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Category:Exemption from NRC Requirements
MONTHYEARML23348A2162023-12-15015 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)) ML21057A1892021-03-30030 March 2021 Exemption from Select Requirements of 10 CFR Part 26 (EPID L-2021-LLE-0013 (COVID-19)) ML21056A5142021-02-25025 February 2021 Incoming Request-Braidwood-Exelon Generation Co. LLC ML20322A3382020-12-10010 December 2020 Exemption from Annual Force-on-Force Exercise Requirements of 10 CFR Part 73, Appendix B, General Criteria for Security Personnel, Subsection VI.C.3(I)(1) (EPID L-2020-LLE-0198) (COVID-19) ML20324A0022020-12-0101 December 2020 Exemption from Select Requirements of 10 CFR Part 26 (EPID L-2020-LLE-0207 (COVID-19)) ML20323A0082020-11-17017 November 2020 Incoming Request-Braidwood-Exelon Generation Co., LLC NMP1L3362, Request for an Exemption from 10 CFR 73, Appendix B, Section VI, Subsection C.3.(I)(1) Regarding 2020 Annual Force-on-Force (FOF) Exercises Due to COVID- 19 Public Health Emergency2020-11-13013 November 2020 Request for an Exemption from 10 CFR 73, Appendix B, Section VI, Subsection C.3.(I)(1) Regarding 2020 Annual Force-on-Force (FOF) Exercises Due to COVID- 19 Public Health Emergency ML20253A0622020-09-16016 September 2020 Exemption from Select Requirements of 10 CFR Part 26 (EPID L-2020-LLE-0139 (COVID-19)) ML20119A5242020-05-0707 May 2020 FRN: Notice of Issuance of Multiple Exemptions Regarding 10 CFR Part 26 (COVID-19) ML20099A5192020-04-13013 April 2020 Exemption from Select Requirements of 10 CFR Part 26 (COVID-19) ML16126A0612016-06-20020 June 2016 Exemption from the Requirements of 10 CFR Part 50, Section 50.46 and Appendix K to Allow the Use of Optimized Zirlo Clad Fuel Rods ML16126A0322016-06-20020 June 2016 Exemption from the Requirements of 10 CFR Part 50, Section 50.46 and Appendix K to Allow the Use of Optimized Zirlo Clad Fuel Rods (Cac Nos. MF7399, MF7400, MF7401, MF7402) ML0726102132007-09-27027 September 2007 Exemption from the Requirements of 10 CFR Part 50, Section 46, and Appendix K to Part 50 ML0618900032006-11-22022 November 2006 Stations, Exemption from the Requirements of 10 CFR Part 50, Appendix G ML0614302462006-06-27027 June 2006 TMI and Zion - Exemption from the Requirements of 10 CFR 50.54(a)(3) Re Submittal of Changes to Quality Assurance Topical Report 2023-12-15
[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
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March 30, 2021 Mr. David Rhoades Senior Vice President Exelon Generation Company, LLC President and Chief Nuclear Officer (CNO)
Exelon Nuclear 4300 Winfield Road Warrenville, IL 60555
SUBJECT:
BRAIDWOOD STATION, UNITS 1 AND 2 - EXEMPTION FROM SPECIFIC REQUIREMENTS OF 10 CFR PART 26 (EPID L-2021-LLE-0013 [COVID-19])
Dear Mr. Rhoades:
The U.S. Nuclear Regulatory Commission (NRC) has approved the requested temporary exemption from specific requirements of Title 10 of the Code of Federal Regulations (10 CFR)
Part 26, Fitness for Duty Programs, Section 26.205, Work hours, for Braidwood Station, Units 1 and 2 (Braidwood). This action is in response to the Exelon Generation Company, LLC (Exelon, the licensee) application dated February 25, 2021 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML21056A514). This application cited the November 10, 2020, letter from Mr. Ho Nieh (ADAMS Accession No. ML20261H515),
describing a process to request expedited review of certain exemptions from 10 CFR Part 26 during the Coronavirus Disease 2019 (COVID-19) public health emergency (PHE).
The application provided the following information:
A statement that explains how, and for which covered groups at Braidwood, the COVID-19 PHE impacts the licensees ability to meet the work-hour control requirements of 10 CFR 26.205(d)(1)-(d)(7);
A statement that describes how the licensee would use an exemption from the 10 CFR 26.205(d)(1)-(d)(7) work-hour control requirements to manage the impact of the COVID-19 PHE on maintaining plant operational safety and security at Braidwood; A list of positions for which Exelon may implement alternative work-hour controls at Braidwood upon the NRC granting the requested exemption; The date and time when the licensee will begin implementing site-specific COVID-19 PHE fatigue-management controls at Braidwood for personnel specified in 10 CFR 26.4(a);
A statement that the licensees site-specific COVID-19 fatigue-management controls at Braidwood are consistent with the constraints outlined in the November 10, 2020, letter; and
D. Rhoades A statement that the licensee will establish alternative controls at Braidwood for the management of fatigue during the period of the exemption and that, at a minimum, the controls ensure the following for individuals subject to these alternative controls:
o Individuals will not work more than 16 work hours in any 24-hour period and not more than 86 work hours in any 7-day period, excluding shift turnover; o A minimum 10-hour break is provided between successive work periods; o 12-hour shifts are limited to not more than 14 consecutive days; o A minimum of 6 days off is provided in any 30-day period; and o Requirements have been established for behavioral observation and self-declaration during the period of the exemption.
