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Category:Letter
MONTHYEARML25031A0592025-01-31031 January 2025 Annual Commitment Revision Report for the Period 01/01/24 Through 12/31/24 ML25024A1482025-01-24024 January 2025 Request for Exemption from Certain Requirements of 10 CFR 72.212 and 10 CFR 72.214 RS-25-001, Subsequent License Renewal Environmental Review, Response to NRC Requests for Confirmation of Information (Rcis) and Request for Additional Information (RAI)2025-01-21021 January 2025 Subsequent License Renewal Environmental Review, Response to NRC Requests for Confirmation of Information (Rcis) and Request for Additional Information (RAI) ML24353A1372025-01-15015 January 2025 Proprietary Determination Constellation Energy Generation, LLC 2024 Deferred Premiums ML25013A0642025-01-13013 January 2025 Requalification Program Inspection ML25010A1502025-01-10010 January 2025 Notification of Commercial Grade Dedication Inspection (05000277/2025011 and 05000278/2025011) and Request for Information IR 05000171/20230012025-01-0707 January 2025 Constellation Energy Generation, LLC, Peach Bottom Atomic Power Station Unit 1 - NRC Inspection Report No. 05000171/2023001 ML25006A0942025-01-0606 January 2025 (Wcgs), Revision of One Form That Implements the Radiological Emergency Response Plan (RERP) ML24324A3312024-12-23023 December 2024 Exemption from the Requirements of 10 CFR Part 50, Sections 50.82(a)(8)(1)(A) and 50.75(h)(1)(iv) (EPID L-2024-LLE-0018) (Ltr) ML24344A2742024-12-19019 December 2024 Alternative Request to Use American Society of Mechanical Engineers Boiler and Pressure Vessel Code Case OMN-32 ML24339B7292024-12-18018 December 2024 Amd - Constellation - Adoption of TSTF-591 ML24317A2472024-12-16016 December 2024 Environmental Assessment and Finding of No Significant Impact Related to Exemption from the Requirements of 10 CFR Part 50 (Letter) ML24344A1102024-12-13013 December 2024 Suppl Env Audit Summary Letter ML24347A0122024-12-12012 December 2024 Revision of One Form That Implements the Radiological Emergency Response Plan (RERP) ML24331A2592024-11-27027 November 2024 Reassignment of the U.S. Nuclear Regulatory Commission Branch Chief in the Division of Operating Reactor Licensing for Plant Licensing Branch III ML24331A2792024-11-26026 November 2024 Supplement to 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 - Revise LaSalle, Units 1 and 2 Technical Specificati ML24327A1642024-11-22022 November 2024 Fws to NRC, Federal Agency Coordination Under ESA Section 7 for Peach Bottom SLR and Concurrence with Not Likely to Adversely Affect Finding for Northern long-eared and Tricolored Bats ML24327A1652024-11-22022 November 2024 Fws to NRC, List of Threatened and Endangered Species That May Occur in Your Proposed Project Location or May Be Affected by Peach Bottom SLR ML24319A0752024-11-14014 November 2024 Additional Information Report for the Peach Bottom Atomic Power Station Units 2 and 3 Subsequent License Renewal Environmental Review ML24313A1012024-11-13013 November 2024 SLRA Supplemental Environmental Audit Plan ML24317A1432024-11-0404 November 2024 Constellation Energy Generation, LLC, 2024 Annual Report - Guarantees of Payment of Deferred Premiums 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 IR 05000277/20244012024-10-17017 October 2024 Security Baseline Inspection Report 05000277/2024401 and 05000278/2024401 (Cover Letter Only) 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 ML24255A8642024-09-0606 September 2024 Rscc Wire & Cable LLC Dba Marmon Industrial Energy & Infrastructure - Part 21 Retraction of Final Notification 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 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) 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 05000482/20240052024-08-14014 August 2024 Updated Inspection Plan for Wolf Creek Generating Station (Report 05000482/2024005) ML24227A5492024-08-14014 August 2024 Integrated Inspection Report 05000277/2024002 and 05000278/2024002 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 ML24178A3672024-06-26026 June 2024 Correction to 2023 Annual Radioactive Effluent Release Report – Report 47 ML24178A4142024-06-26026 June 2024 Revision of One Procedure and One Form That Implement the Radiological Emergency Response Plan (RERP) 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 2025-01-07
