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Category:Letter
MONTHYEARML24291A0012024-10-17017 October 2024 Submittal of Core Operating Limits Report, Cycle 25 RS-24-095, Relief Request I4R-19 and I4R-26, Associated with the Fourth and Fifth Inservice Inspection Intervals2024-10-10010 October 2024 Relief Request I4R-19 and I4R-26, Associated with the Fourth and Fifth Inservice Inspection Intervals 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 ML24275A2442024-10-0303 October 2024 Reassignment of the U.S. Nuclear Regulatory Commission Branch Chief, Division of Operating Reactor Licensing ML24263A1272024-09-23023 September 2024 – Request for Additional Information (EPID 2023-LLA-0136) - Non-Proprietary IR 05000456/20240112024-09-12012 September 2024 Biennial Problem Identification and Resolution Inspection Report 05000456/2024011 and 05000457/2024011 ML24164A0032024-09-10010 September 2024 Issuance of Amendment Nos. 235 and 235 Revision of Technical Specifications for the Ultimate Heat Sink IR 05000456/20240052024-08-29029 August 2024 Updated Inspection Plan and Assessment Follow-Up Letter for Braidwood Station, Units 1 and 2 (Report 05000456/2024005 and 05000457/2024005) ML24227A0522024-08-29029 August 2024 Audit Plan for LAR to Remove ATWS Mtc Limit ML24225A1112024-08-13013 August 2024 Notification of NRC Fire Protection Team Inspection Request for Information 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 IR 05000456/20240022024-08-0808 August 2024 Integrated Inspection Report 05000456/2024002 and 05000457/2024002 ML24172A1252024-07-26026 July 2024 Environmental Assessment and Finding of No Significant Impact Related to a Requested Increase in Ultimate Heat Sink Temperature (EPID L-2024-LLA-0075) - Transmittal Letter ML24179A3262024-07-23023 July 2024 LTR - Constellation - SG Welds and Nozzles (L-2023-LLR-0053, L-2023-LLR-0054, L-2023-LLR-0055, L-2023-LLR-0056) 05000456/LER-2024-001, Submittal of LER 2024-001-00 for Braidwood Station, Unit 1, Trip on Low Steam Generator Level Due to Failure to Verify Isolation Valves Were Open2024-07-0303 July 2024 Submittal of LER 2024-001-00 for Braidwood Station, Unit 1, Trip on Low Steam Generator Level Due to Failure to Verify Isolation Valves Were Open ML24163A3922024-06-25025 June 2024 Individual Notice of Consideration of Issuance of Amendments to Renewed Facility Operating Licenses, Proposed No Significant Hazards Consideration Determination, & Opportunity for a Hearing (EPID L-2024-LLA-0075)- Letter 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 ML24164A2132024-06-13013 June 2024 Information Request to Support Upcoming Problem Identification and Resolution (Pi&R) Inspection at Braidwood Nuclear Plant RS-24-057, License Amendment to Technical Specification 3.7.9, Ultimate Heat Sink2024-06-0404 June 2024 License Amendment to Technical Specification 3.7.9, Ultimate Heat Sink IR 05000456/20240102024-05-31031 May 2024 License Renewal Phase 1 Report 05000456/2024010 RS-24-044, License Amendment to Transition to Framatome Gaia Fuel and Exemptions to 10 CFR 50.46 and 10 CFR 50 Appendix K. Attachments 1 to 11 Enclosed2024-05-28028 May 2024 License Amendment to Transition to Framatome Gaia Fuel and Exemptions to 10 CFR 50.46 and 10 CFR 50 Appendix K. Attachments 1 to 11 Enclosed RS-24-043, Application to Remove Power Distribution Monitoring System (Pdms) Details from Technical Specifications2024-05-24024 May 2024 Application to Remove Power Distribution Monitoring System (Pdms) Details from Technical Specifications ML24079A0762024-05-23023 May 2024 Issuance of Amendments to Adopt TSTF 264 ML24142A3352024-05-21021 May 2024 Quad Cities—Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes RS-24-055, 2023 Corporate Regulatory Commitment Change Summary Report2024-05-17017 May 2024 2023 Corporate Regulatory Commitment Change Summary Report ML24136A0132024-05-15015 May 2024 2023 Annual Radiological Environmental Operating Report ML24136A2452024-05-15015 May 2024 Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000457/2024004 ML24128A1212024-05-0707 May 2024 Response to Braidwood and Dresden FOF Dates Change Request (2025) ML24122A6522024-05-0101 May 2024 Submittal of 2023 Annual Radioactive Effluent Release Report 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 IR 05000456/20243012024-04-29029 April 2024 NRC Initial License Examination Report 05000456/2024301; 05000457/2024301 RS-24-026, License Amendment