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Category:Letter
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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 ML24115A2152024-05-0707 May 2024 LTR: CNP Non-Acceptance with Opportunity TS 3-8-1 AEP-NRC-2024-24, Form OAR-1, Owners Activity Report2024-05-0707 May 2024 Form OAR-1, Owners Activity Report 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-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 ML18219B5551978-09-12012 September 1978 Letter from Indiana & Michigan Power Co to NRC Submitting Licensee Event Reports (RO 78-56/03L-1 and RO 78-061/03L-0) ML18219E1541978-09-12012 September 1978 Submit Licensee Event Report No. RO 78-049/03L-0 ML18219B5561978-09-0808 September 1978 Letter from Indiana & Michigan Power Co to NRC Submitting Licensee Event Reports (RO 78-059/03L-1 and RO 78-060/03L-0) ML18219E1551978-09-0808 September 1978 Submit Licensee Event Report No. RO 78-048/03L-0 ML18219B5571978-09-0505 September 1978 Letter from Indiana & Michigan Power Co to NRC Submitting License Event Report RO 78-059/03L-0 ML18219B5581978-08-30030 August 1978 Letter from Indiana & Michigan Power Co to NRC Submitting Licensee Event Report RO 78-058/03L-0 ML18219B5621978-08-22022 August 1978 Letter from Indiana & Michigan Power Co to NRC Submitting Licensee Event Reports (RO 78-056/03L-0 and RO 78-057/03L-0) ML18219B5611978-08-18018 August 1978 Letter from Indiana & Michigan Power Co to NRC Submitting Licensee Event Reports (RO 78-052/03L-0, RO 78-053/03L-0, RO 78-054-03L-0 and RO 78-055/03L-0) ML18219E1561978-08-15015 August 1978 Submit Licensee Event Report No. RO 78-047/03L-0 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) 2024-09-12
[Table view] |
LER-2024-002, Manual Reactor Trip Following Rapid Downpower for Steam Leak |
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Reporting criterion: |
10 CFR 50.73(a)(2)(iv)(A), System Actuation |
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3162024002R01 - NRC Website |
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INDIANA MICHIGAN POWER" An MP Company BOUNDLESS ENERGY-September 12, 2024 Docket No.: 50-316 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Donald C. Cook Nuclear Plant Unit 2 LICENSEE EVENT REPORT 316/2024-002-01 Indiana Michigan Power Cook Nuclear Plant One Cook Place Bridgman, Ml 49106 indianamichiganpower.com AEP-NRC-2024-73 10 CFR 50.73 Unit 2 Manual Reactor Trip Following Rapid Downpower for Steam Leak In accordance with 10 CFR 50. 73, Licensee Event Report (LER) System, Indiana Michigan Power Company, the licensee for Donald C. Cook Nuclear Plant Unit 2, is submitting as an enclosure to this letter the following report:
LER 316/2024-002-01 : Unit 2 Manual Reactor Trip Following Rapid Downpower for Steam Leak.
This LER is a revision to LER 316/2024-002-00, which was previously submitted by letter dated July 15, 2024. The enclosed LER has been revised to update the cause of the event and the corrective actions.
There are no commitments contained in this letter.
Should you have any questions, please contact Mr. Michael K. Scarpello, Regulatory Affairs Director, at (269) 466-2649.
Sincerely,
~t~~
Kelly J. Ferneau Site Vice President MPH/sjh Enclosure: Licensee Event Report 316/2024-002-01: Unit 2 Manual Reactor Trip Following Rapid Downpower for Steam Leak
U.S. Nuclear Regulatory Commission Page 2 c:
EGLE - RMD/RPS J.B. Giessner-NRC Region Ill NRC Resident Inspector N. Quilico - MPSC R. M. Sistevaris -AEP Ft. Wayne S. P. Wall, NRC Washington D.C.
A. J. Williamson - AEP Ft. Wayne AEP-NRC-2024-73
Enclosure to AEP-NRC-2024-73 Licensee Event Report 316/2024-002-01: Unit 2 Manual Reactor Trip Following Rapid Downpower for Steam Leak
Abstract
On May 15, 2024, at 04:27 EDT, the Donald C. Cook Nuclear Plant (CNP) Unit 2 reactor was manually tripped from 20%
reactor power following a rapid downpower in response to a steam leak. All control rods fully inserted, and electrical power was supplied by offsite. Auxiliary Feedwater Pumps automatically started as required, and decay heat removal was through the Condenser Steam Dump system. All required equipment operated as expected, and the trip was not complicated.
A leak on a one-inch diameter steam line caused by vibration required a unit downpower to take the Main Turbine offline, which led to diverging steam generator level oscillations that resulted in operators manually tripping the reactor. The reactor trip was caused by inadequate operating methodology of the Steam Generator Water Level Control '(SGWLC) System. A methodology was established to provide SGWLC during startup and low power operating conditions prior to restarting the reactor.