[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-2019-001, Failure of Reactor Mode Switch Results in Condition Prohibited by Technical Specifications2019-12-19019 December 2019 Failure of Reactor Mode Switch Results in Condition Prohibited by Technical Specifications 05000277/LER-2019-001, Regarding Emergency Bus Breaker Relay Failure Results in Loss of Safety Function2019-04-11011 April 2019 Regarding Emergency Bus Breaker Relay Failure Results in Loss of Safety Function 05000277/LER-2018-002-01, Emergency Diesel Generator Air Inlet Check Valve Failure Results in a Condition Prohibited by Technical Specifications2019-03-0404 March 2019 Emergency Diesel Generator Air Inlet Check Valve Failure Results in a Condition Prohibited by Technical Specifications 05000278/LER-2018-002-01, Reactor Coolant System Pressure Boundary Leakage Resulting in Technical Specification Required Shutdown2018-12-21021 December 2018 Reactor Coolant System Pressure Boundary Leakage Resulting in Technical Specification Required Shutdown 05000278/LER-2018-004, Failure of a Main Steam Isolation Valve to Fully Close2018-11-30030 November 2018 Failure of a Main Steam Isolation Valve to Fully Close 05000278/LER-2018-003, Automatic Reactor Scram Due to Loss of Two Condensate Pumps2018-11-29029 November 2018 Automatic Reactor Scram Due to Loss of Two Condensate Pumps 05000278/LER-2018-002, Reactor Coolant System Pressure Boundary Leakage Resulting in Technical Specification Required Shutdown2018-11-19019 November 2018 Reactor Coolant System Pressure Boundary Leakage Resulting in Technical Specification Required Shutdown 05000277/LER-2018-002, Unit 3, Emergency Diesel Generator Air Inlet Check Valve Failure Results in a Condition Prohibited by Technical Specifications2018-08-10010 August 2018 Unit 3, Emergency Diesel Generator Air Inlet Check Valve Failure Results in a Condition Prohibited by Technical Specifications 05000278/LER-2018-001, Reactor Core Isolation Cooling System Pressure Switch Failure Results in Condition Prohibited by TS2018-06-21021 June 2018 Reactor Core Isolation Cooling System Pressure Switch Failure Results in Condition Prohibited by TS 05000277/LER-2018-001, Fire Safe Shutdown Requirements Not Met for Spurious Operation of Valves at a High-Low Pressure Interface2018-05-11011 May 2018 Fire Safe Shutdown Requirements Not Met for Spurious Operation of Valves at a High-Low Pressure Interface 05000278/LER-1917-001, Regarding Reactor Pressure Boundary Leakage Due to Weld Failure in One-Inch Diameter Instrument Line2017-12-20020 December 2017 Regarding Reactor Pressure Boundary Leakage Due to Weld Failure in One-Inch Diameter Instrument Line 05000277/LER-2017-001, Regarding Emergency Diesel Generator Exhaust Stacks Nonconforming Design for Tornado Missile Protection2017-03-0808 March 2017 Regarding Emergency Diesel Generator Exhaust Stacks Nonconforming Design for Tornado Missile Protection 05000278/LER-2016-001, Regarding Leak in High Pressure Coolant Injection Drain Pipe Results in a Loss of Safety Function2016-11-22022 November 2016 Regarding Leak in High Pressure Coolant Injection Drain Pipe Results in a Loss of Safety Function 05000277/LER-2016-001, Regarding Leak in High Pressure Service Water Pipe Results in Condition Prohibited by Technical Specifications2016-11-11011 November 2016 Regarding Leak in High Pressure Service Water Pipe Results in Condition Prohibited by Technical Specifications 05000278/LER-2015-001, Regarding Loss of High Pressure Coolant Injection System Function as a Result of Failed Flow Controller Signal Converter2016-02-26026 February 2016 Regarding Loss of High