to Braidwood Station, Units 1 and 2, and Byron Station, Units 1 and 2, Technical Specifications 5.6.5, Core Operating Limits Report (COLR)2024-04-25025 April 2024 License Amendment to Braidwood Station, Units 1 and 2, and Byron Station, Units 1 and 2, Technical Specifications 5.6.5, Core Operating Limits Report (COLR) ML24116A0052024-04-25025 April 2024 Transmittal of Braidwood Station, Unit 1, Core Operating Limits Report, Braidwood Unit 1 Cycle 25 IR 05000456/20240012024-04-24024 April 2024 Integrated Inspection Report 05000456/2024001 and 05000457/2024001 ML24113A1272024-04-22022 April 2024 Audit Plan in Support of Review of LAR Revision of TS 3.7.15, 3.7.16, and 4.3.1 (EPID: L-2023-LLA-0136) (Non-Proprietary) IR 05000457/20240902024-04-19019 April 2024 Final Significance Determination for 2b Auxiliary Feedwater Pump Diesel Engine Fuel Oil Dilution Issue - NRC Inspection Report 05000457/2024090 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 RS-24-034, Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors2024-04-10010 April 2024 Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors ML24094A2692024-04-0303 April 2024 Notification of Deviation from Pressurized Water Reactor Owners Group (PWROG) Report, WCAP-17451-P, Revision 2, Reactor Internals Guide Tube Wear Westinghouse Domestic Fleet Operational Projections 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 ML24057A0372024-03-26026 March 2024 Proposed Alternative from Certain Requirements Contained in the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI RS-24-024, Response to Request for Additional Information Regarding Proposed Alternative for Examination of Pressurizer Circumferential and Longitudinal Shell-to-Head Welds and Nozzle-to-Vessel Welds2024-03-22022 March 2024 Response to Request for Additional Information Regarding Proposed Alternative for Examination of Pressurizer Circumferential and Longitudinal Shell-to-Head Welds and Nozzle-to-Vessel Welds ML24067A3252024-03-0707 March 2024 U.S. Department of Energy, Office of Legacy Management, 2023 Annual Site Inspection and Monitoring Report for Uranium Mill Tailings Radiation Control Act Title I Disposal Sites ML24066A0122024-03-0606 March 2024 Operator Licensing Examination Approval Braidwood Station, Units 1 and 2, March 2024 IR 05000456/20244012024-03-0505 March 2024 Cyber Security Inspection Report 05000456/2024401 and 05000457/2024401 (Public) IR 05000456/20230062024-02-28028 February 2024 Annual Assessment Letter for Braidwood Station, Units 1 and 2 (Report 05000456/2023006 and 05000457/2023006) ML24057A3022024-02-26026 February 2024 Regulatory Conference Supplemental Information ML24047A2382024-02-20020 February 2024 Regulatory Conference to Discuss Risk Associated with 2b Auxiliary Feedwater Pump Diesel Engine Fuel Oil Leak RS-24-013, Response to Request for Additional Information Regarding Proposed Alternative to Distribution Requirements of ASME Code Table IWC-2411-1 for the Steam Generators2024-02-13013 February 2024 Response to Request for Additional Information Regarding Proposed Alternative to Distribution Requirements of ASME Code Table IWC-2411-1 for the Steam Generators IR 05000456/20230042024-02-0202 February 2024 Integrated Inspection Report 05000456/2023004 and 05000457/2023004 2024-09-23
[Table view] Category:Licensee Response to Notice of Violation
MONTHYEARBW240002, Response to Nrg Inspection Report and Preliminary Greater than Green Finding and Apparent Violation2024-02-0202 February 2024 Response to Nrg Inspection Report and Preliminary Greater than Green Finding and Apparent Violation ML13350A3422013-12-13013 December 2013 Reply to Notice of Violation, EA-13-209 IR 05000456/20120042012-12-0707 December 2012 Reply to a Notice of Violation Regarding Inspection Reports 05000456/2012004-03; 05000457/2012004-03 ML12342A4122012-12-0707 December 2012 Reply to a Notice of Violation Regarding Inspection Reports 05000456/2012004-03; 05000457/2012004-03 ML12297A2972012-10-23023 October 2012 Reply to a Notice of Violation; 05000457/2012008-01 ML1108907372011-03-30030 March 2011 Reply to a Notice of Violation; EA-10-220 ML1106200892011-03-0202 March 2011 Response to NRC Verification Inspection Report; 05000456/2011009; 05000457/2011009 ML0620904022006-07-28028 July 2006 Reply to Notice of Violation: EA-06-081 ML0610704972006-02-0202 February 2006 Letter from Keith Poison, Braidwood Station to Beverly Booker, Illinois Environmental Protect Agency ML0617102232005-12-19019 December 2005 NRC Email from Steven Orth to Braidwood Communications Team, Bwd IEPA Violation ML0224603322002-08-22022 August 2002 Reply to a Notice of Violation ML0224000322002-08-19019 August 2002 Revised Response to a Notice of Violation ML0221204842002-07-24024 July 2002 Additional Information Regarding a Reply to a Notice of Violation ML0213502262002-05-0303 May 2002 Follow-up Reply to Notice of Violation ML0203505112002-01-11011 January 2002 Reply to a Notice of Violation 2024-02-02
