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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
March 30, 2011 BW110030 U.S. Nuclear Regulatory Commission ATIN: Document Control Desk Washington, D.C. 20555-0001 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 SUbject: Reply to a Notice of Violation; EA-10-220
Reference:
Letter from Hironori Peterson (U.S. NRC) to Michael J. Pacilio (Exelon Generation Company, LLC), "Braidwood Station, Units 1 and 2 Follow-up Inspection of Emergency Action Level and Emergency Plan Change Inspection Report 05000456/2010503(DRS); 05000457/2010503(DRS) and Notice of Violation" dated February 28, 2011 In the referenced letter, based on the results of an inspection completed on February 10, 2011, the NRC concluded that Braidwood Station was in violation of the requirements of 10 CFR 50.54(q) in that it made a change to the Emergency Plan which decreased the effectiveness without prior approval. 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 (Le.
March 30, 2011).
The attachment to this letter contains our response to the Notice of Violation.
EGC does not contest the violation.
If you have any questions regarding this reply, please contact Mr. Chris VanDenburgh, Regulatory Assurance Manager, at (815) 417-2800.
kff;~ ~Lp6 Site Vice President Braidwood Station
Attachment:
Reply to Notice of Violation cc: Regional Administrator - NRC Region III cc: NRC Senior Resident Inspector - Braidwood Station
Attachment Reply to Notice of Violation In a letter from Hironori Peterson (U.S. NRC) to Michael J. Pacilio (Exelon Generation Company, LLC), dated February 28,2011, the NRC issued a Notice of Violation. The violation of NRC requirements was identified during an NRC inspection completed on February 10, 2011. The violation is listed below:
Title 10 CFR 50.54(q) requires, in part, "A licensee authorized to possess and operate a nuclear power reactor shall follow and maintain in effect emergency plans which meet the standards in §50.47(b) and the requirements in Appendix E of this part. The licensee may make changes to these plans without Commission approval only if the changes do not decrease the effectiveness of the plans and the plans, as changed, continue to meet the standards of §50.47(b) and the requirements of Appendix E," Title 10 CFR 50.47(b)(4) requires, in part, "A standard emergency classification and action level scheme, the bases of which include facility system and effluent parameters, is in use by the nuclear facility licensee, and State and local response plans call for reliance on information provided by facility licensees for determinations of minimum initial offsite response measures."
Contrary to the above, as of March 28, 2008, the licensee made a change to its emergency plan which decreased the effectiveness of the plan and caused the emergency plan to no longer meet the standards of 50.47(b) and Appendix E to this part without Commission approval. Specifically, the licensee modified the Emergency Action Level (EAL) Basis in EAL HU6, Revision 21, to delay the 15-minute classification time by the dispatching of personnel, reporting the notification of a fire from the field, and extinguishing the fire. As a result, this change indefinitely extends the start of the 15-minute emergency classification clock beyond a credible notification that a fire is occurring or indication of a valid fire detection system alarm. This change decreased the effectiveness of the emergency plan by reducing the capability to perform a risk significant planning function in a timely manner.
This is a Security Level IV Violation (Section 6.6).
This violation is associated with a Green SOP finding.
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Response
Reason for the violation A change was made to the basis for EGC's fire EAL HU6 under 10 CFR 50.54(q) to provide guidance to support the definition of VALID in regards to validation of fire alarms as prescribed in NEI-99-01, "Methodology for Development of Emergency Action Levels," Revision 4. It was identified that the change to the basis conflicted with the NRC-approved threshold basis and the changed basis could add an indefinite amount of time prior to classifying and declaring an emergency.
Corrective steps that have been taken and the results achieved Training material for the fire EAL HU6 revision to remove the added basis information was developed.
EGC has conducted training and evaluation on the revision. The EAL basis for the fire EAL HU6 was revised to remove the information that could have led to an increase in classification time and will be implemented on April 8, 2011. The EAL basis revision and the training conducted will align the appropriate time period for classification of the fire EAL, HU6, with the NRC-approved threshold basis.
Corrective steps that will be taken The EGC 10 CFR 50.54(q) process and procedures have been revised. The revision consisted of providing a more in-depth explanation of the terms "timeliness and capabilities" and how they are applied in evaluating potential changes. The procedure revision provided a clear relationship between Planning Standards, Planning Functions, and Program Elements to allow proper evaluation of standards and their affects on proposed changes.
Date when full compliance will be achieved Full compliance will be achieved through implementation of Revision 27 of the Braidwood Annex (EP-AA-1 001) on April 8, 2011.
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