Pressure Coolant Injection System Function as a Result of Failed Flow Controller Signal Converter 05000277/LER-2015-001, Regarding Condition Prohibited by Technical Specification Due to Insufficient Remote Shutdown System Surveillance Testing2015-10-20020 October 2015 Regarding Condition Prohibited by Technical Specification Due to Insufficient Remote Shutdown System Surveillance Testing 05000277/LER-2014-003, Regarding Containment Leakage Limit Exceeded Due to Through-Seat Leakage of Feed Water Check Valves2014-12-0505 December 2014 Regarding Containment Leakage Limit Exceeded Due to Through-Seat Leakage of Feed Water Check Valves 05000277/LER-2014-001, Regarding Unanalyzed Condition Due to Broken Wires in Breakers Used for Appendix R Post-Fire Safe Shutdown2014-07-17017 July 2014 Regarding Unanalyzed Condition Due to Broken Wires in Breakers Used for Appendix R Post-Fire Safe Shutdown 05000278/LER-2013-001, Re Laboratory Analysis Identifies Safety Relief Valves and Safety Valve Set Point Deficiencies2013-11-22022 November 2013 Re Laboratory Analysis Identifies Safety Relief Valves and Safety Valve Set Point Deficiencies ML13058A0432013-02-22022 February 2013 Submittal of Independent Spent Fuel Storage Installation (ISFSI) Cask Event Report 05000278/LER-2012-003, Regarding Loss of Control Room Emergency Ventilation Function Due to Failure of Ventilation Fan to Start2012-11-29029 November 2012 Regarding Loss of Control Room Emergency Ventilation Function Due to Failure of Ventilation Fan to Start 05000277/LER-2012-002, Regarding Common Cause Inoperability of Reactor Protection System Turbine Control Valve Instruments2012-11-21021 November 2012 Regarding Common Cause Inoperability of Reactor Protection System Turbine Control Valve Instruments 05000277/LER-2012-001, Regarding Laboratory Analysis Identities Safety Relief Valves and Safety Valve Set Point Deficiencies2012-11-0202 November 2012 Regarding Laboratory Analysis Identities Safety Relief Valves and Safety Valve Set Point Deficiencies 05000278/LER-2012-002, Regarding Failure of Primary Containment Isolation Valve Due to Foreign Material Results in Condition Prohibited by TS2012-08-22022 August 2012 Regarding Failure of Primary Containment Isolation Valve Due to Foreign Material Results in Condition Prohibited by TS 05000278/LER-2012-001, For Peach Bottom Atomic, Unit 3 Regarding Concurrent Inoperability of Two Trains of Core Spray Pressure Switches Results in Condition Prohibited by TS2012-06-13013 June 2012 For Peach Bottom Atomic, Unit 3 Regarding Concurrent Inoperability of Two Trains of Core Spray Pressure Switches Results in Condition Prohibited by TS 05000278/LER-2011-004, Regarding HPCI Cable Routing Error Results in Degraded Post Fire Safe Shutdown (Fssd) Analysis2012-01-13013 January 2012 Regarding HPCI Cable Routing Error Results in Degraded Post Fire Safe Shutdown (Fssd) Analysis 05000277/LER-2011-005, For Peach Bottom, Unit 2, Regarding Inoperability of Qualified Offsite Power Circuit Due to Design Weakness2011-12-15015 December 2011 For Peach Bottom, Unit 2, Regarding Inoperability of Qualified Offsite Power Circuit Due to Design Weakness 05000278/LER-2011-001, Regarding Containment Isolation Valve Inability to Close for a Design Basis Event Due to Degraded Lubricant2011-12-0909 December 2011 Regarding Containment Isolation Valve Inability to Close for a Design Basis Event Due to Degraded Lubricant 05000277/LER-2011-004, For Peach Bottom, Unit 2, Regarding Oil Leak Resulting in E1 Emergency Diesel Generator Inoperability2011-11-22022 November 2011 For Peach Bottom, Unit 2, Regarding Oil Leak Resulting in E1 Emergency Diesel Generator Inoperability 05000278/LER-2011-003, For Peach Bottom Unit 3, Regarding Automatic Depressurization System Safety Relief Valve Actuator Diaphragm Thread Seal Leak2011-11-18018 November 2011 For Peach Bottom Unit 3, Regarding Automatic Depressurization System Safety Relief Valve Actuator Diaphragm Thread Seal Leak 05000278/LER-2011-002, For Peach