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Category:Inspection Report
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 IR 05000456/20200232023-12-15015 December 2023 Baseline Security Inspection Document; 05000456/2023/402; 05000457/2023/402 ML23313A1552023-12-0101 December 2023 Review of the Fall 2022 Steam Generator Tube Inspection Report IR 05000456/20230102023-10-18018 October 2023 Functional Engineering Inspection Commercial Grade Dedication Report 05000456/2023010 and 05000457/2023010 IR 05000456/20234012023-10-18018 October 2023 Security Baseline Inspection Report 05000456/2023401 and 05000457/2023401 IR 05000456/20230052023-08-30030 August 2023 Updated Inspection Plan for Braidwood Station Report 05000456/2023005 and 05000457/2023005 IR 05000456/20230022023-08-0303 August 2023 Integrated Inspection Report 05000456/2023002 and 05000457/2023002 IR 05000456/20230012023-05-0808 May 2023 Integrated Inspection Report 05000456/2023001 and 05000457/2023001 IR 05000457/20214202023-03-22022 March 2023 Reissued - Braidwood Generating Station, Unit 1 and 2, Security Inspection Report Cover Letter 05000456 and 05000457-2021420 IR 05000456/20220062023-03-0101 March 2023 Annual Assessment Letter for Braidwood Station, Units 1 and 2 (Report 05000456/2022006 and 05000457/2022006) IR 05000456/20220042023-01-26026 January 2023 Integrated Inspection Report 05000456/2022004 and 05000457/2022004 ML22269A4992022-11-0808 November 2022 Review of the Fall 2021 Steam Generator Tube Inspection Report IR 05000456/20220032022-10-25025 October 2022 Integrated Inspection Report 05000456/2022003 and 05000457/2022003 and Exercise of Enforcement Discretion IR 05000456/20224202022-10-24024 October 2022 Cover Letter Braidwood Station Units 1 and 2 Security Baseline Inspection Report 05000456/2022420 and 05000457/2022420 IR 05000456/20224032022-08-23023 August 2022 Material Control and Accounting Program Inspection Report 05000456/2022403 and 05000457/2022403 IR 05000456/20220052022-08-22022 August 2022 Updated Inspection Plan for Braidwood Station Units 1 and 2 (Report 05000456/2022005; 05000457/2022005) IR 05000456/20220022022-07-26026 July 2022 Integrated Inspection Report 05000456/2022002; 05000457/2022002; and 07200073/2022001 IR 05000456/20220112022-07-20020 July 2022 Biennial Problem Identification and Resolution Inspection Report 05000456/2022011 and 05000457/2022011 IR 05000456/20224012022-07-13013 July 2022 Security Baseline Inspection Report 05000456/2022401 and 05000457/2022401 IR 05000456/20224022022-06-30030 June 2022 Cyber Security Inspection Report 05000456/2022402 and 05000457/2022402 IR 05000456/20220102022-06-22022 June 2022 Design Basis Assurance Inspection (Teams) Inspection Report 05000456/2022010 and 05000457/2022010 IR 05000456/20220012022-05-0303 May 2022 Integrated Inspection Report 05000456/2022001 and 05000457/2022001 IR 05000456/20223012022-04-0606 April 2022 NRC Initial License Examination Report 05000456/2022301 and 05000457/2022301 IR 05000456/20225012022-03-21021 March 2022 Emergency Preparedness Biennial Exercise Inspection Report 05000456/2022501 and 05000457/2022501 IR 05000456/20210062022-03-0202 March 2022 Annual Assessment Letter for Braidwood Station, Units 1 and 2 (Report 05000456/2021006 and 05000457/2021006) IR 05000456/20210042022-01-28028 January 2022 Integrated Inspection Report 05000456/2021004 and 05000457/2021004 IR 05000456/20210032021-10-26026 October 2021 Integrated Inspection Report 05000456/2021003 and 05000457/2021003 IR 05000456/20214022021-09-16016 September 2021 Security Baseline Inspection Report 05000456/2021402 and 05000457/2021402 IR 05000456/20210052021-09-0101 September 2021 Updated Inspection Plan for Braidwood Station, Units 1 and 2 (Report 05000456/2021005 and 05000457/2021005) IR 05000456/20210022021-07-22022 July 2021 Integrated Inspection Report 05000456/2021002 and 05000457/2021002 IR 05000456/20210102021-07-19019 July 2021 Triennial Fire Protection Inspection Report 05000456/2021010 and 05000457/2021010 IR 05000456/20214012021-05-20020 May 2021 Security Baseline Inspection Report 