA
& MICHIGANPOWER COMPANY DONALD C. COOK NUCLEAR PLANT P.O. Box 458, Bridgman, Michigan 49106 V7 7 r;j fC"7f'7 c Cr~'
June 30, 1978 1 ~
7 f '7.4 C iC9 "7
7 C"3 Cl7 C77
~>cv C.M Mr. J.G. Keppler, Regional Director ~7 Kl CD Office of Inspection and Enforcement United States Nuclear Regulatory Commission CD Region III C/7 799 Roosevelt Road Glen Ellyn, IL 60137 Operating License DPR-74 Docket No. 50-316
Dear Mr. Keppler:
Pursuant to the requirements of the Appendix A Technical Specifications the following reports are submitted:
RO 78-038/03L-0 RO 78-039/03L-0 RO 78-040/03L-0 RO 78-041/03L-O.
Sincerely, D.VS Shaller Plant Manager
/bab cc: J.E. Dolan R.W. Jurgensen R.F. Kroeger R. Kilburn R.J. Vollen BPI K.R. Baker RO:III R.C. Callen MPSC P.W. Steketee, Esq.
R. Walsh, Esq.
G. Charnoff, Esq.
G. Olson J.M. Kennigan PNSRC J.F. Stietzel R.S. Keith Dir., IE (30 copies) JUL 03 1978 Dir., MIPC (3 copies) Y.
LP ll
NRC FORM 366 U. S. NUCLEAR REGULATORY COMMISSION (7.77)
LICE NT REPORT CONTROL BLOCK: Qi (PLEASE PRINT OR TYPE ALL REOUIRED INFORMATION)
I 6
[os) M I D D C 2 Q2 14 15 0 0 - 0 0 0 0 LICENSE NUMBER
- p 0 25 Qs 26 4 1 1 1 LICENSE TYPE 30 1 QE~QE 57 CAT 58 7 8 9 LICENSEE CODE CON'T
~o1 " ' ~LQB 0 5 '0 0 0 3 1 6 Q7 0 6 0 " 7 8 QB 0 6 3 0 7 8 ee 68 69 EVENT DATE 74 75 REPORT DATE 80 7 8 60 61 DOCKET NUMBER EVENT DESCRIPTION AND PROBABLE CONSEQUENCES Q10 During survei 11 ance test on CD Plant Battery, cel 1 )I 89 was found to have a
~O3 specif ic gravi ty of 1 ~ 195 whi ch is below the 1 ~ 200 minimum speci fic gravity
~O4 allowed per T. S. 4.8. 2. 3. 2a, 2, which .-constituted an inoperable battery.
~OS AB battery was operable. DC loads were shifted to AB battery for a period of
~OB 16 mi nutes whi-1 e cell 889 was jumpered . CD battery was returned to service a fter
~O7 being inoperable for 80 minutes. This event had no,effect upon public health
~OB and safety.
80 7 8 SYSTEM CAUSE CAUSE COMP. VALVE SUBCODE COMPONENT CODE SUBCODE SUBCODE
~og 7 8
~EC 9
CODE 10 Q>>
CODE 11 E
Q LAJQ73 12 13 8 A .T T R Y 18 8 LZJQEE 19 L2J 20 Q
REVISION SEQUENTIAL OCCURRENCE REPORT REPORT NO. CODE TYPE NO.
U EVENT YEAR Q17 LF R(RO REPoRT ~78 21 22 23 L0038 26I 24 L~J 27 LLJ 28 29 UL 30 Q
31 32 0
ACTION FUTURE EFFECT SHUTDOWN ATTACHMENT NPRDP PRIME COMP. COMPONENT TAKEN ACTION ON PLANT METHOD HOURS Q22 SUBMITTED FORM SUB. SUPPLIER MANUFACTURER LCJQ>> LZJQ23 LZJQ>> O O O O ~NQ23 ~YQ24 ~AQEE E 3 5 5 Q23 LXJQER 33 34 35 36 37 40 41 42 43 44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS Q27 The exact cause of the 1 ow speci fi c ravi t could not be determi ned ~ A rocedure i s being developed to attempt to restore the cell . Also, a repl acement cell has been ordered incase restorati on is not possible. Remaining cel 1 s in CD battery 3
show no similar problems ~
4 8 80 7 9 FACILITY METHOD OF OTHER STATUS QBO DISCOVERY DISCOVERY DESCRIPTION Q32 STATUS ~ % POWER 7 8
~BQ23 9
~pg 10 p Qs 12 13 NA 44
~BQ31 45 46 NA 80 ACTIVITY CONTENT RELEASED OF RELEASE AMOUNT OF ACTIVITY Q NA LOCATION OF RELEASE Q
~Z Q33 Z Q34 NA 7 8 9 10 11 44 45 80 PERSONNEL EXPOSURES NUMBER TYPE DESCRIPTION Q39 Q37 MZQ33 NA 8 11 12 13 80 7 9 PERSONNEL INJURIES '.