Bottom Unit 3 - Residual Heat Removal Leaking Relief Valve Results in Condition Prohibited by Technical Specifications2011-11-17017 November 2011 For Peach Bottom Unit 3 - Residual Heat Removal Leaking Relief Valve Results in Condition Prohibited by Technical Specifications 05000277/LER-2011-003, Regarding Delayed Relay Operation Results in E-3 Emergency Diesel Generator Actuation During Surveillance Testing2011-10-21021 October 2011 Regarding Delayed Relay Operation Results in E-3 Emergency Diesel Generator Actuation During Surveillance Testing 05000277/LER-2011-002, For Peach Bottom, Units 2 and 3 - Condition Prohibited by Technical Specifications Due to Degraded Spent Fuel Pool Racks Boraflex Panels2011-07-29029 July 2011 For Peach Bottom, Units 2 and 3 - Condition Prohibited by Technical Specifications Due to Degraded Spent Fuel Pool Racks Boraflex Panels 05000277/LER-2011-001, For Peach Bottom Unit 2 High Pressure Coolant System Inoperable Due to Leaking Cooling Water Header Relief Valve2011-05-0606 May 2011 For Peach Bottom Unit 2 High Pressure Coolant System Inoperable Due to Leaking Cooling Water Header Relief Valve 05000277/LER-2010-004, Regarding Improper Credit for Function of Off-Site Power Source Transformer Load Tap Changer2010-11-24024 November 2010 Regarding Improper Credit for Function of Off-Site Power Source Transformer Load Tap Changer 05000277/LER-2010-003, Regarding Laboratory Analysis Identifies Safety Relief Valves and Safety Valve Set Point Deficiencies2010-11-19019 November 2010 Regarding Laboratory Analysis Identifies Safety Relief Valves and Safety Valve Set Point Deficiencies 05000277/LER-2010-002, Regarding Improperly Fastened Rod Hanger Results in Inoperable Subsystem of Emergency Service Water2010-11-15015 November 2010 Regarding Improperly Fastened Rod Hanger Results in Inoperable Subsystem of Emergency Service Water 05000277/LER-2010-001, Regarding Multiple Slow Control Rods Results in Condition Prohibited by Technical Specifications2010-03-19019 March 2010 Regarding Multiple Slow Control Rods Results in Condition Prohibited by Technical Specifications 2024-09-05
[Table view] |
LER-2016-001, Regarding Leak in High Pressure Service Water Pipe Results in Condition Prohibited by Technical Specifications |
Event date: |
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Report date: |
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Reporting criterion: |
10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded
10 CFR 50.73(a)(2)(viii)(A)
10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition
10 CFR 50.73(a)(2)(ix)(A)
10 CFR 50.73(a)(2)(iv)(A), System Actuation
10 CFR 50.73(a)(2)(x)
10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor
10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat
10 CFR 50.73(a)(2)(v), Loss of Safety Function
10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown
10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
10 CFR 50.73(a)(2)(vii), Common Cause Inoperability
10 CFR 50.73(a)(2)(i) |
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2772016001R00 - NRC Website |
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text
Exelon Generation November 11, 2016 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001
Subject:
Peach Bottom Atomic Power Station (PBAPS) Unit 2 Renewed Facility Operating License No. DPR-44 NRC Docket No. 50-277 Licensee Event Report (LER) 2-16-001 10CFR 50.73 Enclosed is a Licensee Event Report concerning a condition prohibited by Technical Specifications (TS) resulting from a pipe leak in the High Pressure Service Water system. In accordance with NEI 99-04, the regulatory commitment contained in this correspondence is to restore compliance with the regulations. The specific methods that have been planned to restore and maintain compliance are discussed in the LER. If you have any questions or require additional information, please do not hesitate to contact Jim Armstrong, Site Regulatory Assurance Manager, at 717-456-3351.