05000456/2021401 and 05000457/2021401 IR 05000456/20210012021-04-16016 April 2021 Integrated Inspection Report 05000456/2021001 and 05000457/2021001 IR 05000456/20200062021-03-0404 March 2021 Annual Assessment Letter for Braidwood Station (Report 05000456/2020006 and 05000457/2020006) IR 05000456/20200042021-01-26026 January 2021 Integrated Inspection Report 05000456/2020004; 05000457/2020004; and 07200073/2020001 IR 05000456/20200122020-11-18018 November 2020 Design Basis Assurance Inspection (Programs) Inspection Report 05000456/2020012 and 05000457/2020012 IR 05000456/20200032020-11-10010 November 2020 Integrated Inspection Report 05000456/2020003 and 05000457/2020003 IR 05000456/20204022020-10-0202 October 2020 Security Baseline Inspection Report 05000456/2020402 and 05000457/2020402 IR 05000456/20200052020-09-0101 September 2020 Updated Inspection Plan for Braidwood Station Units 1 and 2 (Report 05000456/2020005 and 05000457/2020005) IR 05000456/20203012020-08-27027 August 2020 NRC Initial License Examination Report 05000456/2020301 and 05000457/2020301 ML20238B8692020-08-25025 August 2020 Notification of an NRC Triennial Heat Sink Performance Inspection and Request for Information; Inspection Report 05000456/2020004; 05000457/2020004 IR 05000456/20200022020-07-28028 July 2020 Integrated Inspection Report 05000456/2020002 and 05000457/2020002 IR 05000456/20200012020-04-21021 April 2020 Integrated Inspection Report 05000456/2020001 and 05000457/2020001 IR 05000456/20205012020-04-0808 April 2020 Emergency Preparedness Inspection Report 05000456/2020501 and 05000457/2020501 IR 05000456/20204012020-03-31031 March 2020 Security Baseline Inspection Report 05000456/2020401 and 05000457/2020401 IR 05000456/20200102020-03-25025 March 2020 Biennial Problem Identification and Resolution Inspection Report 05000456/2020010 and 05000457/2020010 IR 05000456/20190062020-03-0303 March 2020 Annual Assessment Letter for Braidwood Station, Units 1 and 2 (Report 05000456/2019006 and 05000457/2019006) ML20056F2972020-02-25025 February 2020 Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000457/2020002 2024-02-02
[Table view] 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:Notice of Violation
MONTHYEARML14105A3382014-05-0101 May 2014 Sliv Notice of Violation IR 05000456/20130082013-11-14014 November 2013 IR 05000456-13-008; 050000457-13-008; 09/09/2013 - 10/29/2013; Braidwood Station, Inservice Inspection ML12314A0832012-11-0808 November 2012 Nuclear Regulatory Commission Integrated Inspection Report 05000456-12-004; 05000457-12-004 and Notice of Violation IR 05000456/20120082012-09-24024 September 2012 IR 05000456-12-008, 05000457-12-008; 07/25/2012 ?09/07/2012; Braidwood Station, Units 1 and 2; Routine Triennial Fire Protection Baseline Inspection and Notice of Violation ML12269A1882012-09-24024 September 2012 IR 05000456-12-008, 05000457-12-008; 07/25/2012 ?09/07/2012; Braidwood Station, Units 1 and 2; Routine Triennial Fire Protection Baseline Inspection and Notice of Violation ML1106009032011-02-28028 February 2011 IR 05000456-10-503, 05000457-10-503; on 06/16/2010 - 02/10/2011; Braidwood Station, Units 1 & 2; Results of NRC Emergency Action Level and Emergency Plan Changes Inspection and Follow-up of Unresolved Item 05000456-09-005-07; 05000457-09-00 IR 05000456/20100082010-02-25025 February 2010 EA-09-259, Braidwood Nuclear Power Station, Unit 1, Final Significance Determination for a White Finding; Notification of Follow-up Assessment; and Notice of Violation; NRC Inspection Report No. 05000456/2010008 ML0712201272007-05-0101 May 2007 IA-07-015, Hess, Notice of Violation IR 05000456/20060122006-06-29029 June 2006 EA-06-081, Braidwood Nuclear Power Plant, Units 1 and 2; Final Significance Determination for a White Finding and Notice of Violation (NRC Inspection Report Nos. 05000456/2006012; 05000457/2006012) ML0618100132006-06-29029 June 2006 EA-06-081, Braidwood Nuclear Power Plant, Units 1 and 2; Final Significance Determination for a White Finding and Notice of Violation (NRC Inspection Report Nos. 05000456/2006012; 