12-19-2016 | On October 23, 2016, while conducting refueling and Operations with a Potential for Draining the Reactor Vessel activities, Control Room Emergency Filter System ( CREFS) Supply Fan A (SF-C-1A) experienced high vibration. A vibration analysis was performed and results indicated that vibration readings were elevated across all points for the motor and fan. Consequently, Operations declared CREFS inoperable at 19:08 hours. At 19:53 hours, SF-C-1B was started, CREFS was transferred to the alternate supply, and SF-C-1A was secured. At 23:41, Event Notification 52315 was made to the Nuclear Regulatory Commission Operations Center.
The fan was repaired on October 24 and 25, 2016, and a vibration analysis was performed on October 26, 2016, with satisfactory results. Operations declared CREFS operable at 1341 on October 27, 2016.
The root cause was the preventive maintenance strategy for the fan was ineffective to ensure shaft to bearing engagement is maintained. To prevent recurrence, the applicable maintenance plan will be revised to include verification that the bearings are adequately engaged to the fan shaft.
This is a Safety System Functional Failure.
3. LER NUMBER 2. DOCKET NUMBER 05000- 298 Cooper Nuclear Station -00 2016 - 006 |
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Category:Letter
MONTHYEARML23334A2012024-01-0303 January 2024 Issuance of Amendment No. 274 Revision to Technical Specifications to Adopt TSTF-551, Revision 3, Revise Secondary Containment Surveillance Requirements ML23311A1122023-11-0909 November 2023 Project Manager Assignment ML23311A2082023-11-0909 November 2023 Reassignment of U.S. Nuclear Regulatory Commission Branch Chief in the Division of Operating Reactor Licensing for Plant Licensing Branch IV IR 05000298/20230032023-11-0202 November 2023 Integrated Inspection Report 05000298/2023003 IR 05000298/20234012023-11-0101 November 2023 Cyber Security Report 05000298/2023401 Public ML23264A8052023-10-11011 October 2023 Issuance of Amendment No. 273 Revision to Technical Specifications to Adopt TSTF-580, Revision 1, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling ML23233A1882023-09-0505 September 2023 Regulatory Audit Plan in Support of Relief Request RC3-02 Regarding Drywell Head Bolting IR 05000298/20243012023-09-0101 September 2023 Notification of NRC Initial Operator Licensing Examination 05000298/2024301 IR 05000298/20230052023-08-21021 August 2023 Updated Inspection Plan for Cooper Nuclear Station (Report 05000298/2023005)- Mid Cycle Letter IR 05000298/20230022023-08-0808 August 2023 Integrated Inspection Report 05000298/2023002 IR 05000298/20234022023-08-0303 August 2023 NRC Security Inspection Report 05000298/2023402 ML23214A2742023-08-0303 August 2023 Nuclear Station - Notification of Inspection (NRC Inspection Report 05000298/2023004) and Request for Information IR 05000298/20234202023-08-0101 August 2023 Security Baseline Inspection Report 05000298/2023420 ML23173A0862023-06-26026 June 2023 Information Request for the Cybersecurity Baseline Inspection, Notification to Perform Inspection 05000298/2023401 IR 05000298/20230102023-05-17017 May 2023 Biennial Problem Identification and Resolution Inspection Report 05000298/2023010 IR 05000298/20234032023-05-0404 May 2023 Security Baseline Inspection Report 05000298/2023403 ML23129A2822023-04-20020 April 2023 Submittal of Revision 31 to Updated Safety Analysis Report ML23102A0282023-04-19019 April 2023 U.S. Nuclear Regulatory Commission Presentation at the May 8, 2023, Brownville Village Meeting IR 05000298/20230012023-04-17017 April 2023 Integrated Inspection Report 05000298/2023001 ML23060A1582023-03-0808 March 2023 Design Basis Assurance Inspection (Programs) Inspection Report 05000298/2023001 IR 05000298/20220062023-03-0101 March 2023 Annual Assessment Letter for Cooper Nuclear Station Report 05000298/2022006 ML23041A1622023-02-10010 February 2023 Licensed Operator Positive Fitness-for-Duty Test Request for Additional Information IR 05000298/20220042023-01-30030 January 2023 Integrated Inspection Report 05000298/2022004 IR 05000298/20220112022-12-23023 December 2022 License Renewal Phase 4 Inspection Report 05000298/2022011 ML22286A2072022-11-30030 November 2022 Issuance of Amendment No. 272 Revision to Technical Specifications to Adopt TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements IR 05000298/20220032022-10-27027 October 2022 Integrated Inspection Report 05000298/2022003 ML22304A0052022-10-26026 October 2022 Surveillance Capsule Location (Re-insertion Into the Reactor Vessel) IR 05000298/20223022022-10-20020 October 2022 NRC Initial Operator Licensing Examination Approval 05000298/2022302 ML22276A1562022-10-0505 October 2022 Notification of Commercial Grade Dedication Inspection 05000298/2023011 and Request for Information IR 05000298/20224022022-09-29029 September 2022 NRC Security Inspection Report 05000298/2022402 (Full Report) IR 05000298/20220052022-08-18018 August 2022 Updated Inspection Plan for Cooper Nuclear Station (Report 05000298 2022005) IR 05000298/20223012022-08-10010 August 2022 NRC Examination Report 05000298/2022301 IR 05000298/20220022022-07-28028 July 2022 Integrated Inspection Report 05000298/2022002 ML22200A2772022-07-21021 July 2022 Correction to Proposed Inservice Testing Alternative RS-01, Revision of Error in Safety Evaluation ML22152A1232022-07-18018 July 2022 Issuance of Amendment No. 271 Request for Exception from Certain Primary Containment Leak Rate Testing Requirements IR 05000298/20224012022-06-29029 June 2022 Security Baseline Inspection Report 05000298/2022401 IR 05000298/20224032022-06-28028 June 2022 Security Baseline Inspection Report 05000298/2022403 IR 05000298/20220102022-06-16016 June 2022 Triennial Fire Protection Inspection Report 05000298/2022010 ML22140A1612022-06-0808 June 2022 Proposed Inservice Inspection Alternative RR5-01 Revision 1 ML22147A1122022-06-0101 June 2022 NRC Initial Operator Licensing Examination Approval 05000298/2022301 ML22111A1382022-05-13013 May 2022 Proposed Inservice Testing Alternative RS-01, Revision 0 IR 05000298/20220012022-04-28028 April 2022 Integrated Inspection Report 05000298/2022001 IR 05000298/20224042022-04-13013 April 2022 Material Control and Accounting Program Inspection Report 05000298/2022404 - (Public) ML22084A6032022-04-0404 April 2022 Notification of NRC Evaluations of Changes, Tests and Experiments Inspection 05000298/2022002 and Request for Information ML22090A2892022-04-0101 April 2022 John Larson'S Invitation to Participate in the 8th Nuclear Regulatory Commission'S Workshop on Vendor Oversight ML22045A0012022-03-31031 March 2022 Proposed Inservice Inspection Alternative RI5- 02 Revision 3 IR 05000298/20210062022-03-0202 March 2022 Annual Assessment Letter for Cooper Nuclear Station (Report 05000298/2021006) IR 05000298/20210042022-01-24024 January 2022 Integrated Inspection Report 05000298/2021004 ML21350A0582021-12-21021 December 2021 Withdrawal of an Amendment Request ML21340A2362021-12-20020 December 2021 Issuance of Amendment No. 270 Adoption of Technical Specifications Task Force Traveler TSTF-582, Revision 0, RPV WIC Enhancements 2024-01-03
[Table view] Category:Licensee Event Report (LER)
MONTHYEAR05000298/LER-2016-0012017-09-27027 September 2017 De-Energized High Pressure Coolant Injection Auxiliary Lube Oil Pump Caused by Relay Failure Results in Loss of Safety Function and a Condition Prohibited by Technical Specifications, LER 16-001-01 for Cooper Nuclear Station Regarding De-Energized High Pressure Coolant Injection Auxiliary Lube Oil Pump Caused by Relay Failure Results in Loss of Safety Function, a Condition Prohibited by Tech Specs, and a 10 CFR Part 21 Report 05000298/LER-2017-0042017-08-17017 August 2017 Torus to Drywell Vacuum Breaker Failure to Indicate Full Closed Causes Loss of Safety Function, LER 17-004-00 for Cooper Nuclear Station Regarding Torus to Drywall Vacuum Breaker Failure to Indicate Full Closed Causes Loss of Safety Function 05000298/LER-2017-0052017-08-17017 August 2017 Traversing In-core Probe In-shield Limit Switch Mounting Failure Results in Common Cause Inoperability of Independent Trains or Channels and Condition Prohibited by Technical Specifications, LER 17-005-00 for Cooper Nuclear Station Regarding Traversing In-core Probe In-shield Limit Switch Mounting Failure Results in Common Cause lnoperability of Independent Trains or Channels and Condition Prohibited by Technical Specifications 05000298/LER-2017-0032017-07-24024 July 2017 Mispositioned Control Room Emergency Filter System Supply Fan Damper Causes Loss of Safety Function, LER 17-003-00 for Cooper Nuclear Station re Mispositioned Control Room Emergency Filter System Supply Fan Damper