On February 5, 2017, during a quarterly sealed valve log audit, Residual Heat Removal ( RHR) Valves RHR-V-58 and RHR-V-60 were discovered sealed closed. Normal configuration for these valves is sealed opened. Consequently, Operations declared RHR pumps A and C Inoperable at 0756 hours0.00875 days <br />0.21 hours <br />0.00125 weeks <br />2.87658e-4 months <br /> and entered Technical Specifications (TS) Limiting Condition for Operation (LCO) 3.5.1 Condition A, LCO 3.6.1.9 Condition A, and LCO 3.6.2.3 Condition A.
Subsequently, the operating crew opened RHR-V-58 and RHR-V-60, independently verified the position of the valves and applied seals to the valves. As such, RHR pumps A and C were declared Operable at 1041 hours0.012 days <br />0.289 hours <br />0.00172 weeks <br />3.961005e-4 months <br /> on February 5, 2017, and TS LCO 3.5.1 Condition A, LCO 3.6.1.9 Condition A, and LCO 3.6.2.3 Condition A were exited.
The root cause is Operations Department standards related to Operator Human Performance and Configuration Control are inadequate and do not meet industry expectations. Licensed and Non-Licensed Operators completed training focused on Standards and Expectations related to attention to detail and configuration control. To prevent recurrence, expectations will be established and institutionalized for Operations Leadership to reinforce consistent application of operator fundamentals and to identify and correct performance gaps for the operating crews.
This is a Safety System Functional Failure. |
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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] |
Reported lessons learned are incorporated into the licensing process and fed back to industry. Send comments regarding burden estimate to the Information Services Branch (T-2 F43), U.S.
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.
-01
PLANT STATUS
Cooper Nuclear Station (CNS) was in Mode 1, Power Operations, at 100 percent power, at the time of discovery.
BACKGROUND
The safety objective of the Residual Heat Removal (RHR) system [El IS:BO] is to provide core cooling, in conjunction with other Emergency Core Cooling Systems, and to provide containment cooling as required during abnormal operational transients and postulated accidents. The RHR system consists of two heat exchangers [EIIS:HX], four main system pumps [EIIS:P] in two divisions, and associated piping, valves, controls and instrumentation.
The motor-operated minimum flow valves automatically provide the necessary flow through the pump in order to prevent pump overheating. The manual isolation valves for the motor-operated minimum flow valves, RHR-V-58 and RHR-V-60, are normally configured open and sealed.
RHR pumps A and C provide RHR Loop A safety functions associated with Low Pressure Cooling Injection (LPCI) and Containment Cooling. These pumps also provide RHR Loop A Shutdown Cooling (SDC) function during outage conditions.
EVENT DESCRIPTION
On September 29, 2016, during Refueling Outage 29 (RE29), RHR-V-58 and RHR-V-60 were closed and danger tagged in accordance with a clearance order to support the RHR Loop A Maintenance Window.
On October 7, 2016, the danger tags for RHR-V-58 and RHR-V-60 were released and the clearance order directed that both valves be restored to their normal configuration. The danger tags were removed and seals applied to the valves. However, the valves were not opened before placing the seals. Second verification incorrectly verified that the valves were sealed open, when they were sealed closed.
A quarterly sealed valve log audit was performed on November 29, 2016, and the seals were verified to be intact. The audit required only that the seals be verified, the audit did not require the valve configuration be checked.
On February 5, 2017, during a quarterly sealed valve log audit, it was discovered that RHR-V-58 and RHR-V-60 were sealed closed. Consequently, Operations declared RHR pumps A and C Inoperable at 0756 hours0.00875 days <br />0.21 hours <br />0.00125 weeks <br />2.87658e-4 months <br /> and entered Technical Specification (TS) Limiting Condition for Operation (LCO) 3.5.1 Condition A, LCO 3.6.1.9 Condition A, and LCO 3.6.2.3 Condition A.
Cooper Nuclear Station 05000- 298 2017
3. LER NUMBER
- 001 Reported lessons learned are incorporated into the licensing process and fed back to industry. Send comments regarding burden estimate to the Information Services Branch (T-2 F43), U.S.