[Table view] |
Text
December 7,2012 BW120120 U.S. Nuclear Regulatory Commission A TIN: Document Control Desk Washington, D.C. 20555-0001 Subject: Reference:
Braidwood Station, Units 1 and 2 Facility Operating License Nos. NPF-72 and NPF-77 NRC Docket Nos. STN 50-456 and STN 50-457 Reply to a Notice of Violation;05000456/2012004-03; 05000457/2012004-03 Letter from Eric R. Duncan (U.S. NRC) to Michael J. Pacilio (Exelon Generation Company, LLC), "Braidwood Station, Units 1 and 2, Nuclear Regulatory Commission Integrated Inspection Report 05000456/2012004; 05000457/2012004 and Notice of Violation," dated November 8,2012 In the referenced letter, based on the results of an inspection completed on September 30, 2012, the NRC concluded that Braidwood Station was in violation of 10 CFR 50, Appendix B, Criterion III, "Design Control", which requires, in part, that design control measures shall provide for verifying the adequacy of the design, and that the design basis is correctly translated into procedures and instruction The NRC requested Exelon Generation Company, LLC (EGC) to respond to the Notice of Violation within 30 days of the date of the referenced letter. EGC does not contest the violatio Attachment 1 to this letter contains EGC's response to the Notice of Violatio This letter contains new regulatory commitments, which are identified in Attachment 2. If you have any questions regarding this reply, please contact Mr. Chris VanDenburgh, Regulatory Assurance Manager, at (815) 417-280 Daniel J. Enright Site Vice President Braidwood Station Attachments:
1) Reply to Notice of Violation 2) Summary of Regulatory Commitments cc: Regional Administrator
-NRC Region III NRC Senior Resident Inspector
-Braidwood Station ATTACHMENT 1 Reply to Notice of Violation In a letter from Eric R. Duncan (U.S. NRC) to Michael J. Pacilio (Exelon Generation Company, LLC), dated November 8, 2012, the NRC issued a Notice of Violatio The violation of NRC requirements was identified during an NRC inspection completed on September 30, 2012. The violation is listed below: Title 10 of the Code of Federal Regulations Part 50 (10 CFR 50), Appendix B, Criterion III, 'Design Control', requires, in part, that design control measures shall provide for verifying the adequacy of the design, and that the design basis is correctly translated into procedures and instruction Contrary to the above, from initial plant construction to September 30, 2012, the licensee failed to verify the adequacy of the design of the Braidwood Unit 1 and Unit 2 recycle holdup tanks, which are safety-related components subject to the requirements of 10 CFR 50, Appendix B, Criterion III, and failed to correctly translate the design basis of the Braidwood Unit 1 and Unit 2 recycle holdup tanks into procedures and instruction Specifically, the license failed to evaluate the effect of dynamic loads on inlet piping from Unit 1 and Unit 2 residual heat removal system suction relief valves that discharge to the recycle holdup tanks and, as a result, failed to verify the adequacy of the recycle holdup tank design to withstand design loads that would result from a discharge of residual heat removal system suction relief valves into the recycle holdup tanks. This violation is associated with a Green Significance Determination Process finding. Response: 1 ) Reason for the violation The failure to restore compliance in a timely manner was caused by inadequate Engineering oversight and prioritization of dual site projects and over-reliance on existing multi-site Engineering Design processes to drive the issue to resolutio This is documented in the corrective action program in issue report 1404575. The delays were caused by linear prioritization of available resources based on perceived risk significanc Delay can be attributed to deficient "crew teamwork" under the classification of "supervision during work" (ref. TapRoot).