Causes Loss of Safety Function 05000298/LER-2017-0022017-04-27027 April 2017 Valve Test Failures Result in Condition Prohibited by Technical Specifications and a Loss of Safety Function, LER 17-002-00 for Cooper Nuclear Station Regarding Valve Test Failures Result in Condition Prohibited by Technical Specifications and a Loss of Safety Function 05000298/LER-2017-0012017-04-0505 April 2017 Residual Heat Removal Minimum Flow Valves OUt of Position Results in Loss of Safety Function and Condition Prohibited by Technical Specifications, LER 17-001-00 for Cooper Regarding Residual Heat Removal Minimum Flow Valves Out of Position Results in Loss of Safety Function and Condition Prohibited by Technical Specifications 05000298/LER-2016-0082017-01-0505 January 2017 Purchase and Installation of Incorrect Actuator Results in a Condition Prohibited by Technical Specifications, LER 16-008-00 for Cooper Nuclear Station Regarding Purchase and Installation of Incorrect Actuator Results in a Condition Prohibited by Technical Specifications 05000298/LER-2016-0072016-12-19019 December 2016 Isolation of Shutdown Cooling due to Relay Maintenance Results in a Loss of Safety Function, LER 16-007-00 for Cooper Nuclear Station Regarding Isolation of Shutdown Cooling due to Relay Maintenance Results in a Loss of Safety Function 05000298/LER-2016-0062016-12-19019 December 2016 High Vibration on Control Room Emergency Filter System Fan Results in Inoperability and Loss of Safety Function, LER-16-006-00 for Cooper Nuclear Station Regarding High Vibration on Control Room Emergency Filter System Fan Results in Inoperability and Loss of Safety Function 05000298/LER-2016-0042016-11-22022 November 2016 Closure of Multiple Main Steam Isolation Valves due to High Flow Signal, LER 16-004-00 for Cooper Nuclear Station Regarding Closure of Multiple Main Steam Isolation Valves due to High Flow Signal 05000298/LER-2016-0032016-11-0909 November 2016 Scaffold Construction Places Plant in a Condition Prohibited by Technical Specifications, LER 16-003-00 for Cooper Nuclear Station RE: Scaffold Construction Places Plant in a Condition Prohibited by Technical Specifications 05000298/LER-2016-0022016-06-27027 June 2016 De-Energized High Pressure Coolant Injection Auxiliary Lube Oil Pump Caused By Light Bulb Failure Results in Loss of Safety Function, LER 16-002-00 for Cooper Regarding De-Energized High Pressure Coolant Injection Auxiliary Lube Oil Pump Caused By Light Bulb Failure Results in Loss of Safety Function NLS2015063, Retraction of Licensee Event Report 2014-005-00, Lube Oil Leak Results in a Potential Condition Prohibited by Technical Specifications and a Potential Loss of Safety Function.2015-06-0909 June 2015 Retraction of Licensee Event Report 2014-005-00, Lube Oil Leak Results in a Potential Condition Prohibited by Technical Specifications and a Potential Loss of Safety Function. ML13149A1722013-05-26026 May 2013 E-mail from Micheal Mulligan to R.Guzman, Pilgrim Evacuation Plan Broken During Blizzard Nemo and Unenforced by the Nrc. NLS2013015, Special Report, Offgas Treatment System Charcoal Adsorbers Out of Service2013-01-29029 January 2013 Special Report, Offgas Treatment System Charcoal Adsorbers Out of Service NLS2008058, LER 08-S01-00 for Cooper Regarding Temporary Suspension of Security Measures Due to Tornado Warning2008-08-0505 August 2008 LER 08-S01-00 for Cooper Regarding Temporary Suspension of Security Measures Due to Tornado Warning 2017-09-27
[Table view] |
v LICENSEE EVENT REPORT (LER) / (See Page 2 for required number of digits/characters for each block) (See NUREG-1022, R 3 for instruction and guidance for completing this form http://www.nrc.govireading-rm/doc-collections/nuregs/staff/sr1022/r3/) APPROVED BY OMB: NO. 3150-0104 EXPIRES: 10/31/2018 Reported lessons learned are incorporated into the licensing process and fed back to industry. Send comments regarding burden estimate to the FOIA, Privacy and Information Collections Branch (1-5 F53), U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001, or by e-mail to Affairs, NEOB-10202, (3150-0104), Office of Management and Budget, Washington, DC 20503. If a means used to impose an information collection does not display a currently valid OMB control number, the NRC may not conduct or sponsor, and a person is not required to respond to, the information collection.
