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Category:Letter
MONTHYEARIR 05000277/20240032024-11-0404 November 2024 Integrated Inspection Report 05000277/2024003 and 05000278/2024003 RS-24-093, Response to Request for Additional Information - Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests2024-10-10010 October 2024 Response to Request for Additional Information - Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests ML24284A2842024-10-10010 October 2024 (Wcgs), Revision of One Form That Implements the Radiological Emergency Response Plan (RERP) ML24281A1012024-10-0707 October 2024 Senior Reactor and Reactor Operator Initial License Examinations ML24275A2442024-10-0303 October 2024 Reassignment of the U.S. Nuclear Regulatory Commission Branch Chief, Division of Operating Reactor Licensing ML24240A1692024-09-18018 September 2024 Cy 2023 Summary of Decommissioning Trust Fund Status ML24221A2582024-09-0606 September 2024 Response to Request for Re-Engagement Regarding the Subsequent License Renewal Environmental Review for Peach Bottom Atomic Power Station, Units 2 and 3 ML24255A8642024-09-0606 September 2024 Rscc Wire & Cable LLC Dba Marmon Industrial Energy & Infrastructure - Part 21 Retraction of Final Notification 05000277/LER-2024-003, Automatic Reactor Scram Following Main Turbine Trip Due to Degraded Condenser Vacuum2024-09-0505 September 2024 Automatic Reactor Scram Following Main Turbine Trip Due to Degraded Condenser Vacuum IR 05000277/20240052024-08-29029 August 2024 Updated Inspection Plan for Peach Bottom Atomic Power Station, Units 2 and 3 (Report 05000277/2024005 and 05000278/2024005) ML24239A3972024-08-23023 August 2024 Rssc Wire & Cable LLC Dba Marmon - Part 21 Final Notification - 57243-EN 57243 ML24235A0342024-08-23023 August 2024 U.S. Nuclear Regulatory Commission’S Analysis of Constellation Energy Generation’S Decommissioning Funding Status Report IR 05000277/20240102024-08-23023 August 2024 Fire Protection Team Inspection Report 05000277/2024010 and 05000278/2024010 IR 05000277/20240022024-08-14014 August 2024 Integrated Inspection Report 05000277/2024002 and 05000278/2024002 IR 05000482/20240052024-08-14014 August 2024 Updated Inspection Plan for Wolf Creek Generating Station (Report 05000482/2024005) ML24225A1692024-08-12012 August 2024 10 CFR 50.46 Annual Report ML24222A6772024-08-0909 August 2024 Response to Request for Additional Information for Application to Revise Technical Specifications to Adopt TSTF-591-A, Revise Risk Informed Completion Time (RICT) Program Revision 0 and Revise 10 CFR 50.69 License Condition ML24214A3232024-08-0101 August 2024 Response to Request for Additional Information - Request for Alternative Schedule to Complete Decommissioning Beyond 60 Years of Permanent Cessation of Operations ML24208A0962024-07-25025 July 2024 57243-EN 57243 - Rssc Wire & Cable LLC, Dba Marmon - Part 21 Notification ML24206A1252024-07-24024 July 2024 Revision of Three Procedures and Two Forms That Implement the Radiological Emergency Response Plan (RERP) ML24191A0612024-07-0606 July 2024 Independent Spent Fuel Storage Installation (ISFSI) - Annual Radioactive Effluent Release Report ML24178A4142024-06-26026 June 2024 Revision of One Procedure and One Form That Implement the Radiological Emergency Response Plan (RERP) ML24178A3672024-06-26026 June 2024 Correction to 2023 Annual Radioactive Effluent Release Report – Report 47 ML24177A1512024-06-24024 June 2024 Post Accident Monitoring Instrumentation Report ML24166A1172024-06-20020 June 2024 Regulatory Audit Summary Regarding Proposed Alternative Schedule to Complete Decommissioning Beyond 60 Years RS-24-061, Constellation Energy Generation, LLC, Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations2024-06-14014 June 2024 Constellation Energy Generation, LLC, Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations IR 05000277/20243012024-06-13013 June 2024 Initial Operator Licensing Examination Report 05000277/2024301 and 05000278/2024301 RS-24-058, Regarding Subsequent License Renewal Environmental Review2024-06-0505 June 2024 Regarding Subsequent License Renewal Environmental Review ML24151A6482024-06-0303 June 2024 Changes in Reactor Decommissioning Branch Project Management Assignments for Some Decommissioning Facilities ML24150A2722024-05-29029 May 2024 Annual Radiological Environmental Operating Report 81, January 1, 2023 Through December 31, 2023 ML24150A0032024-05-28028 May 2024 Request for Exemptions from 10 CFR 50.82(a)(8)(i)(A) and 10 CFR 