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Category:Inspection Plan
MONTHYEARML23339A0452023-12-0505 December 2023 Request for Information for an NRC Post-Approval Site Inspection for License Renewal Inspection Report 05000546/2024010 IR 05000456/20230052023-08-30030 August 2023 Updated Inspection Plan for Braidwood Station Report 05000456/2023005 and 05000457/2023005 IR 05000456/20220062023-03-0101 March 2023 Annual Assessment Letter for Braidwood Station, Units 1 and 2 (Report 05000456/2022006 and 05000457/2022006) IR 05000456/20220052022-08-22022 August 2022 Updated Inspection Plan for Braidwood Station Units 1 and 2 (Report 05000456/2022005; 05000457/2022005) ML22111A0752022-04-21021 April 2022 Information Request Letter for 2022 Problem Identification and Resolution Inspection at Braidwood Station IR 05000456/20210062022-03-0202 March 2022 Annual Assessment Letter for Braidwood Station, Units 1 and 2 (Report 05000456/2021006 and 05000457/2021006) ML22034A9862022-02-0404 February 2022 Information Request for the Cyber-Security Baseline Inspection, Notification to Perform Inspection 05000456/2022402 05000457/2022402 ML21350A4372021-12-16016 December 2021 Request for Information for an NRC Triennial Baseline Design Bases Assurance Inspection (Team) Inspection Report 05000456/2022010 and 05000457/2022010 IR 05000456/20210052021-09-0101 September 2021 Updated Inspection Plan for Braidwood Station, Units 1 and 2 (Report 05000456/2021005 and 05000457/2021005) ML21193A0942021-07-12012 July 2021 Notification of an NRC Biennial Licensed Operator Requalification Program Inspection and Request for Information ML21057A1022021-02-25025 February 2021 Notification of NRC Fire Protection Team Inspection Request for Information; Inspection Report 05000456/2021010; 05000457/2021010 ML21020A1292021-01-20020 January 2021 Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000456/2021002; 05000457/2021002 IR 05000456/20200052020-09-0101 September 2020 Updated Inspection Plan for Braidwood Station Units 1 and 2 (Report 05000456/2020005 and 05000457/2020005) ML20183A3912020-07-0101 July 2020 Notification of NRC Design Bases Assurance Inspection (Programs) and Initial Request for Information: Inspection Report 05000456/2020012 and 05000457/2020012 IR 05000456/20190062020-03-0303 March 2020 Annual Assessment Letter for Braidwood Station, Units 1 and 2 (Report 05000456/2019006 and 05000457/2019006) IR 05000456/20190052019-08-28028 August 2019 Updated Inspection Plan for Braidwood Station, Units 1 and 2 (Report 05000456/2019005; 05000457/2019005) ML19154A6152019-06-0303 June 2019 Ltr. 06/03/19 Braidwood Station, Unit 1 - Notification of NRC Inspection and Request for Information; Inspection Report 05000456/2019004; 05000457/2019004 (DRS-J.Bozga) ML19136A1852019-05-15015 May 2019 Byron Station, Clinton Power Station, Dresden Nuclear Power Station, LaSalle County Station, and Quad Cities Nuclear Power Station-Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency IR 05000456/20180062019-03-0404 March 2019 Annual Assessment Letter for Braidwood Station, Units 1 and 2 (Report 05000457/2018006 and 05000456/2018006) ML18305A3542018-10-31031 October 2018 Ltr. 10/31/18 Braidwood Station, Units 1 and 2 - Request for Information for an NRC Triennial Baseline Design Bases Assurance Inspection (Team); Inspection Report 05000456/2019010; 05000457/2019010 (DRS-J.CorujoSandin) IR 05000456/20180052018-08-28028 August 2018 Updated Inspection Plan for Braidwood Station, Units 1 and 2 (Report 05000456/2018005 and 05000457/2018005) IR 05000456/20170062018-03-0202 March 2018 Annual Assessment Letter for Braidwood Station, Units 1 and 2 (Report 05000456/2017006 and 05000457/2017006) IR 05000456/20170052017-08-28028 August 2017 Updated Inspection Plan for Braidwood Station, Units 1 and 2 (Report 05000456/2017005 and 05000457/2017005) IR 05000456/20160062017-03-0101 March 2017 Annual Assessment Letter for Braidwood Station Units 1 and 2 (Report 05000456/2016006 and 