PLANT STATUS
Cooper Nuclear Station was in MODE 5, Refueling, at 0 percent power, at the time of the event. Diesel Generator (DG) 2 was inoperable for maintenance.
BACKGROUND
The Control Room Emergency Filter System (CREFS) [EIIS:JH] is designed to provide a radiologically controlled environment to ensure the habitability of the control room for the safety of control room operators under all plant conditions. The CREFS is a standby system. The instrumentation and controls for the CREFS automatically isolate the normal ventilation intake and initiate action to pressurize the main control room and filter incoming air to minimize the infiltration of radioactive material into the control room environment.
The safety related function of CREFS includes a single high efficiency air filtration system for emergency treatment of outside supply air and a Control Room Envelope boundary that limits the inleakage of unfiltered air. The system consists of a prefilter, a high efficiency air particulate air filter [El IS:FLT], an activated charcoal adsorber [EllS:ADS] section, a supply fan [EllS:FAN], and emergency booster fan, an exhaust booster fan, and the associated ductwork [EIIS:DUCT], valves [EllS:V] or dampers [EIIS:DMP], doors [EllS:DR], barriers, and instrumentation.
Technical Specifications (TS) 3.7.4 requires one supply fan to be Operable to support CREFS Operability.
In MODES 4 and 5, maintaining CREFS operable is not required except during Operations with a Potential for Draining the Reactor Vessel (OPDRV); and during movement of lately irradiated fuel assemblies in the secondary containment. Due to radioactive decay, CREFS is only required to be OPERABLE during fuel handing involving handling of lately irradiated fuel.
Power supply for Supply. Fan SF-C-1A is MCC LX (Division 1). Power supply for SF-C-1B is MCC-TX (Division 2).
EVENT DESCRIPTION
On October 21, 2016, Operations declared Diesel Generator 2 Inoperable in preparation for performing planned maintenance: Therefore, only SF-C-1A had essential power available.
On October 23, 2016, at 11:54 hours, Operations entered an OPDRV condition for Control Rod Drive maintenance using a freeze seal. The OPDRV condition required CREFS to be operable.
On October 23, 2016, at 13:56 hours, it was observed that control room supply fans were shaking while SF-C-1A was running, and it was noticed that a belt guard bracket had broken off.
Reported lessons learned are incorporated into the licensing process and fed back to industry. Send comments regarding burden estimate to the FOIA, Privacy and Information Collections Branch (T-5 F53), U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001, or by e-mail to Affairs, NEOB-10202, (3150-0104), Office of Management and Budget, Washington, DC 20503. If a means used to impose an information collection does not display a currently valid OMB control number, the NRC may not conduct or sponsor, and a person is not required to respond to, the information collection.
U.S. NUCLEAR REGULATORY COMMISSION A vibration analysis was performed and results indicated that vibration readings were elevated across all points for the motor and fan. It was recommended that SF-C-1A be removed from service. Operations declared CREFS inoperable at 19:08 hours, entering TS Limiting Condition for Operation 3.7.4, Condition A. At 19:53 hours, SF-C-1B was started and SF-C-1A was secured.
The fan was repaired on October 24 and 25, 2016. A vibration analysis was performed on October 26, 2016, with satisfactory results and Operations declared CREFS operable at 13:41 on October 27, 2016.
During investigation it was found that the drive end bearing locking collar was loose from the bearing and the shaft. This allowed the shaft to turn within the bearing inner race, causing damage to the shaft and resulting in high vibration levels. Preventive Maintenance (PM) on the Control Room supply fans are lubricated every 26 weeks, but the PM does not verify that bearing setscrews or locking collars are tight.
