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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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Exekr,-ns.
Exelon Generation Company, LLC Braidwood Station wwwexeloncorp corn Nuclear 35100 South Rt 53, Suite 84 Braceville, IL60407-9619 Tel 815-458-2801 August 22, 2002 BW020094 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555-001 Braidwood Station, Unit 1 Facility Operating License No. NPF-72 NRC Docket No. STN 50-456
Subject:
Reply to a Notice of Violation
Reference:
Letter from G. E. Grant (NRC Region III) to J. L. Skolds (Exelon Generation Company, LLC), "Final Significance Determination for a White Finding and Notice of Violation (NRC Inspection Report No. 50-456/02-03; 50-457/02-03) (Braidwood Station, Unit 1)," dated July 23, 2002 In the referenced letter, based on the results of an inspection, the NRC determined that Braidwood Station was in violation of Criterion XVI, "Corrective Action," of 10 CFR 50, Appendix B, for failure to correct and prevent recurrence of Unit 1 pressurizer power operated relief valve (PORV) air accumulator check valve leak-through between 1991 and 2001.
The attachment to this letter contains our response to the Notice of Violation.
If you have any questions regarding this reply, please contact Amy Ferko, Regulatory Assurance Manager, at (815) 417-2699.
Respectfully,
- a. es D. von Suskil Lie Vice President Braidwood Station
Attachment:
Reply to Notice of Violation X'0\I cc: Regional Administrator- NRC Region III NRC Senior Resident Inspector - Braidwood Station
ATTACHMENT Reply to Notice of Violation In a letter from G. E. Grant (NRC Region Ill) to J. L. Skolds (Exelon Generation Company, LLC),
dated July 23, 2002, the NRC issued a Notice of Violation. The violation of NRC requirements was identified during an NRC inspection conducted on February 4, 2002 through February 22, 2002 and is provided below:
"10 CFR Part 50, Appendix B, Criterion XVI, "Corrective Action," requires, in part, that conditions adverse to quality be promptly identified and corrected. In the case of significant conditions adverse to quality, the measures shall assure that the cause of the condition is determined and corrective actions taken to preclude repetition.
Contrary to the above, between April 1991 and October 1995, the licensee failed to correct and prevent recurrence of the Unit 1 pressurizer power operated relief valve (PORV) air accumulator check valves leak-through, a significant condition adverse to quality.
Specifically, Unit 1 pressurizer relief valves failed to meet testing acceptance criteria in April 1991, October 1992, April 1994, January 1995, October 1995, October 1998, and September 2001. This resulted in several extended periods where the unit was operated in a condition where the pressurizer PORVs may not have been able to perform their intended safety function of opening following events which resulted in isolation of instrument air to the containment or loss of the service air compressors.
This violation is associated with a White SDP finding."
Response
The following is our response to the Notice of Violation.
Reason for the violation.
The failure to correct and prevent recurrence of the Unit I PORV air accumulator check valve leak through was due to ineffective corrective actions. The Unit 1 PORV air accumulator check valves had a history of surveillance test failures dating to 1991, but the actual root cause of the check valve failures was not determined until a recent root cause investigation (RCI) was completed on May 24, 2002.
The corrective steps that have been taken and the results achieved.
The RCI determined that the check valve failures were caused by incorrect valve tolerances that resulted in valve disc o-ring interference with the valve seat. This disc o-ring interference coupled with the large number of valve cycles that occur during air accumulator refill caused the disc o-ring to dislocate.
During the fall, 2001 Unit 1 refueling outage, the check valve maintenance and testing sequence was performed such that the as-left valve testing was performed after all activities that may have resulted in cycling of the check valves were completed. The Unit 1 valves are operable as demonstrated by the successful as-left check valve testing.
The corrective steps that will be taken to avoid further violations.
The procedure governing the testing sequence for routine and post maintenance testing will be revised to ensure that testing is scheduled so that the final operability testing is performed following all maintenance activities, as was done during the fall, 2001 Unit 1 refueling outage.
The RCI revealed that the approved maintenance procedure for maintaining the check valves was not used during past maintenance on the check valves. By not using the approved maintenance procedure, incorrect valve tolerances resulted. The model work orders for pressurize PORV air accumulator check valves will be revised to ensure the correct maintenance procedure is used for all check valve maintenance.
The Unit 1 check valve tolerances will be corrected and the check valve discs will be replaced with an improved design recommended by the manufacturer.
The date when full compliance will be achieved.
The procedure governing the testing sequence will be revised by September 30, 2002. The model work orders will be revised by December 13, 2002. The Unit 1 check valve tolerance adjustments and disc replacements will be completed during the next Unit 1 refueling outage, currently scheduled for April, 2003.