Letter Sequence Other |
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MONTHYEARML0807403252008-03-14014 March 2008
Evaluation of New Information Related to Alloy 82/182 Pressurizer Butt Weld Inspections Confirmatory Action Letter NRR-07-008
Project stage: Other
ML0819202872008-07-10010 July 2008
Closeout of Confirmatory Action Letter Requirements - Unit 2
Project stage: Other
ML0825200392008-09-16016 September 2008
Closure of Confirmatory Action Letter NRR-07-008
Project stage: Other
2008-07-10
[Table View] |
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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:Confirmatory Action Letter (CAL)
MONTHYEARML0825200392008-09-16016 September 2008
Closure of Confirmatory Action Letter NRR-07-008
ML0819202872008-07-10010 July 2008
Closeout of Confirmatory Action Letter Requirements - Unit 2
ML0807403252008-03-14014 March 2008
Evaluation of New Information Related to Alloy 82/182 Pressurizer Butt Weld Inspections Confirmatory Action Letter NRR-07-008
ML0733901792007-12-17017 December 2007
Completion of Actions for Confirmatory Action Letter NRR-07-008
ML0731803832007-11-14014 November 2007
Closeout of Confirmatory Action Letter Requirements
ML0724302922007-09-0707 September 2007
Evaluation of Finite Element Analysis in Support of Alloy 82/182 Pressurizer Butt Weld Inspections in 2008 as Provided by Completion of Analysis Required by CAL NRR-07-008
ML0707402942007-03-22022 March 2007
Confirmatory Action Letter - Braidwood, Units 1 and 2
2008-09-16
[Table view] |
Text
March 14, 2008 Mr. Charles G. Pardee Chief Nuclear Officer and Senior Vice President Exelon Generation Company, LLC 4300 Winfield Road Warrenville, IL 60555
SUBJECT:
BRAIDWOOD STATION, UNIT 2 - EVALUATION OF NEW INFORMATION RELATED TO ALLOY 82/182 PRESSURIZER BUT WELD INSPECTIONS RE:
CONFIRMATORY ACTION LETTER NRR-07-008 (TAC NO. MD7295)
Dear Mr. Pardee:
On March 22, 2007, the U.S. Nuclear Regulatory Commission (NRC) issued Confirmatory Action Letter (CAL) No. NRR-07-008 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML070740294) regarding dissimilar metal welds in the pressurizer surge, spray, and safety/relief nozzle-to-safe end welds at Braidwood Station (Braidwood), Unit 2 . The CAL and the supporting commitment letter (ADAMS Accession No. ML070520499) indicate that inspection and mitigation actions may be conducted during your spring 2008 refueling outage, contingent on the industry providing an analysis that demonstrates an acceptable level of safety to the NRC for the operation of these welds until the spring of 2008.
The NRC received MRP-216, Rev. 1, Materials Reliability Program: Advanced FEA [Finite Element Analysis] Evaluation of Growth of Postulated Circumferential PWSCC [Primary Water Stress-Corrosion Cracking] Flaws in Pressurizer Nozzle Dissimilar Metal Welds, on August 13, 2007 (ADAMS Accession No. ML072410235). Based on our review of this report, NRC concluded that the analysis provided adequate justification to permit inspections during your spring 2008 refueling outage, and that the analysis was applicable to Braidwood, Unit 2. On September 7, 2007, the NRC issued a letter to Exelon Generation Company, LLC (ADAMS Accession No. ML072430292), informing you that a plant shutdown by December 31, 2007, was no longer needed and Braidwood, Unit 2 could continue to operate until the spring 2008 outage.
On March 4, 2008, the NRC became aware of emerging information regarding certain welds in nozzles on a retired pressurizer from a pressurized-water reactor facility. This was related to new reports (ADAMS Accession Nos. ML080701017 and ML080701020) on weld examinations of those nozzles. This information raised questions regarding the technical basis for the September 7, 2007, letter. The NRC dispatched technical experts in non-destructive examination to independently review industry analyses and actions regarding this matter. On March 13, 2008, a public meeting was held in NRC Headquarters, Rockville, MD, with representatives of the eight licensees whose plants had not yet shut down for spring 2008 outages and who are subject to commitments to inspect or mitigate similar welds during spring 2008 outages.
C. Pardee The NRC has evaluated the non-destructive automated phased array ultrasonic examination performed since March 4, 2008, and concluded there is reasonable assurance that there is no structurally significant service-related degradation in those nozzles that would alter the conclusions provided in our letter dated September 7, 2007, that allowed continued operation of Braidwood, Unit 2 until the spring 2008 refueling outage. The NRC will continue to evaluate new information as it becomes available. All other requirements of the CAL and the supporting commitment letter regarding enhanced inspection and leakage monitoring requirements for the reactor coolant system and associated reports remain valid.
The CAL will remain open until all CAL commitments pertaining to Braidwood, Unit 2 are complete.
Current NRC guidance regarding CALs is contained in the NRC Enforcement Policy and the NRC Enforcement Manual, which are available at the NRC web site at http://www.nrc.gov/about-nrc/regulatory/enforcement.html (click on Enforcement Policy or Enforcement Guidance) or by contacting the Government Printing Office (GPO) toll-free at 1-888-293-6498. The GPO is open from 7:00 a.m. to 9:00 p.m. EST, Monday through Friday (except Federal holidays).
In accordance with Title 10 of the Code of Federal Regulations, Part 2, Section 390, of the NRC's "Rules of Practice," a copy of this letter will be made available electronically for public inspection in the NRC Public Document Room or from the NRCs document system (ADAMS),
accessible from the NRC Web site at http://www.nrc.gov/reading-rm.html.