Engineers at other sites took the lead to resolve this issue (Exelon plan for sharing of resources)
and, in the beginning, there was insufficient Braidwood oversight of Lead Engineer progres Braidwood personnel focused on other site priorities, permitting other personnel to "drive" final resolutio Poor communication between the Site Points of Contact resulted in delayed Project Review Committee (PRC) approval for funding and EOC re-work of the required RELAP5 hydraulic analysis of the piping since the EOC focused on Byron piping subsystems and neglected to evaluate the Braidwood piping subsystem This was partially the result of the original piping analysis feasibility study performed in 2009 using the Byron piping models as a cost-saving measure and the EOC using this study as the starting point for the final analysi This resulted in a delay in completion of the RELAP hydraulic analysi Braidwood has taken the Lead Role in resolution and is working directly with the EOC to complete the last remaining project segment. Page 1 of 3 2) Corrective steps that have been taken and the results achieved The following corrective actions have been completed to address this issue: * For the immediate protection of the Recycle Hold-up Tank (RHUT) from the effects of potential steam relief, station procedures were revised to ensure the relief piping to the RHUT remained covered by water whenever the RHUT was aligned to the relief header. * A detailed evaluation of the RHUT under the conditions of potential steam relief from the Residual Heat Removal (RH) System relief valve was completed in February 2010. The evaluation was documented in calculation CN-CRA-09-29 to verify that the RHUT would be protected with appropriate submergence of the relief header discharge piping, * A revision of the Exclusion Area Boundary (EAB). Low Population Zone (LPZ) and Main Control Room (MCR) dose calculation for RHUT failure was completed in September 2011 and documented in calculation BRW-10-0010- This Design Issue is receiving elevated Senior Management oversight and support both within Exelon and the EOC. Further attempts to develop best-estimate relief valve opening characteristics have been suspended and known. conservative, valve response parameters will be used to permit timely completion of the RELAP5 model. 3) Corrective steps that will be taken * The priority for final resolution of the identified issue has been elevated within both Exelon and the EOC to ensure the necessary piping analyses and any necessary piping system modifications are complete The dynamic piping analysis will be completed based on existing, conservative, operating parameters by May 5, 2013. * Plant modifications will be issued to 1) install low-point drains and vents to eliminate water traps in the exhaust piping where possible and 2) modify or add piping supports if necessary to address the calculated support loads. Issuance of the above modifications will be completed by August 16. 2013. * Plant modifications will be installed by June 30. 2014. * Issue resolution is not required for the Emergency Core Cooling System (ECCS) function of the RH system as system pressures in the injection and recirculation modes are not high enough to challenge the relief valve setpoin ) Date when full compliance will be achieved Actions to restore full compliance will be completed by the end of the second quarter 2014 (June 30, 2014). Page 2 of 3 1. 2. 3. ATTACHMENT 2 Summary of Regulatory Commitments The following table identifies commitments made in this document. (Any other actions discussed in the submittal represent intended or planned actions. They are described to the NRC for the NRC's information and are not regulatory commitments.)
COMMITTED COMMITMENT TYPE COMMITMENT DATE OR ONE-TIME ACTION PROGRAMMATIC "OUTAGE" (Yes/No) (Yes/No)
Exelon Generation Company, LLC (EGC) will complete the dynamic piping analysis based on existing, conservative, operating May 5,2013 Yes No parameter EGC will issue plant modifications to: 1) Install low-point drains and vents to eliminate water traps in the exhaust piping August 16, 2013 Yes No where possible and 2) Modify or add piping supports if necessary to address the calculated support loads. EGC will complete the required modifications by the end of the second Yes No quarter 2014 June 30, 2014 Page 3 of 3