BASIS FOR REPORT
This event is reportable in accordance with 10 CFR 50.73(a)(2)(v)(D) as a condition that could have prevented the fulfillment of the safety function of structures or systems that are needed to mitigate the consequences of an accident. Event Notification 52315 was made to the Nuclear Regulatory Commission Operations Center.
SAFETY SIGNIFICANCE
This is a Safety System Functional Failure because of the loss of a single train safety-related system.
The plant was in MODE 5 performing refueling activities and conducting an OPDRV activity. CREFS was required to be operable in case of a drain down event resulting in uncovering fuel. The CREF system was fully functional with the exception of the SF-C-1A fan and the DG2 emergency electrical power supply to SF-C-1B. In the case of a drain down event, SF-C-1B was capable of being manually started and still had electrical power available from the Normal Station Service Transformer back feed and the Emergency Station Service Transformer. There were no actual safety consequences associated with this event. The potential safety consequences of this event were minimal due to the limited duration the condition existed and the redundant safety equipment which remained operable.
CAUSE
The root cause is the preventive maintenance strategy for the fan was ineffective to ensure shaft to bearing engagement is maintained.
Reported lessons learned are incorporated into the licensing process and fed back to industry. Send comments regarding burden estimate to the FOIA, Privacy and Information Collections Branch (T-5 F53), U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001, or by e-mail to Affairs, NEOB-10202, (3150-0104), Office of Management and Budget, Washington, DC 20503. If a means used to impose an information collection does not display a currently valid OMB control number, the NRC may not conduct or sponsor, and a person is not required to respond to, the information collection.
05000- 298 Cooper Nuclear Station - 006 -00 2016
CORRECTIVE ACTIONS
To prevent recurrence of this event, the Maintenance Plan will be revised to include verification that the bearings are adequately engaged to the fan shaft.
PREVIOUS EVENTS
There have been no events reported in the past three years related to CREFS being declared inoperable.
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05000298/LER-2016-001 | De-Energized High Pressure Coolant Injection Auxiliary Lube Oil Pump Caused by Relay Failure Results in Loss of Safety Function and a Condition Prohibited by Technical Specifications LER 16-001-01 for Cooper Nuclear Station Regarding De-Energized High Pressure Coolant Injection Auxiliary Lube Oil Pump Caused by Relay Failure Results in Loss of Safety Function, a Condition Prohibited by Tech Specs, and a 10 CFR Part 21 Report | 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000298/LER-2016-002 | De-Energized High Pressure Coolant Injection Auxiliary Lube Oil Pump Caused By Light Bulb Failure Results in Loss of Safety Function LER 16-002-00 for Cooper Regarding De-Energized High Pressure Coolant Injection Auxiliary Lube Oil Pump Caused By Light Bulb Failure Results in Loss of Safety Function | 10 CFR 50.73(a)(2)(v), Loss of Safety Function | 05000298/LER-2016-003 | Scaffold Construction Places Plant in a Condition Prohibited by Technical Specifications LER 16-003-00 for Cooper Nuclear Station RE: Scaffold Construction Places Plant in a Condition Prohibited by Technical Specifications | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000298/LER-2016-004 | Closure of Multiple Main Steam Isolation Valves due to High Flow Signal LER 16-004-00 for Cooper Nuclear Station Regarding Closure of Multiple Main Steam Isolation Valves due to High Flow Signal | 10 CFR 50.73(a)(2)(iv)(A), System Actuation | 05000298/LER-2016-005 | Implementation of Enforcement Guidance Memorandum 11-003, Revision 3, Causes Conditions Prohibited by Technical Specifications | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000298/LER-2016-006 | High Vibration on Control Room Emergency Filter System Fan Results in Inoperability and Loss of Safety Function LER-16-006-00 for Cooper Nuclear Station Regarding High Vibration on Control Room Emergency Filter System Fan Results in Inoperability and Loss of Safety Function | 10 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident | 05000298/LER-2016-007 | Isolation of Shutdown Cooling due to Relay Maintenance Results in a Loss of Safety Function LER 16-007-00 for Cooper Nuclear Station Regarding Isolation of Shutdown Cooling due to Relay Maintenance Results in a Loss of Safety Function | 10 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident | 05000298/LER-2016-008 | Purchase and Installation of Incorrect Actuator Results in a Condition Prohibited by Technical Specifications LER 16-008-00 for Cooper Nuclear Station Regarding Purchase and Installation of Incorrect Actuator Results in a Condition Prohibited by Technical Specifications | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications |
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