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Category:Letter
MONTHYEARML24313A1012024-11-13013 November 2024 SLRA Supplemental Environmental Audit Plan ML24310A2832024-11-0404 November 2024 Issuance of the Core Operating Limits Report for Reload 25, Cycle 26 IR 05000277/20240032024-11-0404 November 2024 Integrated Inspection Report 05000277/2024003 and 05000278/2024003 ML24317A1432024-11-0404 November 2024 Constellation Energy Generation, LLC, 2024 Annual Report - Guarantees of Payment of Deferred Premiums 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 05000277/20240022024-09-0404 September 2024 Reissued Integrated Inspection Report 05000277/2024002 and 05000278/2024002 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) IR 05000277/20240102024-08-23023 August 2024 Fire Protection Team Inspection Report 05000277/2024010 and 05000278/2024010 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 ML24227A5492024-08-14014 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 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 05000277/LER-2021-001, High Pressure Coolant Injection System Declared Inoperable Due to Instrument Power Inverter Failure2021-06-24024 June 2021 High Pressure Coolant Injection System Declared Inoperable Due to Instrument Power Inverter Failure 05000277/LER-2020-002, Degraded Condition Due to RPV Instrument Nozzle Leakage2020-12-22022 December 2020 Degraded Condition Due to RPV Instrument Nozzle Leakage 05000277/LER-2020-001, Emergency Diesel Generator Shutdown Due to Intercooler Low Pressure Results in Condition Prohibited by Technical Specifications2020-04-24024 April 2020 Emergency Diesel Generator Shutdown Due to Intercooler Low Pressure Results in Condition Prohibited by Technical Specifications 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-2023-002, Main Steam Isolation Valves Stroke Times Exceed Technical Specification Limit |
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10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications |
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10 CFR 50.73 CCN: 23-97 December 14, 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) 2023-002-00 Main Steam Isolation Valves Stroke Times Exceed Technical Specification Limit 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 plants 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) 456-3047.
Respectfully, Ryan C. Stiltner 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 Stiltner, Ryan C Digitally signed by Stiltner, Ryan C
Date: 2023.12.14 12:40:36 -05'00'
Abstract
On October 16, 2023, during performance of a surveillance test while beginning a refueling outage, the stroke times of Main Steam Isolation Valves (MSIVs) exceeded the Technical Specifications limit of five (5) seconds. The apparent causes attributed to two (2) of the MSIVs had the potential to exist during the previous operating cycle. Therefore, the two (2) MSIVs are being reported under 10CFR50.73(a)(2)(i)(B) as a condition prohibited by Technical Specifications because the apparent causes had the potential to have existed longer than allowed by Technical Specifications.
The condition was corrected and the valves were returned to satisfactory performance by adjusting the dashpots and exhaust restrictors as needed. There were no safety consequences associated with this condition, as the valve stroke times did not exceed the times considered in the safety analysis.
(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.gov/reading-rm/doc-collections/nuregs/staff/sr1022/r3/) Page 3 of 3 The Energy Industry Identification System component function identifier and name of each component or system:
EIIS: Main Steam, SB AO-3-01A-086A, A Main Steam Line Outboard Isolation Valve AO-3-01A-080B, B Main Steam Line Inboard Isolation Valve Manufacturer: Atwood and Morrill Model: 20851-H Safety Consequences The Technical Specification Surveillance Requirement (SR) 3.6.1.3.9 requires the MSIVs to close within 3 to 5 seconds. The Updated Final Safety Analysis Report (UFSAR) conservatively utilizes a maximum valve closure time of 10 seconds for analyses where the loss of reactor coolant inventory is the controlling variable, which provides conservatism between the SR and the analyzed performance. The observed stroke times for the noted MSIVs were no greater than 6.2 seconds. Therefore, the stroke times observed were not outside the bounds of the analyses and the safety function was maintained. There were no actual or potential safety consequences as a result of this event because this issue was identified during testing and the MSIVs closed within their analyzed times.
Since the remaining MSIVs closed satisfactorily, the overall containment isolation function would have been accomplished in 5.1 seconds.
Corrective Actions This condition was corrected by performing follow up stroke timing for each MSIV and making adjustments such as dashpot and exhaust restrictor tuning as required to return the valves to desired performance.
The valve performance has been entered into the Corrective Action Program for further evaluation of the test performance and evaluation methodology.
Previous Similar Events Peach Bottom Unit 3 LER 3-2009-007: An MSIV stroked below the minimum allowable stroke time due to dashpot oil leakage.
Peach Bottom Unit 3 LER 3-1998-003: An MSIV stroked outside the acceptance range.
Peach Bottom Unit 2 LER 2-1983-025: An MSIV stroked above the maximum allowable stroke time due to insufficient flow through the dashpot needle valve.