05000457/2016006) ML16265A5772016-09-20020 September 2016 E-Mail; Braidwood Station, Unit 1 - Baseline Inservice Inspection Onsite Information Request (Msh) IR 05000456/20160052016-08-31031 August 2016 MID-CYCLE Assessment Letter for Braidwood Station Units 1 and 2 (Report 05000456/2016005; 05000457/2016005) ML16174A0852016-06-21021 June 2016 Notification of NRC Inspection and Request for Information 05000456/2016004; 05000457/2016004 IR 05000456/20150062016-03-0202 March 2016 Annual Assessment Letter for Braidwood Station Units 1 and 2 (Inspection Report 05000456/2015006 and 05000457/2015006) ML15328A5022015-11-24024 November 2015 Request for Information for an NRC Triennial Baseline Component Design Bases Inspection; Inspection Report 05000456/2016008; 05000457/2016008 (Bxj) IR 05000456/20150052015-09-0101 September 2015 Mid-Cycle Assessment Letter for Braidwood, Units 1 and 2 (Report 05000456/2015005; 05000457/2015005) ML15231A1492015-08-17017 August 2015 Ltr. 08/17/15 Braidwood Station, Unit 2 - Notification of NRC Inspection and Request for Information (Txb) IR 05000456/20140012015-03-0404 March 2015 Annual Assessment Letter for Braidwood Station, Units 1 and 2 (Report 05000456/2014001; 05000457/2014001) ML15021A2322015-01-20020 January 2015 U1 ISI Request for Information ML14245A0692014-09-0202 September 2014 Mid-Cycle Assessment Letter for Braidwood Station, Units 1 and 2 ML14223B2132014-08-11011 August 2014 Heat Sink Request for Information IR 05000456/20130012014-03-0404 March 2014 Annual Assessment Letter for Braidwood Station, Units 1 and 2 (Report 05000456/2013001; 05000457/2013001) IR 05000456/20130062013-09-0303 September 2013 Mid-Cycle Assessment Letter (IR 05000456-13-006 & 05000457-13-006) ML13120A5842013-04-29029 April 2013 Request for Information for an NRC Triennial Baseline Component Design Bases Inspection (CDBI) Inspection Report 05000456-13-007 05000457-13-007 IR 05000456/20120012013-03-0404 March 2013 Annual Assessment Letter - Braidwood Station, Units 1 and 2, 05000456/2012001 and 05000457/2012001 ML12248A3062012-09-0404 September 2012 Mid-Cycle Assessment Letter for Braidwood Station Units 1 and 2 IR 05000456/20110072012-03-0505 March 2012 Annual Assessment Letter for Braidwood Station, Units 1 & 2 (Report 05000456-11-007 and 05000457-11-007) IR 05000456/20110062011-09-0101 September 2011 Mid-Cycle Letter for Braidwood Station, Units 1 and 2, - 05000456/2011-006; 05000457/2011-006 ML1024401002010-09-0101 September 2010 Mid-Cycle Performance Review and Inspection Plan - Braidwood Nuclear Power Plant IR 05000456/20100012010-03-0303 March 2010 Braidwood Power Plant EOC Annual Assessment Letter (05000456-10-001; 05000457-10-001) ML0924404022009-09-0101 September 2009 Braidwood - Mid-Cycle Performance Review and Inspection Plan ML0906302842009-03-0404 March 2009 Annual Assessment Letter - Braidwood (05000456/2010-001; 05000457/2010-001) ML0824602282008-09-0202 September 2008 Braidwood, Units 1 & 2 - Mid-Cycle Performance Review and Inspection Plan IR 05000456/20080012008-03-0303 March 2008 Braidwood, EOC Annual Assessment Letter (Report 05000456-08-001; 05000457-08-001) ML0735402552007-12-19019 December 2007 Inspection Plan 1/1/08 - 12/31/08 ML0724303542007-08-31031 August 2007 8/31/07 Braidwood - Mid-Cycle Performance Review and Inspection Plan 2023-08-30
[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:Request for Additional Information (RAI)
MONTHYEARML23339A0452023-12-0505 December 2023 Request for Information for an NRC Post-Approval Site Inspection for License Renewal Inspection Report 05000546/2024010 ML23191A8442023-07-10010 July 2023 05000456; 05000457 Notification of an NRC Biennial Licensed Operator Requalification Program Inspection and Request for Information ML23110A3202023-04-21021 April 2023 Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection ML23094A1352023-04-0404 April 2023 Request for Information for Nrc Commercial Grade Dedication Inspection Inspection Report 05000456/2023010 05000457/2023010 ML23069A0332023-03-0606 