Sincer;;~
Patrick D. Navin Plant Manager Peach Bottom Atomic Power Station PDN/dnd/IR 2704854 Attachment cc:
US NRC, Administrator, Region I US NRC, Senior Resident Inspector R. R. Janati, Commonwealth of Pennsylvania S. Gray, State of Maryland B. Watkins, PSE&G, Financial Controls and Co-owner Affairs CCN: 16-102
NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB: NO. 3150-0104 EXPIRES: 10/31/2018 (06-2016)
Estimaled burden per response to comply with this mandatory collection request: 80 hours9.259259e-4 days <br />0.0222 hours <br />1.322751e-4 weeks <br />3.044e-5 months <br />.
/¥\\
Reported lessons learned are incorporated into the licensing process and fed back to industry.
LICENSEE EVENT REPORT (LER)
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
- ~
rfl (See Page 2 for required number of digits/characters for each block}
to lnfocollects.Resource@nrc.gov, and to the Desk Officer, Office of lnfomnation and Regulatory Affairs, NEOB-10202, (3150-0104), Office of Management and Budget, Washington, DC 20503. If a (See NUREG-1022, R.3 for instruction and guidance for completing this form means used to impose an infomnation collection does not display a currently valid OMB control htli;i://www.nrc.gov/reading-rm/doc-i;;ollections/nuregs/staff/sr1022/r3/)
number, the NRC may not conduct or sponsor, and a person is not required to respond to, the infomnation collection.
- 3. PAGE Peach Bottom Atomic Power Station Unit 2 05000277 1 OF 4
- 4. TITLE Leak in High Pressure Service Water Pipe Results in Condition Prohibited by Technical Specifications
- 5. EVENT DATE
- 6. LER NUMBER
- 7. REPORT DATE
- 8. OTHER FACILITIES INVOLVED YEAR I SEQUENTIAL I REV FACILITY NAME DOCKET NUMBER MONTH DAY YEAR NUMBER NO.
MONTH DAY YEAR Peach Bottom APS Unit 3 05000278 FACILITY NAME DOCKET NUMBER 09 12 16 2016 - 001 0
11 11 16
- 9. OPERATING MODE
- 11. THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR §: (Check all that apply)
D 20:2201(b)
D 20.2203(a)(3)(i)
D 50.73(a)(2)(ii)(A)
D 50.73(a)(2)(viii)(A) 1 D
20.2201(d)
D 20.2203(a)(3)(iiJ D
50.73(a)(2)(ii)(B)
D
- 50. 73(a)(2)(viii)(B)
D 20.2203(a)(1)
D 20.2203(a)(4)
D so.13(a)(2)(iii)
D 50.73(a)(2)(ix)(A)
D 20.2203(a)(2)(i)
D 50.36(c)(1)(i)(A)
D 50.73(a)(2)(iv)(A)
D 50.73(a)(2)(x)
- 10. POWER LEVEL D
20.2203(a)(2)(ii)
D 50.36(c)(1 )(ii)(A)
D 50.73(a)(2)(v)(A)
D 13.11(a)(4)
D 20.2203(a)(2)(iii)
D so.3a(c)(2)
D 50.73(a)(2)(v)(B)
D 13.11(a)(s)
D 20.2203(a)(2)(iv)
D so.4a(a)(3)(ii)
D 50.73(a)(2)(v)(C)
D 13.77(a)(1) 100%
D 20.2203(a)(2)(v)
D 50.73(a)(2)(i)(A)
D 50.73(a)(2)(v)(D)
D 73.77(a)(2)(i)
D 20.2203(a)(2)(vi)
~ 50.73(a)(2)(i)(B)
D 50.73(a)(2)(vii)
D 73.77(a)(2)(ii)
D 50.73(a)(2)(i)(C)
D OTHER Specify in Abstract below or in SEQUENTIAL NUMBER 001 REV NO.