The event is reportable in accordance with 10 CFR 50. 73(a)(2)(iv)(A), System Actuation, due to the valid actuation of the Reactor Protection System and the Auxiliary Feedwater System, as a result of the manual reactor trip.
EVENT DESCRIPTION
- 2. DOCKET NUMBER
- 3. LER NUMBER I
00316 NUMBER NO.
I YEAR SEQUENTIAL REV
~-I 002 1-0 On May 15, 2024, at 04:27 EDT, the Donald C. Cook Nuclear Plant (CNP) Unit 2 Reactor was manually tripped from 20 percent power following a rapid downpower in response to a steam leak on a one-inch diamater steam line.
Unit 2 was supplied by offsite power before and after the reactor trip. All control rods fully inserted. Following the trip, the Auxiliary Feedwater (AFW)[BA] Pumps [P] started as required and operated as designed. Decay heat removal was through the Condenser Steam Dump system [Jl][COND]. All required equipment operated as expected, and the trip was not complicated.
Prior to the event, CNP performed a downpower of Unit 2 to take the Main Turbine [TA] offline for repair of a leak on a one-inch diameter steam line downstream of the Right Outer High Pressure Turbine Stop-Control Valve [XCV]. During the downpower, the leak worsened and operators transitioned to the rapid downpower procedure. Operators manually tripped the Main Turbine from 25 percent power at 03:55 EDT to isolate the steam leak. Following the turbine trip, Steam Generator
[SB][SG] water level oscillations resulted in operators manually tripping the reactor.
Event Notification 57128 was submitted in accordance with 10 CFR 50.72(b)(2)(iv)(B), Reactor Protection System (RPS) actuation as a four (4) hour non-emergency report, and under 10 CFR 50.72(b)(3)(iv)(A), specified system actuation of the AFW System, as an eight (8) hour non-emergency report.
The event is being reported in accordance with 10 CFR 50.73(a)(2)(iv)(A), System Actuation, due to the valid actuation of the RPS and the AFW System, as a result of the manual reactor trip.
CAUSE OF THE EVENT The direct cause of the event was the leak on a one-inch diameter steam line downstream of the Right Outer High Pressure Turbine Stop-Control Valve. The leak was caused by a crack in the steam line that initiated at the toe of a weld and worsened during the downpower due to vibration-induced crack propagation.
Operators transitioned to the rapid downpower procedure to expedite tripping the Main Turbine to isolate the steam leak.
Following the Main Turbine trip, Steam Generator water level oscillations resulted in operators manually tripping the reactor prior to reaching pre-established operational limits. The level oscillations were caused by inadequate administrative and engineering barriers associated with the operating methodology of the SGWLC System.
IMMEDIATE CORRECTIVE ACTIONS The steam leak downstream of the Right Outer High Pressure Turbine Stop-Control Valve was repaired.
A methodology was established to provide SGWLC during startup and low power operating conditions prior to restarting the reactor.
PLANNED CORRECTIVE ACTIONS
- 2. DOCKET NUMBER
- 3. LER NUMBER I
00316 NUMBER NO.
I YEAR SEQUENTIAL REV
~-I 002 1-0 The steam lead will be replaced with an upgraded design that will reduce vibration and ensure adequate support. Operating procedures will be revised and operators will be trained on an improved SGWLC operating methodology. Long-term corrective actions will enhance the engineering features of the SGWLC system.
ASSESSMENT OF SAFETY CONSEQUENCES NUCLEAR SAFETY All required equipment operated as designed and there was no actual or potential nuclear safety hazard resulting from the steam generator water level oscillations and subsequent reactor trip.
INDUSTRIAL SAFETY There was no actual personnel safety hazard resulting from the steam generator water level oscillations and subsequent reactor trip.
RADIOLOGICAL SAFETY There was no actual or potential radiological safety hazard, or radiological release, resulting from the steam generator water level oscillations and subsequent reactor trip.
PROBABILISTIC RISK ASSESSMENT (PRA)
A PRA risk assessment was performed by calculating the Conditional Core Damage Probability (CCDP) and the Conditional Large Early Release Probability (CLERP) of the transient initiating event. A comparison of the results of these calculations to the thresholds provided in NRC Inspection Manual Chapter (IMC) 0609, determined this event to be of "Very Low Safety Significance".
PREVIOUS SIMILAR EVENTS LER 316/2022-001-00, Automatic Reactor Trip Due to High-High Steam Generator Level, was submitted to the NRC as an enclosure to letter AEP-NRC-2023-01 (ML23004A205). The scope of the RCE conducted for the previous event was specific to operating conditions of the event and did not include low power operating conditions with the main turbine offline following a rapid downpower. Page 3
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