March 2023 Email to K. Lueshen Byron and Braidwood Commitment 10 - Request for Additional Information Set 1 ML23069A0342023-03-0606 March 2023 Unit 1 Lr Commitment 10 RAI Set 1 - (Non-Proprietary) ML23018A1632023-01-18018 January 2023 Notification of NRC Baseline Inspection and Request for Information ML22241A0522022-08-29029 August 2022 Notification of NRC Baseline Inspection and Request for Information Inspection Report 05000456/2022004 05000457/2022004 ML22271A0772022-05-0606 May 2022 NRR E-mail Capture - Final RAIs 9.1.2021 Constellation Relief Request ML22129A0132022-05-0606 May 2022 NRR E-mail Capture - Draft RAIs for Requests for Alternatives I4R-17, I4R-23, ISI-05-018, I6R-10 ML22091A0852022-04-0101 April 2022 NRR E-mail Capture - Braidwood and Byron - Final RAI Regarding Proposed Alternative for Various Pressurizer Welds (EPID L-2021-LLR-0035 and 0036) ML22041B5362022-02-10010 February 2022 NRR E-mail Capture - Constellation Energy Generation, LLC - Request for Additional Information Regarding Fleet License Amendment Request to Adopt TSTF-541 ML22034A9862022-02-0404 February 2022 Information Request for the Cyber-Security Baseline Inspection, Notification to Perform Inspection 05000456/2022402 05000457/2022402 ML21350A4372021-12-16016 December 2021 Request for Information for an NRC Triennial Baseline Design Bases Assurance Inspection (Team) Inspection Report 05000456/2022010 and 05000457/2022010 ML21256A1902021-09-10010 September 2021 NRR E-mail Capture - Exelon Generation Company, LLC - Request for Additional Information Regarding License Transfer Application ML21228A2352021-08-17017 August 2021 Notification of NRC Baseline Inspection and Request for Information Inspection Report 05000457/2021004 ML21193A0942021-07-12012 July 2021 Notification of an NRC Biennial Licensed Operator Requalification Program Inspection and Request for Information ML21189A1602021-07-0808 July 2021 NRR E-mail Capture - Request for Additional Information - Braidwood, Byron, and Ginna - Amendment to Address the Issues in Westinghouse NSALs ML21144A2132021-05-24024 May 2021 NRR E-mail Capture - Exelon Generation Company, LLC - Request for Additional Information Regarding License Transfer Application ML21117A0342021-05-0505 May 2021 Request for Additional Information Regarding Proposed Alternative to Use ASME Code Case N-893 ML21062A0652021-03-0101 March 2021 NRR E-mail Capture - Exelon Generation Company, LLC - Request for Additional Information Regarding Proposed Fleet Alternative to Documentation Requirements for Pressure Retaining Bolting ML21057A1022021-02-25025 February 2021 Notification of NRC Fire Protection Team Inspection Request for Information; Inspection Report 05000456/2021010; 05000457/2021010 ML21049A2572021-02-18018 February 2021 Request for Additional Information Byron/Dresden Proposed Changes to Site Emergency Plans to Support Post-Shutdown and Permanently Defueled Conditions (EPID-2020-LLA-0240 & EPID-2020-LLA-0237) ML21029A3302021-01-29029 January 2021 NRR E-mail Capture - Exelon Generation Company, LLC - Request for Additional Information Regarding Fleet Alternative Request to Use ASME Code Case N-885 ML21020A1292021-01-20020 January 2021 Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000456/2021002; 05000457/2021002 ML21004A1452020-12-30030 December 2020 NRR E-mail Capture - Request for Additional Information Regarding Relief Requests Braidwood I4R-11 and Byron I4R-18 ML20289A1142020-10-0909 October 2020 NRR E-mail Capture - Preliminary RAIs for LAR Regarding Non-conservative TS EDG Frequency Tolerance ML20153A7042020-06-0101 June 2020 NRR E-mail Capture - Preliminary RAI for Fleet Request to Use Alternative OMN-26 ML20104C1452020-04-10010 April 2020 NRR E-mail Capture - Preliminary RAIs for Exelon'S April 6, 2020, Application to Defer Braidwood, Unit 2, Steam Generator Inspections ML20023A0812020-01-23023 January 2020 NRR E-mail Capture - RAIs for L-2019-LLA-0201 - Braidwood, Units 1 and 2, LAR to Revise TS 3.7.9, Ultimate Heat