Letter Sequence Request |
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Initiation
- Request, Request, Request, Request, Request, Request, Request, Request, Request, Request
- Acceptance, Acceptance
- Supplement, Supplement
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MONTHYEARML1106200892011-03-0202 March 2011 Response to NRC Verification Inspection Report; 05000456/2011009; 05000457/2011009 Project stage: Request ML1117900402011-04-12012 April 2011 Westinghouse Electric Company Affidavit Supporting Withholding, Attachment 6 to Braidwood Station, Units 1 & 2, Byron Station, Unit 1 & 2, Request for License Amendment Regarding Measurement Uncertainty Recapture (Mur) Power Uprate Project stage: Request ML1117900432011-05-0909 May 2011 Affidavit from Cameron International Corporation Supporting Withholding of Attachments 8a Through 8d Project stage: Request ML1117900422011-06-21021 June 2011 Mur Technical Evaluation, (Non-Proprietary Version), Attachment 7 to Braidwood Station, Units 1 & 2, Byron Station, Unit 1 & 2, Request for License Amendment Regarding Measurement Uncertainty Recapture (Mur) Power Uprate Project stage: Request RS-11-099, Request for License Amendment Regarding Measurement Uncertainty Recapture (Mur) Power Uprate2011-06-23023 June 2011 Request for License Amendment Regarding Measurement Uncertainty Recapture (Mur) Power Uprate Project stage: Request ML1117900382011-06-23023 June 2011 Steam Generator Tube Rupture Analysis Report, Attachment 5a to Braidwood Station, Units 1 & 2, Byron Station, Unit 1 & 2, Request for License Amendment Regarding Measurement Uncertainty Recapture (Mur) Power Uprate Project stage: Request ML11224A0832011-08-0303 August 2011 NRR E-mail Capture - Draft - Supplemental Information Request Braidwood and Byron Mur LAR (ME6587-ME6590) Project stage: Draft Other ML1121505632011-08-22022 August 2011 Supplemental Information Needed for Acceptance of Licensing Action Measurement Uncertainty Recapture Power Uprate Project stage: Acceptance Review ML1122315742011-09-19019 September 2011 Acceptance Review of License Amendment Request (LAR) Measurement Uncertainty Recapture (Mur) Power Uprate Project stage: Acceptance Review ML11266A0022011-09-19019 September 2011 NRR E-mail Capture - Draft RAI Braidwood/Byron - Measurement Uncertainty Recapture LAR Project stage: Draft RAI ML11262A1612011-10-12012 October 2011 Request for Addtional Information Measurement Uncertainty Power Uprate Request Project stage: Other RS-11-169, Additional Information Supporting Request for License Amendment Regarding Measurement Uncertainty Recapture Power Uprate2011-11-0101 November 2011 Additional Information Supporting Request for License Amendment Regarding Measurement Uncertainty Recapture Power Uprate Project stage: Request ML1129203422011-11-0303 November 2011 Request for Withholding Information from Public Disclosure Affidavit CAW-11-3137 Project stage: Withholding Request Acceptance ML1129305492011-11-0303 November 2011 Request for Withholding Information from Public Disclosure Affidavit CAW-11-03 Project stage: Withholding Request Acceptance ML1130104032011-11-28028 November 2011 Request for Additional Information #2 Measurement Uncertainty Power Uprate Request Project stage: RAI ML1202701462012-02-14014 February 2012 Request for Additional Information Measurement Uncertainty Recapture Power Uprate Request Project stage: RAI ML1202609362012-02-14014 February 2012 Request for Additional Information Measurement Uncertainty Recapture Power Uprate Request Project stage: RAI ML1205302582012-02-24024 February 2012 Request for Additional Information Measurement Uncertainty Recapture Power Uprate Request Project stage: RAI ML12068A3822012-03-0808 March 2012 E-MAIL - Mur LAR #1 Response Date Project stage: Other ML12068A2942012-03-0808 March 2012 Request for Additional Information Regarding Reactor Systems Mur Review (TACs