05000457/2006012) ML0610107442005-12-19019 December 2005 NRC E-mail from Steven Orth to Braidwood Communications Team Bwd IEPA Violation ML0610107002005-12-16016 December 2005 Illinois Environmental Protection Agency Ltr to Exelon - Violation Notice W-2005-00537 ML1017302052005-12-16016 December 2005 Ltr from M. Garretson to J. Petro Violation Notice Exelon Generation - Braidwood Station Violation Notice No. W-2005-00537 IR 05000456/20020032002-07-23023 July 2002 IR 05000456-02-003, IR 05000457-02-003, on 02/04/2002 -02/22/2002, Braidwood Station Units 1 & 2. NOV - Final Significance Determination for White Finding 2014-05-01
[Table view] |
Text
uly 23, 2002
SUBJECT:
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)
Dear Mr. Skolds:
The purpose of this letter is to provide you with the final results of our significance determination of the finding identified in the subject inspection report. As discussed in the letter from the NRC to you, dated June 25, 2002, the inspection finding was assessed using the significance determination process and was preliminarily characterized as White, an issue with low to moderate increased importance to safety, which may require additional NRC inspections.
This White finding involved your corrective actions for Unit 1 pressurizer power operated relief valve (PORV) air accumulator check valve failures.
In a telephone conversation with Mrs. Ann Marie Stone of NRC, Region III, on July 9, 2002, Mr. Thomas Joyce, Braidwood Plant Manager, indicated that Exelon Generating Company agreed with the preliminary characterization of the risk significance of this finding and the apparent violation associated with this issue. Mr. Joyce also indicated that there was no additional information you wished to present and, therefore, a Regulatory Conference was not needed.
After considering the information developed during the inspections, the NRC has concluded that the inspection finding is appropriately characterized as White (i.e., an issue with low to moderate increased importance to safety, which may require additional NRC inspections).
You have 30 calendar days from the date of this letter to appeal the staffs determination of significance for the identified White finding. Such appeals will be considered to have merit only if they meet the criteria given in NRC Inspection Manual Chapter 0609, Attachment 2.
The NRC has also determined that your staff failed to take prompt corrective actions to prevent recurrence of a significant condition adverse to quality, specifically, Unit 1 pressurizer PORV air accumulator check valves leak-through, as evidenced by repeated failures to meet testing acceptance criteria between 1991 and 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 is a violation of Criterion XVI, Corrective Action, of 10 CFR Part 50, Appendix B, which 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. The violation is cited in the attached Notice of Violation (Notice). The circumstances surrounding the violation are described in detail in the subject inspection reports. In accordance with the NRC Enforcement Policy, NUREG-1600, the Notice of Violation is considered escalated enforcement because it is associated with a White finding.
You are required to respond to this letter and should follow the instructions specified in the enclosed Notice when preparing your response.
As stated in our Annual Assessment letter dated March 4, 2002, the performance indicator for the Safety System Unavailability, Heat Removal System (Auxiliary Feedwater) was determined to be in the White performance band in the Mitigation Systems cornerstone. This current finding, pressurizer PORV air accumulator check valve failures, also affects the Mitigation System cornerstone. Therefore, per the NRC Action Matrix, overall plant performance for Braidwood Unit 1 has been determined to be in the degraded cornerstone band due to the two white issues in the same cornerstone. We will use the NRC Action Matrix to determine the most appropriate NRC response for these events and will notify you, by separate correspondence, of that determination.
