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Category:Letter
MONTHYEARIR 05000456/20230042024-02-0202 February 2024 Integrated Inspection Report 05000456/2023004 and 05000457/2023004 ML24025C7242024-01-29029 January 2024 Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000456/2024002; 05000457/2024002 IR 05000457/20230112024-01-25025 January 2024 2B Auxiliary Feedwater Pump Diesel Fuel Oil Dilution Report 05000457/2023011 and Preliminary Greater than Green Finding and Apparent Violation ML24018A0362024-01-17017 January 2024 Paragon Energy Solutions, Defect with Detroit Diesel/Mtu Fuel Injectors P/N R5229660 Cat Id 0001390618 RS-24-004, Proposed Alternative to the Distribution Requirements of ASME Code Table IWC-2411-1 for the Steam Generators2024-01-11011 January 2024 Proposed Alternative to the Distribution Requirements of ASME Code Table IWC-2411-1 for the Steam Generators ML23348A2162023-12-15015 December 2023 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0030 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) IR 05000456/20200232023-12-15015 December 2023 Baseline Security Inspection Document; 05000456/2023/402; 05000457/2023/402 ML23277A0032023-12-11011 December 2023 Issuance of Amendments Regarding Adoption of TSTF-370 ML23339A0452023-12-0505 December 2023 Request for Information for an NRC Post-Approval Site Inspection for License Renewal Inspection Report 05000546/2024010 ML23313A1552023-12-0101 December 2023 Review of the Fall 2022 Steam Generator Tube Inspection Report ML23331A8922023-11-22022 November 2023 Supplement - Braidwood Security Rule Exemption Request ISFSI Docket No. Reference 05000457/LER-2023-001, Submittal of LER 2023-001-00 for Braidwood Station, Unit 2, Train B Auxiliary Feedwater Pump Was Inoperable Due to Degraded Oil in the Crank Case2023-11-17017 November 2023 Submittal of LER 2023-001-00 for Braidwood Station, Unit 2, Train B Auxiliary Feedwater Pump Was Inoperable Due to Degraded Oil in the Crank Case ML23321A0442023-11-17017 November 2023 Notification of Deviation from Electric Power Research Institute (EPRI) Topical Report MRP-227, Revision 1-A, Materials Reliability Program: Pressurized Water Reactor Internals Inspection and Evaluation Guideline RS-23-118, Supplemental Information Letter for Part 73 Exemption Request - Responses to Request for Confirmatory Information2023-11-10010 November 2023 Supplemental Information Letter for Part 73 Exemption Request - Responses to Request for Confirmatory Information ML23317A1192023-11-10010 November 2023 Constellation Energy Generation, LLC - 2023 Annual Report - Guarantees of Payment of Deferred Premiums RS-23-114, Proposed Alternative for Examination of Pressurizer Circumferential and Longitudinal Shell-to-Head Welds and Nozzle-to-Vessel Welds2023-11-0101 November 2023 Proposed Alternative for Examination of Pressurizer Circumferential and Longitudinal Shell-to-Head Welds and Nozzle-to-Vessel Welds IR 05000456/20234012023-10-18018 October 2023 Security Baseline Inspection Report 05000456/2023401 and 05000457/2023401 IR 05000456/20230102023-10-18018 October 2023 Functional Engineering Inspection Commercial Grade Dedication Report 05000456/2023010 and 05000457/2023010 RS-23-097, Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans2023-10-12012 October 2023 Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans RS-23-108, Proposed Alternative for Examinations of Examination Categories B-B, B-D, and C-A Steam Generator Pressure Retaining Welds and Full Penetration Welded Nozzles2023-10-11011 October 2023 Proposed Alternative for Examinations of Examination Categories B-B, B-D, and C-A Steam Generator Pressure Retaining Welds and Full Penetration Welded Nozzles RS-23-105, Proposed Alternative for Examinations of Examination Category C-B Steam Generator Nozzle-to-Shell Welds and Nozzle Inside Radius Sections2023-10-10010 October 2023 Proposed Alternative for Examinations of Examination Category C-B Steam Generator Nozzle-to-Shell Welds and Nozzle Inside Radius Sections RS-23-093, License Amendment to Braidwood Station, Units 1 and 2, and Byron Station, Units 1 and 2, Technical Specifications 3.7.15, Spent Fuel Pool Boron Concentration, 3.7.16, Spent Fuel.2023-09-29029 September 2023 License Amendment to Braidwood Station, Units 1 and 2, and Byron Station, Units 1 and 2, Technical Specifications 3.7.15, Spent Fuel Pool Boron Concentration, 3.7.16, Spent Fuel. ML23226A0062023-09-19019 September 2023 Review of License Renewal Commitment Number 10 Submittal ML23180A1692023-09-11011 September 2023 Calvert Cliff Units 1 & 2, and R.E. Ginna Plant - Withdrawal of Proposed Alternatives to American Society of Mechanical Engineers (ASME) Requirements (Epids L-2022-LRR-0074, 0076, 0079, 0091, 0092, 0093 and 