50.75(h)(1)(iv) and Proposed Amendment to the Decommissioning Trust Agreement ML24079A0762024-05-23023 May 2024 Issuance of Amendments to Adopt TSTF 264 RS-24-055, 2023 Corporate Regulatory Commitment Change Summary Report2024-05-17017 May 2024 2023 Corporate Regulatory Commitment Change Summary Report IR 05000277/20240012024-05-13013 May 2024 Integrated Inspection Report 05000277/2024001 and 05000278/2024001 ML24134A1792024-05-13013 May 2024 Supplemental Information in Support of Request for Alternative Schedule to Complete Decommissioning Beyond 60 Years of Permanent Cessation of Operations IR 05000277/20245012024-05-0808 May 2024 Emergency Preparedness Biennial Exercise Inspection Report 05000277/2024501 and 05000278/2024501 ML24121A1832024-04-30030 April 2024 Pre-Submittal Meeting Presentation Material Peach Bottom ECCS Compensated Level System Replacement Project RS-24-041, Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests2024-04-30030 April 2024 Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests ML24118A0032024-04-27027 April 2024 2023 Annual Radioactive Effluent Release Report - Report 47 ML24120A2762024-04-23023 April 2024 Independent Spent Fuel Storage Installation (ISFSI) Facility - Annual Radioactive Effluent Release Report 66 January 1, 2023 Through December 31, 2023 CNL-24-033, Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2024-04-17017 April 2024 Central Emergency Control Center Emergency Plan Implementing Procedure Revisions ML24107A2462024-04-15015 April 2024 Submittal of Changes to Technical Specifications Bases ML24103A2042024-04-12012 April 2024 Constellation Energy Generation, LLC, Application to Revise Technical Specifications to Adopt TSTF-591-A, Revise Risk Informed Completion Time (RICT) Program Revision 0 and Revise 10 CFR 50.69 License Condition ML24102A0472024-04-11011 April 2024 Operator Licensing Examination Approval 05000277/LER-2024-002, Uncoordinated DC Circuits Cause Unanalyzed Condition2024-04-0808 April 2024 Uncoordinated DC Circuits Cause Unanalyzed Condition RS-24-002, Constellation Energy Generation, LLC - Annual Property Insurance Status Report2024-04-0101 April 2024 Constellation Energy Generation, LLC - Annual Property Insurance Status Report RS-24-023, Report on Status of Decommissioning Funding.2024-03-22022 March 2024 Report on Status of Decommissioning Funding. IR 05000277/20244022024-03-12012 March 2024 Cybersecurity Inspection Report 05000277/2024402 and 05000278/2024402 (Cover Letter Only) ML24061A2642024-03-0101 March 2024 Revision of Two Procedures That Implement the Radiological Emergency Response Plan (RERP) for Wolf Creek Generating Station (WCGS) Commissioners ML24060A1192024-02-29029 February 2024 Notification of Conduct of a Fire Protection Team Inspection 2024-09-06
[Table view] Category:Licensee Event Report (LER)
MONTHYEAR05000277/LER-2024-003, Automatic Reactor Scram Following Main Turbine Trip Due to Degraded Condenser Vacuum2024-09-0505 September 2024 Automatic Reactor Scram Following Main Turbine Trip Due to Degraded Condenser Vacuum 05000277/LER-2024-002, Uncoordinated DC Circuits Cause Unanalyzed Condition2024-04-0808 April 2024 Uncoordinated DC Circuits Cause Unanalyzed Condition 05000277/LER-2024-001, Automatic Reactor Scram Due to an Invalid Generator Lockout2024-03-21021 March 2024 Automatic Reactor Scram Due to an Invalid Generator Lockout 05000278/LER-2023-002, Main Steam Isolation Valves Stroke Times Exceed Technical Specification Limit2023-12-14014 December 2023 Main Steam Isolation Valves Stroke Times Exceed Technical Specification Limit 05000278/LER-2023-001, Standby Liquid Control Pump Inoperable for Greater than LCO Window Due to Gas Intrusion2023-11-0707 November 2023 Standby Liquid Control Pump Inoperable for Greater than LCO Window Due to Gas Intrusion 05000277/LER-2022-002, Automatic Depressurization System Safety Relief Valve Actuator Diaphragm Degraded2022-12-15015 December 2022 Automatic Depressurization System Safety Relief Valve Actuator Diaphragm Degraded 05000277/LER-2022-001, Automatic Reactor Scram Due to Loss of Power to Both RPS Buses2022-07-15015 July 2022 Automatic Reactor Scram Due to Loss of Power to Both RPS Buses 05000277/LER-2021-003, Manual Reactor Scram Due to Degrading Condenser Vacuum2022-01-12012 January 2022 Manual Reactor Scram Due to Degrading Condenser Vacuum ML21196A4852021-07-16016 July 2021 LER 2-2021-002-00 for Peach Bottom Atomic Power Station, Unit 2, Safety Relief Valve Inoperability Due to Nitrogen Leakage from Braided Hose