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 -01 - 001 2017 Subsequently, the operating crew opened RHR-V-58 and RHR-V-60, independently verified the position of the valves and applied seals to the valves. As such, RHR pumps A and C were declared Operable at 1041 hours0.012 days <br />0.289 hours <br />0.00172 weeks <br />3.961005e-4 months <br /> on February 5, 2017, and TS LCO 3.5.1 Condition A, LCO 3.6.1.9 Condition A, and LCO 3.6.2.3 Condition A were exited.
BASIS FOR REPORT
With the minimum flow isolated since October 7, 2016, this is reportable as a condition prohibited by Technical Specifications per 10 CFR 50.73(a)(2)(i)(B) — 1) due to exceeding the Required Action Completion Time for the RHR subsystem out of service and 2) changing reactor Mode of operation during startup from RE29 with an RHR subsystem inoperable which is a violation of TS LCO 3.0.4. In addition, during the time frame of inoperability, Division 2 RHR had also been inoperable on various occasions resulting in both divisions of RHR being inoperable, creating a loss of safety function per 10 CFR 50.73(a)(2)(v)(B).
SAFETY SIGNIFICANCE
The actual safety significance of this condition is low. RHR Loop B remained available to provide LPCI and Containment Cooling functions for approximately 97% of the at power duration and no events or operations occurred requiring RHR pumps A or C to run dead-headed for an extended period of time.
Additionally, the safety significance of this condition during outage conditions is low. The minimum flow line is isolated by procedure, with the minimum flow valve being tagged closed prior to RHR pump operation when placing SDC in service.
CAUSE
The root cause evaluation determined that Operations Department standards related to Operator Human Performance and Configuration Control are inadequate and do not meet industry expectations.
CORRECTIVE ACTIONS
Licensed and Non-Licensed Operators completed training focused on Standards and Expectations related to attention to detail and configuration control. To prevent recurrence, expectations will be established and institutionalized for Operations Leadership (i.e., Operations Manager, Assistant Operations Managers, and Shift Managers) to reinforce consistent application of operator fundamentals and to identify and correct performance gaps for the operating crews. This will be accomplished by performing focused Crew Assessments in accordance with station procedures; identifying performance gaps and determining actions required to correct those gaps; requiring review of the crew assessments at crew management review meetings; and requiring that crew management review meetings be conducted in accordance with station procedures.
Reported lessons learned are incorporated into the licensing process and fed back to industry. Send comments regarding burden estimate to the Information Services Branch (T-2 F43), U.S.
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.
PREVIOUS EVENTS
03/14/17 — Condition Report written to document incorrectly installed seals on two service water valves (SW-V-105 and SW-V-124) that occurred in late February 2017.
01/30/17 — Fuse was installed incorrectly.
01/10/17 — Incorrect bulb installation caused light for Local Power Range Monitor downscale to remain on.
01/14/17 — Augmented Off-Gas +34 Glycol pump/compressor switches found in an incorrect position.
removed from service due to human error resulting in a loss of safety function.
12/02/16 — Setpoints verified on the Normal Range Kaman instead of the High Range Kaman.
11/21/16 — Incorrect log entry resulted in missed surveillance.
10/15/16 — Relay was found not reset.
10/03/16 — Control Rod Drive high cooling water differential pressure was noticed while making preparations to hang tags. Upon investigation, it was noticed that 75 Hydraulic Control Units (HCUs) were isolated, which left 62 in service for cooling. This is contrary to a precaution statement in a procedure which requires 70 HCUs to be in service.
09/30/16 — A CNS Operator and an Entergy Operator entered the steam tunnel to hang tags and inadvertently severed and extracted tubing being used for Local Leak Rate Testing.
09/28/16 — While performing rounds, the on watch non-licensed plant Operator adjusted air load pressure to the specifications in their logs, not per the procedure for the current plant condition. This caused Control Room indicators to show a lower Reactor Pressure Vessel level than actual.
due to a non-licensed plant Operator inadvertently opening the wrong drain valve while hanging tags.
-01 - 001 2017