0094) IR 05000456/20230052023-08-30030 August 2023 Updated Inspection Plan for Braidwood Station Report 05000456/2023005 and 05000457/2023005 ML23234A2462023-08-25025 August 2023 Confirmation of Initial License Examination IR 05000456/20230022023-08-0303 August 2023 Integrated Inspection Report 05000456/2023002 and 05000457/2023002 ML23188A1292023-07-26026 July 2023 Issuance of Amendment Nos. 233 and 233 Adoption of TSTF-577, Revised Frequencies for Steam Generator Tube Inspections, Revision 1 ML23087A0762023-07-13013 July 2023 Issuance of Amendment Nos. 232 and 232 Revision of Technical Specifications for the Ultimate Heat Sink ML23191A8442023-07-10010 July 2023 05000456; 05000457 Notification of an NRC Biennial Licensed Operator Requalification Program Inspection and Request for Information ML23178A2422023-06-28028 June 2023 Reassignment of the U.S. Nuclear Regulatory Commission Branch Chief in the Division of Operating Reactor Licensing for Plant Licensing Branch III RS-23-083, Withdrawal - Proposed Alternatives Related to the Steam Generators2023-06-27027 June 2023 Withdrawal - Proposed Alternatives Related to the Steam Generators RS-23-077, Response to NRC Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations2023-06-16016 June 2023 Response to NRC Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations ML23110A1152023-06-12012 June 2023 Environmental Assessment and Finding of No Significant Impact Related to a Requested Increase in Ultimate Heat Sink Temperature (EPID L-2023-LLA-0042) (Letter) RS-23-074, Supplement to Application for License Amendment to Braidwood Station, Units 1 and 2, Technical Specification 3.7.9, Ultimate Heat Sink2023-06-0909 June 2023 Supplement to Application for License Amendment to Braidwood Station, Units 1 and 2, Technical Specification 3.7.9, Ultimate Heat Sink RS-23-075, Application for Technical Specification Improvement to Extend the Completion Time for Condition B of Technical Specification 3.5.1, Accumulators, Using the Consolidated Line Item Improvement Process2023-06-0707 June 2023 Application for Technical Specification Improvement to Extend the Completion Time for Condition B of Technical Specification 3.5.1, Accumulators, Using the Consolidated Line Item Improvement Process RS-23-050, Supplement to Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube.2023-05-22022 May 2023 Supplement to Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube. ML23138A1342023-05-18018 May 2023 Information Meeting with a Question and Answer Session to Discuss NRC 2022 End-Of-Cycle Plant Performance Assessment of Braidwood Station and Byron Station ML23132A0472023-05-12012 May 2023 Submittal of 2022 Annual Radiological Environmental Operating Report ML23130A0072023-05-10010 May 2023 Submittal of Core Operating Limits Report Cycle 24, Rev. 16 IR 05000456/20230012023-05-0808 May 2023 Integrated Inspection Report 05000456/2023001 and 05000457/2023001 ML23114A2522023-04-28028 April 2023 Request to Use a Provision of a Later Edition of the ASME Boiler & Pressure Vessel Code, Section XI ML23118A0202023-04-28028 April 2023 Submittal of 2022 Annual Radioactive Effluent Release Report ML23110A3202023-04-21021 April 2023 Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection RS-23-056, Response to Request for Additional Information to Braidwood Station, Unit 1, and Byron Station, Unit 1, for Steam Generator License Renewal Response to Commitment 102023-04-20020 April 2023 Response to Request for Additional Information to Braidwood Station, Unit 1, and Byron Station, Unit 1, for Steam Generator License Renewal Response to Commitment 10 RS-23-055, Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors2023-04-10010 April 2023 Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors ML23095A1292023-04-0505 April 2023 Steam Generator Tube Inspection Report for Refueling Outage 23 ML23094A1352023-04-0404 April 2023 Request for Information for Nrc Commercial Grade Dedication Inspection Inspection Report 05000456/2023010 05000457/2023010 RS-23-052, License Amendment to Braidwood Station, Units 1 and 2, Technical Specification 3.7.9, Ultimate Heat Sink2023-03-24024 March 2023 License Amendment to Braidwood Station, Units 1 and 2, Technical Specification 3.7.9, Ultimate Heat Sink RS-23-049, Constellation Energy Generation, LLC, Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations2023-03-23023 March 2023 Constellation Energy Generation, LLC, Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations 2024-02-02
[Table view] Category:Licensee Response to Notice of Violation
MONTHYEARML13350A3422013-12-13013 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 2013-12-13
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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