ME6587, ME6588, ME6589, and ME6590) Project stage: RAI ML1205904602012-03-0909 March 2012 Request for Additional Information Regarding Measurement Uncertainty Recapture Power Uprate Project stage: RAI ML12089A4902012-03-29029 March 2012 E-MAIL - Draft Balance of Plant Request for Additional Information for Mur Review Project stage: Draft RAI ML12121A6942012-05-10010 May 2012 Braidwood Units 1 and 2 - Request for Additional Information Related to License Application for Measurement Uncertainty Recapture Uprate Project stage: RAI RS-12-081, Additional Information Supporting Request for License Amendment Regarding Measurement Uncertainty Recapture Power Uprate2012-05-16016 May 2012 Additional Information Supporting Request for License Amendment Regarding Measurement Uncertainty Recapture Power Uprate Project stage: Request ML12157A0632012-06-13013 June 2012 Request for Additional Information Related to Measurement Uncertainty Recapture Uprate Project stage: RAI ML12233A6012012-08-27027 August 2012 Request for Additional Information, Measurement Uncertainty Recapture Power Uprate Request Project stage: RAI RS-12-144, Additional Information Supporting Request for License Amendment Regarding Measurement Uncertainty Recapture Power Uprate2012-09-13013 September 2012 Additional Information Supporting Request for License Amendment Regarding Measurement Uncertainty Recapture Power Uprate Project stage: Request ML12216A0002012-09-27027 September 2012 Request for Additional Information Related to Measurement Uncertainty Uprate Project stage: RAI ML12271A3082012-12-0606 December 2012 Request for Additional Information and Suspension of Review of License Amendment Request for Power Uprate Project stage: RAI RS-13-227, Response to NRC HELB Audit Request for Information Supporting Request for License Amendment Regarding Measurement Uncertainty Recapture Power Uprate2013-09-0505 September 2013 Response to NRC HELB Audit Request for Information Supporting Request for License Amendment Regarding Measurement Uncertainty Recapture Power Uprate Project stage: Request RS-13-261, Supplemental Response to NRC HELB Audit Request for Information Supporting Request for License Amendment Regarding Measurement Uncertainty Recapture Power Uprate2013-10-24024 October 2013 Supplemental Response to NRC HELB Audit Request for Information Supporting Request for License Amendment Regarding Measurement Uncertainty Recapture Power Uprate Project stage: Supplement RS-13-267, Supplemental Information Supporting Request for License Amendment Regarding Measurement Uncertainty Recapture Power Uprate2013-11-13013 November 2013 Supplemental Information Supporting Request for License Amendment Regarding Measurement Uncertainty Recapture Power Uprate Project stage: Supplement 2012-02-14
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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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Text
10 CFR 50.109 March 2, 2011 BW110021 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 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:
Response to NRC Verification Inspection Report; 05000456/2011009; 05000457/2011009
Reference:
Letter from Steven A. Reynolds (USNRC) to Michael J. Pacillio (Exelon Generation Company, LLC), "Braidwood Station, Units 1 and 2, Verification Inspection Related to Analysis of Steam Generator Tube Rupture Event Margin to Overfill; 05000456/2011009; 05000457/2011009", dated February 1,2011 In the referenced letter, the NRC notified Exelon Generation Company, LLC (EGC) of the completion of a verification inspection at Braidwood Station, Units 1 and 2. The inspection report documents the actions taken to review a condition related to the analysis for a Steam Generator Tube Rupture (SGTR) event Margin to Overfill (MTO), previously identified at Byron Station with respect to the single failure assumptions used in the SGTR event.