0 The emergency heat sink per TS 3.7.3.B due to potential for loss of inventory (applies to both Units 2 and 3)
The pipe was replaced and the affected equipment was restored to an operable status on 8/18/16 at 0610 hours0.00706 days <br />0.169 hours <br />0.00101 weeks <br />2.32105e-4 months <br />. The elapsed time from the discovery of the failure to when the equipment was returned to service was approximately 45 hours5.208333e-4 days <br />0.0125 hours <br />7.440476e-5 weeks <br />1.71225e-5 months <br /> and 40 minutes.
Analysis of the Event
Initial evaluation of the flaw could not determine if the pipe would have failed during a seismic event.
More detailed modeling of the pipe from its connection on the 18" diameter HPSW line to the first anchor point on the wall determined that seismic stresses could have caused the crack to propagate and result in a complete fracture of the pipe. This conclusion was reached on 9/12/16 and is considered to be the time at which a reportable event was identified. It is unknown at what time the crack developed into the as-tound condition, however it is likely that it existed for a period of time greater than the TS required completion time for the systems to be restored to an operable status (7 days for each condition). Since the condition existed for a period of time longer than the TS required completion time, the condition resulted in a condition prohibited by TS and is being reported pursuant to 10CFR 50.73(a)(2)(i)(B).
Cause of the Event
To determine the cause of the crack, the section of the pipe and the socket weld were sent to an off-site lab for failure analysis. The cracking initiated at the toe of the weld on the outer diameter of the pipe and propagated in one general direction through the pipe wall. The fracture surface was examined by scanning electron microscopy and had transgranular features which are typical of fatigue. There were no material anomalies at the fracture origins and the weld appeared to be of generally good quality. The analysis concluded that the leak was caused by fatigue cracking caused by cyclic loading conditions, such as vibration.
The pipe was anchored to the wall a short distance from its connection to the 18" diameter HPSW line.
This design did not adequately account for vibration in the HPSW line, which resulted in bending stresses in the 1" pipe at the toe of the fillet weld connection to the half coupling. In addition, a 2: 1 weld was not used with the socket weld. The current standard for fillet welds on small bore piping subject to vibration is to use a weld with a length to depth ratio of 2:1 in order to mitigate stress from vibration. A contributing cause is that the pipe appeared to have been slightly distorted in the downward direction.
Corrective Actions
The pipe was replaced between the 18" HPSW pipe and the first valve. A 2: 1 weld was utilized at the socket to mitigate vibration impacts. The configuration of the 1" pipe is used at a total of 16 locations at the plant for the supply and return lines for radiation monitors for the HPSW system. All were visually inspected to determine if similar flaws existed on the other lines. No flaws were identified. Non-YEAR 2016 SEQUENTIAL NUMBER 001 destructive examinations have been scheduled to obtain additional information on the condition of the piping.
Previous Similar Occurrences REV NO.
0 Since the modification in 1994 that installed the radiation monitors and associated piping, there have been no other documented cases of leakage from this piping. Page _4_ of ___!_
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05000278/LER-2016-001, Regarding Leak in High Pressure Coolant Injection Drain Pipe Results in a Loss of Safety Function | Regarding Leak in High Pressure Coolant Injection Drain Pipe Results in a Loss of Safety Function | 10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown 10 CFR 50.73(a)(2)(ix)(A), Prevented Safety Function in Multiple System 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) | 05000277/LER-2016-001, Regarding Leak in High Pressure Service Water Pipe Results in Condition Prohibited by Technical Specifications | Regarding Leak in High Pressure Service Water Pipe Results in Condition Prohibited by Technical Specifications | 10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown 10 CFR 50.73(a)(2)(ix)(A), Prevented Safety Function in Multiple System 10 CFR 50.73(a)(2)(viii)(A) |
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