Wear 05000278/LER-2017-0012017-12-20020 December 2017 Reactor Pressure Boundary Leakage Due to Weld Failure in One-Inch Diameter Instrument Line, LER 17-001-00 for Peach Bottom Atomic Power Station (PBAPS), Unit 3 Regarding Reactor Pressure Boundary Leakage Due to Weld Failure in One-Inch Diameter Instrument Line 05000277/LER-2017-0012017-03-0808 March 2017 Emergency Diesel Generator Exhaust Stacks Nonconforming Design for Tornado Missile Protection, LER 17-001-00 for Peach Bottom Atomic Power Station (PBAPS), Unit 2 Regarding Emergency Diesel Generator Exhaust Stacks Nonconforming Design for Tornado Missile Protection 05000278/LER-2016-0012016-11-22022 November 2016 Leak in High Pressure Coolant Injection Drain Pipe Results in a Loss of Safety Function, LER 16-001-00 for Peach Bottom, Unit 3, Regarding Leak in High Pressure Coolant Injection Drain Pipe Results in a Loss of Safety Function 05000277/LER-2016-0012016-11-11011 November 2016 Leak in High Pressure Service Water Pipe Results in Condition Prohibited by Technical Specifications, LER 16-001-00 for Peach Bottom, Unit 2, Regarding Leak in High Pressure Service Water Pipe Results in Condition Prohibited by Technical Specifications 05000278/LER-2015-0012016-02-26026 February 2016 Loss of High Pressure Coolant Injection System Function as a Result of Failed Flow Controller Signal Converter, LER 15-001-00 for Peach Bottom, Unit 3, Regarding Loss of High Pressure Coolant Injection System Function as a Result of Failed Flow Controller Signal Converter ML13058A0432013-02-22022 February 2013 Submittal of Independent Spent Fuel Storage Installation (ISFSI) Cask Event Report ML1007702362010-03-12012 March 2010 60-Day Security Event Report 2-10-S01 ML0927401622009-09-30030 September 2009 LER 09-S01-00 for Peach Bottom, Units 2 & 3 Regarding Unescorted Access Granted to Contract Worker Who Did Not Provide Complete Work History Information ML1015505682009-07-10010 July 2009 Event Notification for Peach Bottom on Elevated Tritium Levels Found in On-Site Well ML0434503772004-12-10010 December 2004 LER-04-S01-00 for Peach Bottom Atomic Power Station (PBAPS) Unit 2 and Unit 3, 60 Day Security Event Report 2-04-S01 ML19095A7391976-12-0505 December 1976 Reporting Abnormal Occurrence No. 50-278-74-33 at Peach Bottom Atomic Power Station for Failure of Main Steam Line High Flow Switch dPIS-3-2-116C to Trip During Surveillance Test 2024-09-05
[Table view] |
LER-2023-001, Standby Liquid Control Pump Inoperable for Greater than LCO Window Due to Gas Intrusion |
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_,,,,, _,,,,,
~,1c Constellation.
10 CFR 50.73 CCN : 23-78
November 7, 2023
U.S. Nuclear Regulatory Commission ATTN : Document Control Desk Washington, DC 20555-0001
Peach Bottom Atomic Power Station (PBAPS) Unit 3 Subsequent Renewed Facility Operating License No. DPR-56 NRC Docket No. 50 - 278
Subject: Licensee Event Report (LER) 2023-001-00 Standby Liquid Control Pump Inoperable for Greater than LCO Window due to Gas Intrusion
The subject report is being submitted in accordance with 50.73(a)(2)(i)(B) for any operation or condition which was prohibited by the plant's Technical Specifications.
There are no commitments contained in this letter. If you have any questions, please contact the Peach Bottom Regulatory Assurance Manager, Mr. Wade Scott at (717) 456-304 7.
Respectfully, 4-,r:2-Jeremy C. Searer Acting Plant Manager Peach Bottom Atomic Power Station
Enclosure
cc : USNRC, Administrator, Region I USNRC, Senior Resident Inspector W. DeHaas, Commonwealth of Pennsylvania S. Seaman, State of Maryland B. Watkins, PSE&G, Financial Controls and Co-Owner Affairs
Abstract
On September 9, 2023, during performance of a functional test, the Unit 3 B Standby Liquid Control Pump did not produce discharge pressure. The pump was declared inoperable and Technical Specification Limiting Condition for Operation (LCO) 3.1.7 Condition B was entered. Troubleshooting identified that the pump and part of the discharge piping was not sufficiently filled with water. The most likely source of gas intrusion was the nitrogen filled accumulator located on the discharge piping between the pump and the discharge check valve. The piping was refilled and the accumulator was replaced, after which the pump was run successfully. The system was restored to operable and the LCO was exited on September 12, 2023. The gas leakage rate was slow and therefore, the system was likely inoperable longer than the LCO-allowed outage time (i.e., 7 days).