((ygg5 7 8 9 11 12 80 LOSS OF OR DAMAGE TO FACILITY 43 TYPE DESCRIPTION g Z Q42 NA 8 9 10 80 7
PUBLICITY NRC USE ONLY ISSUED DESCRIPTION Q o 7 8
~Ze 9 10 NA 68 69 BOP 2
g NAMF oF PREPARER Dave Wizner PHONE
NRC FORM 366 U. S. NUCI.EAR REGULATORY COMMISSION 1, LICENSEE EVENT REPORT CONTROL BLOCK: QI {PLEASE PRINT OR TYPE ALL. REQUIRED INFORMATION)
I 6
~oi 7 8 9 N I 0 LICENSEE'ODE C C ZJOO 14 15 0 - 0 0 0 0 LICENSE NUMBER 0 0 DQ25 26 1 1 LICENSE TYPE 1 1Q~00 30 57 CAT 58 CON'T
~01 soosos LUQs 0 5 0 0 0 3 1 6 68 Q 69 0 6 1 EVENT DATE 5 7 8 74 Qs0 75 6 3 REPORT DATE 0 7 8 80 Q
60 61 DOCKET NUMBER EVENT DESCRIPTION AND PROBABLE CONSEQUENCES Q10 During survei 1 1 ance test on AB Pl ant Battery, cell 835 was found to have a
~O3 ', specificJgravity of 1.197 which is below the 1.200 minimum specific gravity
~p4 allowed per T.S. 4.8.2.3.2a, 2 which constituted an inoperable battery. CD
~OS battery was operable. DC loads were shifted to CD battery for a period of
~ps 13 minutes while cell 7II35 was jumpered. AB battery was returned to service after
~O7 being inoperable for 29 minutes. This event had no effect on:publ.ic I health and
~08 safety. Reference similar LER No. 78-038/03L-O.
80 7 8 9 4 SYSTEM CAUSE CAUSE COMP. VALVE CODE CODE SUBCODE COMPONENT CODE SUBCODE SUBCODE
~OS C Q11 ~ZQ12 ~AQ13 8 A T T 8 Y Q4 ~ZQ15 ~Z Qs 8 9 10 11 12 13 18 19 20 7
SEQUENTIAL OCCURRENCE REPORT REVISION Q>>
ACTION FUTURE LF R(RO ssso>>
EVENT YEAR
[zan+22 21 EFFECT
+
23 SHUTDOWN
~03 24 REPORT NO.
9 26
+w 27
~03 28 ATTACHMENT CODE 29 NPRDR TYPE
~L 30 PRIME COMP.
31 32 NO.
0 COMPONENT TAKEN ACTION ON PLANT METHOD HOURS Q22 SUBMITTED FORM SUB. SUPPLIER MANUFACTURER
~CQ13 ~ZQ25 ~ZQ>> 0 0 0 0 ~NQ23 ~YQ24 A Q25 5 3 5 5 Qss Q15 33 34 35 36 37 40 41 42 43 44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS Q27 p The exact cause of the low s ecific ravit could not be determined. A procedure is being developed to attempt to restore the cell. Also, a replacement cell has been ordered in case restoration is not possible. Remaining cells in 3
AB battery show no similar problems.