Sink ML19350B2952019-12-16016 December 2019 NRR E-mail Capture - Draft Request for Additional Information Regarding Braidwood Station, Units 1 and 2, Impractical Inservice Inspection Requirements (L-2019-LLA-0081) ML19275H1362019-10-0202 October 2019 NRR E-mail Capture - Exelon Generation Company, LLC - Request for Additional Information Regarding Request to Use ASME Code Case N-879 ML19252C1542019-08-22022 August 2019 NRR E-mail Capture - Issuance of the Remainder of Preliminary RAIs for Braidwood/Byron TSTF-505 Application ML19232A2242019-08-0707 August 2019 NRR E-mail Capture - Partial Issuance of Final RAIs for Braidwood/Byron TSTF-505 Application ML19207A0672019-07-26026 July 2019 NRR E-mail Capture - Partial Issuance of Preliminary RAIs for Braidwood/Byron TSTF-505 Application ML19179A0612019-07-19019 July 2019 Three Mile Point 1 - Supplemental Information Needed to Proposed Alternative to Use ASME Code Case N-879 ML19128A2362019-05-0202 May 2019 NON- PROPRIETARY- Request for Additional Information- Amendment Request Regarding Utilization of Tvel TVS-K Lead Test Assemblies Braidwood Station, Units 1 and 2 ML19066A0432019-03-0707 March 2019 NRR E-mail Capture - Preliminary RAIs for Quality Assurance Review of Braidwood Tvel LTA Application ML18324A8072018-12-12012 December 2018 Supplemental Information Needed for Acceptance of Requested Licensing Action One-Time Extension of Technical Specification 3.8.1, AC Sources-Operating, A2 Completion Time ML18192C1712018-07-11011 July 2018 NRR E-mail Capture - Preliminary Request for Additional Information Regarding Braidwood Station, Units 1 and 2, Relief Request IR4-03 ML18190A4072018-07-0505 July 2018 NRR E-mail Capture - Preliminary Request for Additional Information Regarding Braidwood Station, Units 1 and 2, Relief Request IR4-06 ML18150A6902018-05-30030 May 2018 NRR E-mail Capture - Preliminary RAIs Regarding Braidwood TORMIS Amendment Request ML18149A2842018-05-24024 May 2018 NRR E-mail Capture - B/B 50.69 RAI - Potential Typo ML18135A2202018-05-15015 May 2018 NRR E-mail Capture - Preliminary RAIs for Braidwood Relief Request IR4-05 ML18129A1082018-05-0909 May 2018 NRR E-mail Capture - Preliminary RAIs for Braidwood and Byron Stations 50.69 Amendment ML18067A1482018-03-0808 March 2018 Enclosurequest for Additional Information (Letter to P. R. Simpson Request for Additional Information Regarding Exelon Generating Company, Llc'S Decommissioning Funding Plan Update for Independent Spent Fuel Storage Installation) ML18009B0012018-01-0808 January 2018 Request for Information for an NRC Design Bases Assurance Inspection (Program): Implementation of the Environmental Qualification Program Inspection Report 05000456/2018012; 05000457/2018012 (DRS-J.Bozga) ML17276A0782017-09-27027 September 2017 NRR E-mail Capture - Request for Additional Information Regarding TSTF-547 Supported Amendment ML17228A7972017-08-16016 August 2017 Notification of an NRC Biennial Licensed Operator Requalification Program Inspection and Request for Information (Meb) ML17179A2852017-06-28028 June 2017 NRR E-mail Capture - Request for Additional Information Regarding Braidwood and Byron Amendments to Remove Obsolete License and Technical Specification Items 2023-07-10
[Table view] |
See also: IR 05000456/2021010
Text
February 25, 2021
Mr. David Rhoades
Senior VP, Exelon Generation Company, LLC
President and CNO, Exelon Nuclear
4300 Winfield Road
Warrenville, IL 60555
SUBJECT: BRAIDWOOD GENERATING STATION, UNITS 1 AND 2 - NOTIFICATION OF
NRC FIRE PROTECTION TEAM INSPECTION REQUEST FOR INFORMATION;
INSPECTION REPORT 05000456/2021010; 05000457/2021010
Dear Mr. Rhoades:
The purpose of this letter is to notify you that the U.S. Nuclear Regulatory Commission (NRC)
Region III staff will conduct a Fire Protection Team Inspection (FPTI) at your Braidwood
Generating Station, Units 1 and 2 beginning May 24, 2021. The inspection will be conducted in
accordance with IP 71111.21N.05, Fire Protection Team Inspection (FPTI), dated
June 12, 2019.