In accordance with 10 CFR 2.790 of the NRC's "Rules of Practice," a copy of this letter, its enclosure, and your response will be available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records System (PARS) component of NRC's document system (ADAMS). ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).
Sincerely,
/RA/
Geoffrey E. Grant, Director Division of Reactor Projects Docket No. 50-456 License No. NPF-72 Enclosure: Notice of Violation See Attached Distribution
DOCUMENT NAME: C:\ORPCheckout\FileNET\ML022040424.wpd To receive a copy of this document, indicate in the box: "C" = Copy without attachment/enclosure "E" = Copy with attachment/enclosure "N" = No copy OFFICE RIII RIII RIII NAME AMStone:dtp BClayton GGrant DATE 07/16/02 07/19/02 07/23/02 OFFICIAL RECORD COPY cc w/encl: Site Vice President - Braidwood Braidwood Station Plant Manager Regulatory Assurance Manager - Braidwood Chief Operating Officer Senior Vice President - Nuclear Services Senior Vice President - Mid-West Regional Operating Group Vice President - Mid-West Operations Support Vice President - Licensing and Regulatory Affairs Director Licensing - Mid-West Regional Operating Group Manager Licensing - Braidwood and Byron Senior Counsel, Nuclear, Mid-West Regional Operating Group Document Control Desk - Licensing M. Aguilar, Assistant Attorney General Illinois Department of Nuclear Safety State Liaison Officer Chairman, Illinois Commerce Commission ADAMS Distribution:
AJM DFT MLC RidsNrrDipmIipb GEG HBC SPR C. Ariano (hard copy)
DRPIII DRSIII PLB1 JRK1
NOTICE OF VIOLATION Exelon Generating Company Docket No. 50-456 Braidwood Station, Unit 1 License No. NPF-72 EA-02-118 During an NRC inspections conducted from February 4 through February 22, 2002, a violation of NRC requirements was identified. In accordance with the "General Statement of Policy and Procedure for NRC Enforcement Actions," NUREG-1600, the violation is listed 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.
Pursuant to the provisions of 10 CFR 2.201, Exelon Generating Company, is hereby required to submit a written statement or explanation to the U.S. Nuclear Regulatory Commission, ATTN:
Document Control Desk, Washington, DC 20555, with a copy to the Regional Administrator, Region III, and a copy to the NRC Resident Inspector at Braidwood, within 30 days of the date of the letter transmitting this Notice of Violation (Notice). This reply should be clearly marked as a "Reply to a Notice of Violation" and should include: (1) the reason for the violation, or, if contested, the basis for disputing the violation or significance determination, (2) the corrective steps that have been taken and the results achieved, (3) the corrective steps that will be taken to avoid further violations, and (4) the date when full compliance will be achieved. Your response may reference or include previous docketed correspondence, if the correspondence adequately addresses the required response. If an adequate reply is not received within the time specified in this Notice, an order or a Demand for Information may be issued as to why the license should not be modified, suspended, or revoked, or why such other action as may be proper should not be taken. Where good cause is shown, consideration will be given to extending the response time.
If you contest this enforcement action, you should also provide a copy of your response, with the basis for your denial, to the Director, Office of Enforcement, United States Nuclear Regulatory Commission, Washington, DC 20555-0001.
Notice of Violation -2-Because your response will be made available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records (PARS) component of NRCs document system (ADAMS), to the extent possible, it should not include any personal privacy, proprietary, or safeguards information so that it can be made available to the public without redaction. ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room). If personal privacy or proprietary information is necessary to provide an acceptable response, then please provide a bracketed copy of your response that identifies the information that should be protected and a redacted copy of your response that deletes such information. If you request withholding of such material, you must specifically identify the portions of your response that you seek to have withheld and provide in detail the bases for your claim of withholding (e.g., explain why the disclosure of information will create an unwarranted invasion of personal privacy or provide the information required by 10 CFR 2.790(b) to support a request for withholding confidential commercial or financial information). If safeguards information is necessary to provide an acceptable response, please provide the level of protection described in 10 CFR 73.21.
In accordance with 10 CFR 19.11, you may be required to post this Notice within two working days.
Dated this 23 day of July 2002.