Sincerely,
/RA by Tim McGinty for/
Catherine Haney, Director Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. STN 50-457 cc: See next page
C. Pardee The NRC has evaluated the non-destructive automated phased array ultrasonic examination performed since March 4, 2008, and concluded there is reasonable assurance that there is no detectable structurally significant operational degradation in those nozzles that would alter the conclusions provided in our letter dated September 7, 2007, that allowed continued operation of Braidwood, Unit 2 until the spring 2008 refueling outage. The NRC will continue to evaluate new information as it becomes available. All other requirements of the CAL and the supporting commitment letter regarding enhanced inspection and leakage monitoring requirements for the reactor coolant system and associated reports remain valid.
The CAL will remain open until all CAL commitments pertaining to Braidwood, Unit 2 are complete.
Current NRC guidance regarding CALs is contained in the NRC Enforcement Policy and the NRC Enforcement Manual, which are available at the NRC web site at http://www.nrc.gov/about-nrc/regulatory/enforcement.html (click on Enforcement Policy or Enforcement Guidance) or by contacting the Government Printing Office (GPO) toll-free at 1-888-293-6498. The GPO is open from 7:00 a.m. to 9:00 p.m. EST, Monday through Friday (except Federal holidays).
In accordance with Title 10 of the Code of Federal Regulations, Part 2, Section 390, of the NRC's "Rules of Practice," a copy of this letter will be made available electronically for public inspection in the NRC Public Document Room or from the NRCs document system (ADAMS),
accessible from the NRC Web site at http://www.nrc.gov/reading-rm.html.
Sincerely,
/RA by Tim McGinty for/
Catherine Haney, Director Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. STN 50-457 cc: See next page DISTRIBUTION:
PUBLIC RidsNrrDirs RidsOEMailCenter LPL3-2 R/F RidsNrrDorl RidsOgcRp RidsAcrsAcnw&mMailCenter RidsNrrDorlLpl3-2 RidsRgn3MailCenter RidsEdoMailCenter RidsNrrLAJBurkhardt RLickus, R-III SLO RidsNrrOd RidsNrrLAEWhitt MWidman, EDO R-III RidsNrrDci RidsNrrPMMMarkley RJStrasma, OPA R-III RidsNrrDciCpnb RidsNrrPMMDavid ESullivan, NRR/DCI/CPNB ADAMS Accession No. ML080740325 (*) by e-mail (**) see previous concurrence NRR-106 OFFICE DCI/CPNB DCI/CPNB/BC DORL/LPL3-2/PM DORL/LPL4/LA NAME TSullivan TChan MDavid, CG for JBurkhardt DATE 3/14/08, w/comments 3/14/08 3/14/08 3/14/08 OFFICE DORL/LPLIII-2/BC NRR/DCI/D DRP/D, R-III NRR/DORL/D NAME RGibb, CG for MEvans CPederson, SWest for Chaney, TJM for DATE 3/14/08 3/14/08 3/14/08 3/14/08 OFFICIAL AGENCY RECORD
Braidwood Station Units 1 and 2 cc:
Document Control Desk - Licensing Site Vice President - Braidwood Exelon Generation Company, LLC Exelon Generation Company, LLC 4300 Winfield Road 35100 S. Rt. 53, Suite 84 Warrenville, IL 60555 Braceville, IL 60407-9619 Mr. Dwain W. Alexander, Project Manager Senior Vice President - Operations Support Westinghouse Electric Corporation Exelon Generation Company, LLC Energy Systems Business Unit 4300 Winfield Road Post Office Box 355 Warrenville, IL 60555 Pittsburgh, PA 15230 Chairman, Ogle County Board Ms. Bridget Little Rorem Post Office Box 357 Appleseed Coordinator Oregon, IL 61061 117 N. Linden Street Essex, IL 60935 Manager Regulatory Assurance - Braidwood Exelon Generation Company, LLC Howard A. Learner 35100 S. Rt. 53, Suite 84 Environmental Law and Policy Braceville, IL 60407-9619 Center of the Midwest 35 East Wacker Dr., Suite 1300 Director - Licensing and Regulatory Affairs Chicago, IL 60601-2110 Exelon Generation Company, LLC 4300 Winfield Road U.S. Nuclear Regulatory Commission Warrenville, IL 60555 Braidwood Resident Inspectors Office 35100 S. Rt. 53, Suite 79 Associate General Counsel Braceville, IL 60407 Exelon Generation Company, LLC 4300 Winfield Road Ms. Lorraine Creek Warrenville, IL 60555 RR 1, Box 182 Manteno, IL 60950 Senior Vice President - Midwest Operations Exelon Generation Company, LLC Illinois Emergency Management Agency 4300 Winfield Road Division of Disaster Assistance & Warrenville, IL 60555 Preparedness 1035 Outer Park Dr Vice President - Regulatory Affairs Springfield, IL 62704 Exelon Generation Company, LLC 4300 Winfield Road County Executive Warrenville, IL 60555 Will County Office Building 302 N. Chicago Street Manager Licensing - Braidwood, Byron and Joliet, IL 60432 LaSalle Exelon Generation Company, LLC Attorney General 4300 Winfield Road 500 S. Second Street Warrenville, IL 60555 Springfield, IL 62701 Plant Manager - Braidwood Station Exelon Generation Company, LLC 35100 S. Rt. 53, Suite 84 Braceville, IL 60407-9619