The inspection will verify that plant Systems, Structures, and Components (SSCs) and/or
administrative controls credited in the approved Fire Protection Program (FPP) can perform
their licensing basis function.
The schedule for the inspection is as follows:
- Preparation week (R-III office): May 17, 2021
- Week 1 of onsite inspection: May 24 - 28, 2021
- Week 2 of onsite inspection: June 17 - 21, 2021
Experience has shown that the baseline fire protection team inspections are extremely resource
intensive, both for the NRC inspectors and the licensee staff. In order to minimize the
inspection impact on the site and to ensure a productive inspection for both organizations, we
have enclosed a request for documents needed for the inspection. These documents have
been divided into three groups.
The first group lists information necessary to aid the inspection team in choosing specific focus
areas for the inspection and to ensure that the inspection team is adequately prepared for the
inspection. It is requested that this information be provided to the lead inspector via mail or
electronically no later than April 5, 2021.
The second group of requested documents consists of those items that the team will review, or
need access to, during the inspection. Please have this information available by the first day of
the first onsite inspection week May 24, 2021.
D. Rhoades -2-
The third group lists the information necessary to aid the inspection team in tracking issues
identified as a result of the inspection. It is requested that this information be provided to the
lead inspector as the information is generated during the inspection.
It is important that all of these documents are up to date and complete in order to minimize the
number of additional documents requested during the preparation and/or the onsite portions of
the inspection.
The lead inspector for this inspection is Mr. Jamie Benjamin. If there are any questions about
the inspection or the material requested, please contact the lead inspector at 630-829-9747 or
via e-mail at Jamie.Benjamin@nrc.gov.
This letter, its enclosure, and your response (if any) will be made available for public inspection
and copying at http://www.nrc.gov/reading-rm/adams.html and at the NRC Public Document
Room in accordance with 10 CFR 2.390, Public Inspections, Exemptions, Requests for
Withholding.
Sincerely,
/RA/
Jamie Benjamin, Reactor Inspector
Engineering Branch 2
Division of Reactor Safety
Docket Nos. 50-456 and 50-457
License Nos. NPF-72 and NPF-77
Enclosure:
Information Request for Fire Protection
Team Inspection
cc: Distribution via LISTSERV
D. Rhoades -3-
Letter to David Rhoades from Jamie Benjamin dated February 25, 2021.
SUBJECT: BRAIDWOOD GENERATING STATION, UNITS 1 AND 2 - NOTIFICATION OF
NRC FIRE PROTECTION TEAM INSPECTION REQUEST FOR INFORMATION;
INSPECTION REPORT 05000456/2021010; 05000457/2021010
DISTRIBUTION:
Jessie Quichocho
Mark Haire
RidsNrrDorlLpl3
RidsNrrPMBraidwood Resource
RidsNrrDroIrib Resource
John Giessner
Kenneth OBrien
Jamnes Cameron
Allan Barker
DRPIII
DRSIII
ADAMS Accession Number: ML21057A102
Publicly Available Non-Publicly Available Sensitive Non-Sensitive
OFFICE RIII
NAME JBenjamin:mb
via e-mail
DATE 02/25/2021
OFFICIAL RECORD COPY
FIRE PROTECTION TEAM INSPECTION SUPPORTING DOCUMENTATION
I. Information Requested Prior to the Inspection Preparation Week
The following information is requested by April 5, 2021. If you have any questions
regarding this request, please call the lead inspector as soon as possible. All information
should be sent to Jamie Benjamin (e-mail address Jamie.Benjamin@nrc.gov). Electronic
media is preferred (e.g. via Share File System).
1. One set of hard-copy documents for facility layout drawings which identify plant fire area
delineation; areas protected by automatic fire suppression and detection; and locations
of fire protection equipment.