Therefore, the NRC finds that the technical basis for an exemption described in the March 28, 2020, letter from Mr. Ho Nieh (ADAMS Accession No. ML20087P237) is applicable to the licensees application.
Furthermore, although not explicitly stated as part of the licensees application, the November 10, 2020, letter also states that the controls should ensure that the calculation of work hours and days off includes all work hours and days off during the applicable calculation periods, including those work hours and days off preceding initiation of the exemption period.
The NRC previously approved exemption requests for Braidwood on April 13, 2020, and December 1, 2020, with the preceding exemption periods ending on June 19, 2020, and January 29, 2021 (ADAMS Accession Nos. ML20099A519 and ML20324A002, respectively).
Because the requested exemption will not begin within 14 days of the end of the most recent exemption for Braidwood, the licensee has had sufficient time to manage the potential for cumulative fatigue by implementing the standard work-hour controls administered in accordance with 10 CFR Part 26. Therefore, the NRC did not request that Exelon provide additional information regarding the technical basis for its request, as discussed in the November 10, 2020, letter.
Section 26.9, Specific exemptions, of 10 CFR allows the NRC to grant exemptions from the requirements of 10 CFR Part 26 as it determines are authorized by law, will not endanger life or property or the common defense and security, and are otherwise in the public interest.
The NRC determined that the requested exemption is permissible under the Atomic Energy Act of 1954, as amended, and other regulatory requirements. Therefore, the NRC finds that the requested exemption is authorized by law.
The underlying purpose of 10 CFR 26.205(d) is to prevent impairment from fatigue due to duration, frequency, or sequencing of successive shifts. Based on the evaluation provided in the NRCs March 28 and November 10, 2020, letters along with the criteria discussed above, no new accident precursors are created by using whatever licensee staff resources may be necessary or available during the term of this exemption to respond to a plant emergency and to ensure that the plant maintains a safe and secure status. Therefore, the probability of
D. Rhoades postulated accidents is not increased. Also, the consequences of postulated accidents are not increased because there is no change in the types of accidents previously evaluated. The requested exemption would allow the use of licensee staff resources as may be necessary to maintain safe operation of the plant and to respond to a plant emergency. Therefore, the NRC finds that the requested exemption will not endanger life or property.
The requested exemption would allow the use of licensee security staff resources as may be necessary to ensure the common defense and security. Therefore, the NRC finds that the requested exemption will not endanger the common defense and security.
Due to the impacts that the COVID-19 PHE has had on the licensees ability to comply with the work-hour controls of 10 CFR 26.205(d), the importance of maintaining the operations of Braidwood, and the controls the licensee has established, the NRC finds that the requested exemption is in the public interest.
Granting the requested exemption from the requirements of 10 CFR 26.205 is categorically excluded under 10 CFR 51.22(c)(25), and there are no extraordinary circumstances present that would preclude reliance on this exclusion. The NRC staff determined, per 10 CFR 51.22(c)(25)(vi)(I), that the requirements from which the exemption is sought involve other requirements of an administrative, managerial, or organizational nature.
The NRC staff also determined that approval of this exemption involves no significant hazards consideration because it does not authorize any physical changes to the facility or any of its safety systems, does not authorize changes to any of the assumptions or limits used in the licensees safety analyses, and does not introduce any new failure modes. There is no significant change in the types or significant increase in the amounts of any effluents that may be released offsite because this exemption does not affect any effluent release limits as provided in the licensees technical specifications or by the regulations in 10 CFR Part 20, Standards for Protection Against Radiation. There is no significant increase in individual or cumulative public or occupational radiation exposure because this exemption does not affect the limits on the release of any radioactive material or the limits provided in 10 CFR Part 20 for radiation exposure to workers or members of the public. There is no significant construction impact because this exemption does not involve any changes to a construction permit. There is no significant increase in the potential for or consequences from radiological accidents because the exemption does not alter any of the assumptions or limits in the licensees safety analysis.
In addition, the NRC staff determined that there would be no significant impacts to biota, water resources, historic properties, cultural resources, or socioeconomic conditions in the region.
Therefore, pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the approval of this exemption request.
Based on the above, the NRC finds that (1) the exemption is authorized by law, (2) the exemption will not endanger life or property or the common defense and security, and (3) the exemption is otherwise in the public interest.
D. Rhoades This exemption is effective from April 5, 2021, through June 3, 2021.
Sincerely, Digitally signed by Craig G. Craig G. Erlanger Date: 2021.03.30 Erlanger 08:57:09 -04'00' Craig G. Erlanger, Director Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. STN 50-456 and STN 50-457 cc: Listserv
ML21057A189 *via concurrence with model safety evaluation OFFICE NRR/DORL/LPL3/PM NRR/DORL/LPL3/LA NSIR/DPCP/RSB/BC* NMSS/REFS/ERLRB/BC*
NAME JWiebe SRohrer (JBurkhardt for) ABowers RElliott DATE 03/22/2021 3/22/2021 3/30/2020 3/31/2020 OFFICE NRR/DRO/IOLB/BC OGC (NLO) NRR/DORL/LPL3/BC NRR/DORL/D NAME CCowdrey (LNist for) TJones NSalgado CErlanger DATE 03/23/2021 03/25/2021 03/26/2021 03/29/2021