The inspection concluded the NRC was not clear or consistent with communicating the need to assume passive failures of the electrical components for the SGTR analysis, even though passive failures were required to be evaluated under 10 CFR Part 50, Appendix A. Therefore, the current NRC staff position regarding the requirement to evaluate single passive failures of the electrical components is different than the NRC's position previously communicated to Braidwood Station.
Therefore, the provisions of 10 CFR 50.109, "Backfitting," are applicable.
EGC acknowledges the NRC's revised position concerning the application of single failure criteria, as denoted in 10 CFR 50, Appendix A, to Braidwood Station's SGTR analysis. This revised NRC position now places Braidwood Station's SGTR analysis in noncompliance with NRC regulations.
EGC also acknowledges the NRC's requirement for Braidwood Station to resolve this noncompliance in accordance with 10 CFR 50.109. EGC does not intend to appeal this determination.
March 2,2011 U. S. Nuclear Regulatory Commission Page 2 The NRC requested a response within 30 days of the date of the inspection report with EGC's assessment of the issue and a description of our intended actions and schedule for completion. The NRC also requested the extent of condition to be addressed by reviewing other transients and accidents outlined in Chapter 15 of the Updated Final Safety Analysis Report (UFSAR).
The issue has been entered into the Corrective Action Program (CAP) and EGC intends to bring Braidwood Station into compliance. Compensatory actions have already been implemented pending permanent actions to resolve this issue.
To resolve this issue, EGC commits Braidwood Station Units 1 and 2 to modify the power supplies to the Steam Generator Power Operated Relief Valves (PORVs) by providing a safety related battery backup. This battery backup will restore the limiting single failure for the SGTR analysis to the loss of one SG PORV. These modifications will be installed no later than Unit 1's April 2012 refueling outage and Unit 2's October 2012 refueling outage. However, if a determination is made once the design details are issued that the modifications can be installed on-line, then the installation schedule will be accelerated. EGC will supplement this letter by October 14, 2011, communicating any revisions to the installation schedule based on the on-line/outage determination.
EGC also commits to performing an extent of condition review of other transients and accidents outlined in Chapter 15 of the Braidwood Station UFSAR to identify similar discrepancies with respect to the inappropriate reliance or assumption of a single active failure. Identified discrepancies will be resolved within the CAP and communicated to the NRC Region III Regional Administrator. This extent of condition review is scheduled to be completed by August 4, 2011.
The Attachment to this letter contains a list of regulatory commitments made in this letter. Should you have any questions concerning this letter, please contact Mr. Terence K. Schuster at (815) 417-2800.
Respectfully,
~6~
Site Vice President Braidwood Station Attachment - Summary of Regulatory Commitments cc: NRR Project Manager - Braidwood Station Illinois Emergency Management Agency - Division of Nuclear Safety US NRC Regional Administrator, Region III US NRC Senior Resident Inspector (Braidwood Station)
US NRC Director, Office of Enforcement
ATTACHMENT
SUMMARY
OF REGULATORY COMMITMENTS The following table identifies commitments made in this document. Any other actions discussed in this letter represent intended or planned actions. They are described to the NRC for the NRC's information and are not regulatory commitments.
COMMIITTED COMMITMENT TYPE COMMITMENT DATE OR "OUTAGE" ONE* PROGRAMMATIC TIME (Yes/No)
(Yes/No)
The power supplies to the Steam No later than Generator PORVs will be Unit 1's April 2012 modified with a safety related refueling outage Yes No battery backup. and Unit 2's October 2012 refueling outage A supplement to this letter will be issued to communicate any revisions to the modification October 14, 2011 Yes No installation schedule based on the online/outaQe determination.
An extent of condition review will be conducted of other transients and accidents outlined in Chapter 15 of the Braidwood Station UFSAR to identify similar The review to Yes No discrepancies with respect to the identify similar inappropriate reliance or discrepancies will assumption of a single active be completed by failure. Identified discrepancies August 4, 2011 will be resolved within the Corrective Action Program and communicated to the NRC Region III Regional Administrator.