2. Licensing Information:
a. All NRC Safety Evaluation Reports (SERs) applicable to fire protection (specifically
including those SERs referenced by the plant fire protection license condition) and all
licensing correspondence referenced by the SERs;
b. All licensing correspondence associated with the comparison to Standard Review
Plan (NUREG-0800), Section 9.5.1 or equivalent for licensing purposes;
c. Exemptions from 10 CFR 50.48 and 10 CFR Part 50, Appendix R, and associated
licensing correspondence;
d. For pre-1979 plants, all licensing correspondence associated with those sections of
10 CFR Part 50, Appendix R, that are not applicable to the plant under
10 CFR 50.48(b)(1). Specifically, the licensing correspondence associated with
those fire protection features proposed or implemented by the licensee that have
been accepted by the NRC staff as satisfying the provisions of Appendix A to Branch
Technical Position (BTP) APCSB 9.5-1 reflected in the NRC fire protection SERs
issued before February 19, 1981, (10 CFR 50.48(b)(1)(i)); or those fire protection
features, which were accepted by the NRC staff in comprehensive fire protection
SERs issued before Appendix A to BTP APCSB 9.5-1 was published in August 1976
(10 CFR 50.48(b)(1)(ii)); and
e. The final safety analysis report sections applicable to fire protection, FHA, and SSA
in effect at the time of original licensing.
3. Fire Protection Program:
a. A listing of changes made to the FPP since the last triennial fire protection
inspection;
b. For pre-1979 plants, a listing of the protection methodologies identified under
10 CFR Part 50, Appendix R, Section III.G used to achieve compliance for fire
zones/areas. That is, please specify whether 3-hour rated fire barriers;
(Section III.G.2.a), 20-foot separation along with detection and suppression;
(Section III.G.2.b), 1-hour rated fire barriers with detection and suppression;
(Section III.G.2.c), or alternative shutdown capability; (Section III.G.3) is used as a
strategy for each selected fire zone/area;
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FIRE PROTECTION TEAM INSPECTION SUPPORTING DOCUMENTATION
c. A list of Generic Letter 86-10 evaluations (i.e., a list of adverse to safe shutdown
evaluations);
d. A list of applicable codes and standards related to the design of plant fire protection
features. The list should include National Fire Protection Association (NFPA) code
versions committed to (i.e., the NFPA Codes of Record);
e. List of plant deviations from code commitments and associated evaluations;
f. Fire Protection Program and/or Fire Protection Plan document;
g. (If available) Fire Probabilistic Risk Assessment (PRA) Summary Report or full PRA
document (if summary document not available);
h. List of the top 25 highest fire CDF scenarios for each unit;
i. List of Fire Areas/Zones ranked by contribution to CDF. i.e., ranking of highest to
lowest risk fire areas/zones;
j. List of the top 25 highest fire LERF scenarios for each unit; and
k. Risk ranking of operator actions and/or recovery actions from your site-specific PRA
sorted by RAW and human reliability worksheets for these items.
4. Facility Information:
a. Piping and instrumentation (flow) diagrams showing the components used to achieve
and maintain hot standby and cold shutdown for fires outside the control room, and
those components used for those areas requiring alternative shutdown capability;
b. One-line schematic drawings of the electrical distribution system for 4160 Volts
alternating current (Vac) down to 480Vac;
c. One-line schematic drawings of the electrical distribution system for 250 Volts direct
current (Vdc) and 125Vdc systems as applicable;
d. Logic diagrams showing the components used to achieve and maintain hot standby
and cold shutdown; and
e. Safe shutdown cable routing database (requested electronically, such as on compact
disc, if available).
5. Operations Response for Fire Protection:
a. Plant operating procedures which specify the initial operations response to a fire
alarm or annunciator.
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FIRE PROTECTION TEAM INSPECTION SUPPORTING DOCUMENTATION
6. Corrective Actions:
a. Listing of open and closed fire protection condition reports (i.e., problem identification
forms and their resolution reports) since the date of the last triennial fire protection
inspection; and
b. List of current fire impairments, including duration.
7. General Information:
a. A listing of abbreviations and/or designators for plant systems;
b. Organization charts of site personnel down to the level of fire protection staff
personnel; and
c. A phone list for onsite licensee personnel.
II. Information Requested to Be Available on First Day of the First Onsite
Inspection Week (May 24, 2021)
The following information is requested to be provided on the first day of inspection. It is
requested that this information be provided on three sets of CDs (searchable, if possible).