4 7 8 9 80 FACILITY METHOD OF STATUS 51 POWER OTHER STATUS QSO DISCOVERY DISCOVERY DESCRIPTION Q32 5 ~8 Q25 ~05 0 Q25 NA 44
~BQ" 45 46 NA 80 7 8 9 10 , 12 13 ACTIVITY RELEASED OF RELEASE CONTENT AMOUNT OF ACTIVITY NA Q NA LOCATION OF RELEASE Q 6 ~Z Q33 ~ZQ34 80 7 8 9 10 44 45 PERSONNEL EXPOSURES NUMBER TYPE DESCRIPTION Q39 7 8
~00 9
0 11 Q31 12 Z Qss 13 80 PERSONNEL INJURIES NUMBER DESCRIPTION Q41
~15 ~OO O Q45 NA 80 7 8 9 11 12 LOSS OF OR DAMAGE TO FACILITY 43 TYPE DESCRIPTION z Q4. NA 8 9 10 80 PUBLICITY NRC USE ONLY ISSUED DESCRIPTION Q
~2O ~ZQ4 NA 68 69 80 ~
2 45 8 9 10 616 465 5901 3 EXT 4 398 NAME OF PREPARER PHONE
NRC FORM 366 U. S. NUCLEAR REGULATORY COMMISSION
{7.77) .
LtCENSEE EVENT REPORT CONTROL BLOCK: Ql (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION)
I 6
[os) 8 9
[ D LICENSEE CODE C C 2 14 Q 15 o o o 0 0 LICENSE NUMBER 0 0 0 o 25 Q 26 4 I I I LICENSE T)[PE 30 QE~QE 57 CAT 58 CON'T ULQE 0 6 0 0 0 3 1 6Q70 6 0 3 7 8QE 0 6 3 0 7 8 7 8 60 61 DOCKET NUMBER 68 69 EVENT DATE 74 75 REPORT DATE 5
EVENT DESCRIPTION AND PROBABLE CONSEQUENCES Q10
~O2 AFTER THREE REACTOR TRI'PS ON JUNE 3 9 13 1978 ROD BOTTOM POSI'TIO INDICATION
~O3 FOR CONTROL ROD H-8 DID NOT INDICATE THAT H-8 WAS FULLY INSERTED.
~O4 THE ACTION RE(UIREMENT OF T.S. 3.1.1.1 WAS FULFILLED BY EMERGENCY BORATING FOR 5 MINUTES.
~O6
~O7
~OB 7' 9 80 SYSTEM CAUSE CAUSE COMP. VALVE.
CODE CODE SUBCODE COMPONENT CODE SUBCODE SUBCODE 7 . 8 9 0
10 Q UxQ UxQ 11 12 13 18 Q14 U[
19 Q15 ~Z 20 Q16 SEQUENTIAL OCCURRENCE REPORT REVISION Q17 LF RIRP REPoRT EVENT YEAR I778J U ~04 REPORT NO.
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CODE TYPE UL NO.
laJ 21 22 23 24 27 28 29 30 31 32
'5 ACTION FUTURE EFFECT SHUTDOWN ATTACHMENT NPRDQ PRIME COMP. COMPONENT Q
TAKEN ACTION 33 Ql!I Ux 34 Qlg ONPLANT Uz Q20 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS Q27 METHOD Uz 36 Q21 37 0
HOURS 0 0 0 22 40 SUBMITTED 41 N Q23 ~
FORM SUB.