Therefore, the condition is being reported under 10CFR 50.73(a)(2)(i)(B). There were no other systems which were inoperable during this identified condition that contributed to this event. There were no actual safety consequences as a result of this event.
Event Description
On September 9, 2023, during performance of a functional test, the Unit 3 B Standby Liquid Control (SLC, EIIS: BR) Pump (EIIS: P) did not produce discharge pressure. T he pump was declared inoperable and Technical Specifications (TS) Limiting Condition for Operation (LCO) 3.1.7 Condition B was entered at 20:32 hours. Troubleshooting identified that the pump and part of the discharge piping was not sufficiently filled with water. The most likely source of gas intrusion was a leaking bladder inside the pneumatic-hydraulic accumulator (EIIS: ACC). The device is installed on the piping near the SLC pump discharge relief valve to dampen pulsations from the pumps to protect the system piping. Nominal accumulator pressure is between 325 psig and 450 psig. The accumulator bladder was replaced, a fter which the pump and discharge piping were filled and the pump was run successfully. The system was restored to operable and the LCO was exited on September 12, 2023 at 17:39 hours.
At the time of discovery, Unit 3 was operating in MODE 1 at approximately 91% power, due to end-of-cycle coast down.
Peach Bottom TS LCO 3.1.7 Required Action B.1 requires that a S LC subsystem be restored to operable status within 7 days or in accordance with the Risk Informed Co mpletion Time Program. If this action is not met, the plant is required to be in MODE 3 within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and MODE 4 within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.
The most likely cause of the condition is gas leakage through the accumulator bladder. The estimated leak rate was small, because no visible sources of leakage were foun d on the accumulator bladder and the rate of pressure decay within the accumulator was slow. Failure analys is is being performed on the bladder, but at this time, the exact cause of the leakage is unknown. The 3B S LC subsystem was last run successfully on May 29, 2023. Trending of available accumulator pressure data did not provide a conclusive time of failure.
Due to the slow nature of the leakage and the volume of gas intrusion present, it is highly likely that the condition existed longer than the LCO-allowed outage time.
Since the 3B train of SLC was likely inoperable for greater than the LCO-allowed outage time, this condition is being reported under 10CFR 50.73(a)(2)(i)(B).
The Energy Industry Identification System component function identifier and name of each component or system:
EIIS: Standby Liquid Control System, BR 3BT076, Standby Liquid Control N2 Accumulator Manufacturer: Greer Hydraulics, Inc Model: A68514-200
Safety Consequences
The SLC System is designed to provide the capability of bringin g the reactor, at any time in a fuel cycle, from full power and minimum control rod inventory (which is at the p eak of the xenon transient) to a subcritical condition with the reactor in the most reactive, xenon free state without taking credit for control rod movement.
The SLC System satisfies the requirements of 10 CFR 50.62 on an ticipated transient without scram using highly enriched boron. The SLC System is also used to maintain suppression pool pH at or above 7 following
a loss of coolant accident (LOCA) involving significant fission product releases. The SLC system consists of two redundant trains, either of which is sufficient to perform its safety function.
There were no other systems which were inoperable during this identified condition. The 3A SLC train demonstrated full functional capability by performance of a surveillance test on September 3, 2023. There were no actual safety consequences as a result of this event, b ecause the redundant train maintained operability.
Corrective Actions
The Unit 3 B SLC accumulator bladder was replaced to restore the subsystem to full function. Investigation into the cause of the bladder leakage is ongoing. If the results of this investigation substantially change the assessment of this condition or planned corrective actions, a s upplement to this LER will be submitted.
The remaining SLC discharge lines (2A, 2B, and 3A) were examine d by ultrasonic testing on October 9, 2023.
All three discharge lines contained gas voids, which were significantly less than what was discovered on the 3B line. None of the discovered gas voids extended to the pump casings or internals. The 3A pump was operated with gas voids present, successfully demonstrating tha t this volume of gas intrusion posed no adverse impact to the pump function. The 3B pump was also examined at this time, and the piping was full of water. The SLC pump discharge process piping will be periodica lly monitored until replacement accumulator bladders can be procured and installed.
Previous Similar Events
Peach Bottom has not previously experienced a failure of a SLC system accumulator bladder that adversely impacted pump performance.