1. Program Procedures:
a. Procedures for:
i. Administrative controls (such as allowed out of service times and compensatory
measures) for fire protection systems and components;
ii. Control of transient combustibles; and
iii. Control of hot work.
b. List of maintenance and surveillance testing procedures for alternative shutdown
capability and fire barriers, detectors, pumps, and suppression systems; and
c. List of maintenance procedures which routinely verify fuse breaker coordination in
accordance with the post-fire safe shutdown coordination analysis.
2. Design and Equipment Information (for only selected fire zone/area(s) and/or SSCs
to be determined during inspection preparation week):
a. Coordination calculations and/or justifications that verify fuse/breaker coordination for
SSCs that are fed off of the same electrical buses as components in the protected
safe shutdown train;
b. Copies of significant fire protection and post-fire safe shutdown related design
change package descriptions (including their associated 10 CFR 50.59 evaluations)
and Generic Letter (GL) 86-10 (or adverse to safe shutdown) evaluations;
c. Gaseous suppression system pre-operational testing, if applicable, for selected fire
zones/areas;
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FIRE PROTECTION TEAM INSPECTION SUPPORTING DOCUMENTATION
d. Hydraulic calculations and supporting test data which demonstrate operability for
water suppression systems;
e. Alternating current (ac) coordination calculations for 4160Vac down to 480Vac
electrical systems; and
f. List of all fire protection or Appendix R calculations.
3. Assessment and Corrective Actions:
The three most recent fire protection Quality Assurance audits and/or fire protection self-
assessments.
4. Any updates to information previously provided.
5. Classic Fire Protection (for only selected fire zone/area(s) and/or SSCs to be
determined during inspection preparation week):
a. Copy of fire protection program implementing procedures (e.g., administrative
controls, surveillance testing, and fire brigade);
b. Pre-fire plans for selected fire area(s); and
c. List of fire protection system design changes completed in the last three years.
6. Electrical (for only selected fire zone/area(s) and/or SSCs to be determined during
inspection preparation week):
a. Nuclear safety circuit coordination analysis for fuse and breaker coordination of safe
shutdown components;
b. Administrative or configuration control procedures that govern fuse replacement
(e.g., fuse control procedures);
c. Maintenance procedures that verify breaker over-current trip settings to ensure
coordination remains functional, for post-fire nuclear safety capability components;
d. Last surveillance demonstrating operability of those components operated from the
primary control stations;
e. Schematic or elementary diagrams for circuits (only for selected SSCs) to be
reviewed (C-size paper drawings);
f. Cable routing for components and equipment credited for post-fire nuclear safety
capability systems and components;
g. List of post-fire nuclear safety capability system and component design changes
completed in the last three years; and
h. List of identified fire induced circuit failure analyses.
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FIRE PROTECTION TEAM INSPECTION SUPPORTING DOCUMENTATION
7. Operations:
a. List of procedures that implement Cold Shutdown Repairs (if applicable for selected
fire area);
b. For Cold Shutdown Repairs, provide the following:
i. Procedure for inventory and inspection (i.e., needed tools, material, etc.); and
ii. Most recent inspection and inventory results.
c. List of licensed operator Job Performance Measures for operator actions required to
achieve and maintain post-fire nuclear safety performance criteria (for selected SSCs
and fire area);
d. For Radio communications, provide the following:
i. Communications Plan for firefighting and post-fire safe shutdown manual actions;
ii. Repeater locations;
iii. Cable routing for repeater power supply cables;
iv. Radio coverage test results; and
v. Radio Dead Spot locations in the plant.
e. Environmental and habitability evaluations for post-fire operator actions
(temperature, smoke, humidity, SCBAs, etc.).
8. Administrative Control, Oversight, and Corrective Action Programs:
a. Self-assessments, peer assessments, and audits of fire protection activities for
the last three years;
b. Self-assessments, peer assessments, and audits of post-fire nuclear safety
capability methodology for the last three years; and
c. List of fire event analysis reports for the last three years.
9. Any updates to information previously provided.
III. Information Requested to Be Provided Throughout the Inspection
1. Copies of any corrective action documents generated as a result of the inspection teams
questions or queries during this inspection.
2. Copies of the list of questions submitted by the inspection team members and the
status/resolution of the information requested (provided daily during the inspection to
each inspection team member).
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