42 Q24 SUPPLIER L[LIQ25 43 44 MANUFACTURER II I 2 0 Q25 47 o
NA 3
4 7 8 9 80 5
FACILITY STATUS UD Q25 ~OG 39 POWER 0 Q29 OTHER STATUS NA
~
~3P =
METHOD OF DISCOVERY L[LJ Q31 DISCOVERY DESCRIPTION Q32 7* 8 9 10 12 13 44 45 46 80 QQQ ACTIVITY CONTENT RELEASED OF RELEASE
~Z Q3 Z Q3
~
AMOUNTOF ACTIVITY NA
~ LOCATION OF RELEASE Q 7 8 9 10 11 44 45 80 PERSONNEL EXPOSURES NUMBER TYPE DESCRIPTION Q39 7 ~<< 0 Q37 2 Q35 NA 7 8 9 '1 PERSONNEL INJURIES 12 13 80 NUMBER DESCRIPTION Q
[ii~j ~00 7 8 9 0
511 Q49 12 NA 80 LOSS OF OR DAMAGE TO FACILITY Q43
~IB ~<Q42 NA 7 8 9 10 80 PUBLICITY o
ISSUED
~NQ44 DESCRIPTION Q N NRC USE ONLY o44 7 8 9 10 68 69 80 o 0
NAME OF PREPARER JaCk RlsChlln PHONE:
I
I'RC FORM 366 I7.77),,
LICENSEE EVENT REPORT CONTROL BLOCK: QI (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION) 1 6 7 8 9 M I D LICENSEE CODE C C 2 14 Q2 15 0 0 0 0 0 0 LICENSE NUMBER 0 0 0 0 25 Q34 26 1 1 LICENSE TYPE 1 1 30 Q4~QE 57 CAT 58 CON'T
"'""'LJQBO 5 0 0 0 3 I 6 Q70 6 0 2 7 8 QB 75 0 6 3 0 7 80 REPORT DATE 8'0 7 8 61 DOCKET NUMBER 68 69 EVENT DATE 74 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES Q10 DURING NORMAL OPERATION, ROD POSITION INDICATION FOR CONTRO D-MEF1 THE
+ 12 STEP LIMIT OF T. S. 3.1.3.2. PREVIOUS OCCURRENCES OF A
~O3
~O4 S IMILAR NATURE INCLUDE: RO-050/316-78-31,22,08,07'.~,'RO-050/315-78-.07,04.
~OS 77-34,33,28,27,76-54,44,13.
~O6
~O7
~Os 80 7 8 9 SYSTEM CAUSE CAUSE COMP. VALVE.
CODE CODE SUBCODE COMPONENT CODE SUBCODE SUBCODE 7 8
~IE 9 10 Qll E 11 Q12 ~ZQ13 12 13 I N 5 T R 0 18 Q4 ~IQ19 19
~Z 20 QTE SEQUENTIAL OCCURRENCE REPORT REVISION LF R IRO EVENT YEAR REPORT NO. CODE TYPE Q11 REPORT
[77J 21 22 23
~O< I 24 26
~~
27
~OS 28 29 30 31
+o ACTION FUTURE EFFECT SHUTDOWN ATTACHMENT NPRDR PRIME COMP. COMPONENT TAKEN ACTION ON PLANT METHOD HOURS Q22 SUBMITTED FORM SUB. SUPPLIER MANUFACTURER
~EQTE 33
~Z 34 QEE ~Z 35 Q20 ~Z 36 Q 37 0 0 0 40
~N 41 Q23 LE) Q24 42 IJL) QEE 43 44 47 QE CAUSE DESCRIPTION AND CORRECTIVE ACTIONS Q27
~1O INVESTIGATION REVEALED THAT THE SIGNAL CONDITIONING MODULE OUTPUT VOLTAG AFTER THE ROD'S SECONDARY COIL VOLTAGE WAS MEASURED TO VERIFY THA THE CORRECT POSITION, THE SIGNAL CONDITIONING MODULE WAS RECALIBRATED AND 3 PLACED BACK IN SERVICE RETURNING RPI TO WITHIN THE 12 STEP LIMIT 4
7,8 9 80
~lE FACILITY STATUS
~E Q29 ~06
% POWER 5 Q29 NA OTHER STATUS ~
~3P MfTHDD OF
<<DISCOVERY
~AQ31 OPERATOR OBSERVATION DISCOVERY DESCRIPTION Q32 7 8 9 10 12 13 44 45 46 80 ACTIVITY CONTENT RELEASED OF RELEASE Q33 Z Q34 AMOUNTOF ACTIVITY NA
~ NA LOCATION OF RELEASE Q 7 8 9 10 11 44 45 80 PERSONNEI. EXPOSURES NUMBER TYPE DESCRIPTION Q39 1 ~00 0 QET Z Q39 NA 80 7 8 9 11 12 13 PERSONNEL INJURIES NUMBER DESCRIPTION 41 9
8
~00 9
0 Q49 11 12 QIIA 80 7
LOSS OF OR DAMAGE TO FACILITY TYPE DESCRIPTION Q43 Z Q4, NA.
7 8 9 10 80 PUBLICITY NRC USE ONLY ISSUED DESCRIPTION~ 44 O
O LNJQ4" 7 8 9 10 68 69 80 g Jack Risch]ing 616-465-5901 0 NAME OF PREPARER