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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 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 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 ML18219B5541978-09-18018 September 1978 Letter from Indiana & Michigan Power Co to NRC Submitting Licensee Event Report (RO 78-062/03L-0) ML18219E1531978-09-18018 September 1978 Submit Licensee Event Report No. RO 78-050/03L-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) 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) 2024-09-12
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Z Indiana Michigan Power INDIANA Cook Nuclear Plant MICHIGAN One Cook Place Bridgman. MI 49106 POWERe AEP.com A unit of American Electric Power October 5, 2005 AEP:NRC:5333 Docket No: 50-316 U. S. Nuclear Regulatory Commission ANTN: Document Control Desk Mail Stop O-P1-17 Washington, DC 20555-0001 Donald C. Cook Nuclear Plant Unit 2 SPECIAL REPORT UNIT 2 REACTOR COOLANT INVENTORY TRACKING SYSTEM The attached special report is submitted in accordance with Donald C. Cook Nuclear Plant Improved Technical Specification 3.3.3. The report is required due to the inoperability of Unit 2 Reactor Coolant Inventory Tracking System, Channel B, for a period in excess of 30 days.
There are no regulatory commitments included in this submittal.
Should you have any questions, please contact Mr. Michael K. Scarpello, Regulatory Affairs Supervisor, at (269) 466-2649.
Sincerely, iN. Jensen Site Vice President RAJ/jen Attachment C: J. L. Caldwell, NRC Region III K. D. Curry - AEP Ft. Wayne, w/o attachment J. T. King, MPSC - w/o attachment MDEQ - WHMD/RPMWS - w/o attachment -- -,--E;;2 NRC Resident Inspector D. W. Spaulding, NRC Washington DC
Attachment to AEP:NRC:5333 REACTOR COOLANT INVENTORY TRACKING SYSTEM SPECIAL REPORT Indiana Michigan Power Company, the licensee for Donald C. Cook Nuclear Plant (CNP), is submitting this special report concerning an inoperable period exceeding 30 days for a channel of the Unit 2 Reactor Coolant Inventory Tracking System (RCITS). This special report is required by Improved Technical Specification (ITS) 3.3.3, Condition B, under required Action B.1.
ACTION TAKEN On July 31, 2005, at approximately 1315 hours0.0152 days <br />0.365 hours <br />0.00217 weeks <br />5.003575e-4 months <br />, 2-NLI-131, reactor vessel train B wide range water level indicating instrument, was declared inoperable due to a failed channel check. The Unit 2 Technical Specification (TS) in effect at the time, TS 3.3.3.6, "Post-Accident Instrumentation," Table 3.3-10, Item 16, "Reactor Coolant Inventory Tracking System," required only one of two trains of RCITS to be operable. No additional action requirements were specified. Under the TS, a complete RCITS train required 3 channels: upper plenum level, narrow range, and wide range. With the wide range indication unreliable, train B RCITS was declared inoperable.
Implementation of the ITS at CNP occurred September 25, 2005. RCITS train B (designated as channel B in ITS) was still inoperable. ITS 3.3.3, Condition B, Action B.1, requires action per ITS 5.6.6, "Post Accident Monitoring Report," to be taken if ITS 3.3.3, Condition A.1, restore channel to operable status, is not completed within 30 days of channel inoperability. The channel was returned to service September 29, 2005, following replacement of the circuit card for the 2-NLI-131 wide range instrument.
This information satisfies the requirement to submit a report within 14 days following 30 days of channel inoperability, per ITS 5.6.6.
PRE-PLANNED ALTERNATE METHOD OF MONITORING The RCITS is post-accident monitoring instrumentation. It provides plant operators with the information needed to assess void formation in the reactor vessel head region and the trend of liquid level in the reactor vessel plenum The RCITS consists of two redundant channels, each consisting of upper plenum level, narrow range level, and wide range (dynamic range) level. During the period of inoperability of RCITS channel B, the redundant channel A has been operable, and available for indication, as well as the narrow range and upper plenum level of channel B.
Attachment to AEP:NRC:5333 Page 2 The removal of channel B from operable status eliminated a means of redundant indication for the wide range monitoring. The wide range indication is called upon to determine void content, and is used to support decision making within the emergency operating procedures while the reactor coolant pumps (RCPs) are operating. The narrow range indication, used with no RCPs operating, and the upper plenum indication were still available.
The alternate method of monitoring is the redundant channel A. For the purpose of determining degraded core cooling status, other indications are used to corroborate excessive voiding in the reactor coolant system. They are RCS subcooling and core exit thermocouple temperature.
These diverse indications are used in conjunction with RCITS wide range level in plant emergency operating procedures to support recovery from emergency conditions.
CAUSE OF INOPERABILITY Replacement of the printed circuit card in the instrument rack restored the correct indication.
The channel was monitored for several days, and remained stable. It was concluded that a bad contact between the circuit card and the chassis was the likely mode of failure.
PLANS AND SCHEDULES FOR RESTORING THE SYSTEM TO OPERABLE STATUS RCITS channel B was declared operable on September 29, 2005.
RCITS channel B was again declared inoperable on October 3, 2005. Due to current plant conditions, the entire instrument loop cannot be tested to conclusively identify the failure. If the troubleshooting currently under way identifies components which cannot be replaced or repaired with the unit on line, it will be restored at the first planned outage of sufficient duration, but not later than restart from the Unit 2 Cycle 16 refueling outage scheduled for April 2006.