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Category:Letter type:BW
MONTHYEARBW240053, Revised 2022 Annual Radioactive Effluent Release Report2024-09-0606 September 2024 Revised 2022 Annual Radioactive Effluent Release Report BW240056, Day Inservice Inspection Report for Interval 4, Period 2, (A1R24)2024-08-28028 August 2024 Day Inservice Inspection Report for Interval 4, Period 2, (A1R24) BW240027, Independent Spent Fuel Storage Installation Annual Radioactive Effluent Release Report for April 2023 to March 20242024-05-15015 May 2024 Independent Spent Fuel Storage Installation Annual Radioactive Effluent Release Report for April 2023 to March 2024 BW240025, Cancellation of Licensee Event Report 2023-001-00 - Train B Auxiliary Feedwater Pump Was Inoperable Due to Degraded Oil in the Crank Case2024-04-26026 April 2024 Cancellation of Licensee Event Report 2023-001-00 - Train B Auxiliary Feedwater Pump Was Inoperable Due to Degraded Oil in the Crank Case BW240020, Annual Dose Report for 20232024-04-17017 April 2024 Annual Dose Report for 2023 BW240013, Provides Requested Information from March 7, 2024 Regulatory Information Conference2024-03-18018 March 2024 Provides Requested Information from March 7, 2024 Regulatory Information Conference BW240003, Regulatory Commitment Change Summary Report2024-02-0909 February 2024 Regulatory Commitment Change Summary Report BW240002, Response to Nrg Inspection Report and Preliminary Greater than Green Finding and Apparent Violation2024-02-0202 February 2024 Response to Nrg Inspection Report and Preliminary Greater than Green Finding and Apparent Violation BW230058, Submittal of Integrated Initial License Training Written Examination Materials2023-12-20020 December 2023 Submittal of Integrated Initial License Training Written Examination Materials BW230048, Outage 23 and Unit 2 Refueling Outage 23 Steam Generator Tube Inspection Reports to Reflect TSTF-577 Reporting Requirements2023-11-0101 November 2023 Outage 23 and Unit 2 Refueling Outage 23 Steam Generator Tube Inspection Reports to Reflect TSTF-577 Reporting Requirements BW230046, 10 CFR 72.48 Evaluation Summary Report2023-10-0909 October 2023 10 CFR 72.48 Evaluation Summary Report BW230045, Registration of Use of Casks to Store Spent Fuel2023-09-27027 September 2023 Registration of Use of Casks to Store Spent Fuel BW230039, Inservice Inspection Summary Report2023-08-11011 August 2023 Inservice Inspection Summary Report BW230024, Independent Spent Fuel Storage Installation Annual Radioactive Effluent Release Report2023-05-12012 May 2023 Independent Spent Fuel Storage Installation Annual Radioactive Effluent Release Report BW230007, Regulatory Commitment Change Summary Report2023-02-10010 February 2023 Regulatory Commitment Change Summary Report BW230003, Inservice Inspection Summary Report2023-01-18018 January 2023 Inservice Inspection Summary Report BW220080, 10 Gfr 50.59 Summary Report2022-12-15015 December 2022 10 Gfr 50.59 Summary Report BW220078, Submittal of Licensee Event Report 2022-001-00 - Liquid Penetrant Indications in Control Rod Drive Mechanism Nozzle Seal Weld Repair Due to Subsurface Weld Defects Opening Up from Thermal and Pressure Stresses During Operation2022-11-30030 November 2022 Submittal of Licensee Event Report 2022-001-00 - Liquid Penetrant Indications in Control Rod Drive Mechanism Nozzle Seal Weld Repair Due to Subsurface Weld Defects Opening Up from Thermal and Pressure Stresses During Operation BW220048, Registration of Use of Casks to Store Spent Fuel2022-08-10010 August 2022 Registration of Use of Casks to Store Spent Fuel BW220044, Registration of Use of Casks to Store Spent Fuel2022-07-0606 July 2022 Registration of Use of Casks to Store Spent Fuel BW220041, Registration of Use of Casks to Store Spent Fuel2022-06-29029 June 2022 Registration of Use of Casks to Store Spent Fuel BW220037, Registration of Use of Casks to Store Spent Fuel2022-06-15015 June 2022 Registration of Use of Casks to Store Spent Fuel BW220028, Independent Spent Fuel Storage Installation Annual Radioactive Effluent Release Report2022-05-13013 May 2022 Independent Spent Fuel Storage Installation Annual Radioactive Effluent Release Report BW220024, Annual Dose Report for 20212022-04-14014 April 2022 Annual Dose Report for 2021 BW220011, Inservice Inspection Summary Report2022-01-31031 January 2022 Inservice Inspection Summary Report BW210083, Revision to Unit 1 Inservice Inspection Summary Report2021-12-15015 December 2021 Revision to Unit 1 Inservice Inspection Summary Report BW210082, Notification of Deviation from Electric Power Research Institute Materials Reliability Program 2019-008, Interim Guidance for NEI 03-08 Needed Requirements for Us PWR Plants for Management of Thermal Fatigue in Non-solable Reactor2021-12-15015 December 2021 Notification of Deviation from Electric Power Research Institute Materials Reliability Program 2019-008, Interim Guidance for NEI 03-08 Needed Requirements for Us PWR Plants for Management of Thermal Fatigue in Non-solable Reactor BW210060, National Pollutant Discharge Elimination System2021-08-20020 August 2021 National Pollutant Discharge Elimination System BW210048, Submittal of Analytical Evaluation in Accordance with ASME Code Section XI2021-07-0707 July 2021 Submittal of Analytical Evaluation in Accordance with ASME Code Section XI BW210030, Independent Spent Fuel Storage Installation Annual Radioactive Effluent Release Report2021-05-15015 May 2021 Independent Spent Fuel Storage Installation Annual Radioactive Effluent Release Report BW210026, Annual Dose Report for 20202021-04-15015 April 2021 Annual Dose Report for 2020 BW200090, CFR 50.59 Summary Report2020-12-15015 December 2020 CFR 50.59 Summary Report BW200095, Inservice Inspection Summary Report2020-12-0909 December 2020 Inservice Inspection Summary Report BW200082, Registration of Use of Casks to Store Spent Fuel2020-10-21021 October 2020 Registration of Use of Casks to Store Spent Fuel BW200072, Registration of Use of Casks to Store Spent Fuel2020-09-23023 September 2020 Registration of Use of Casks to Store Spent Fuel BW200069, Request Registration of Use of Casks to Store Spent Fuel2020-08-27027 August 2020 Request Registration of Use of Casks to Store Spent Fuel BW200057, Bwd 2020 Ile Post-Exam Package Cover2020-06-27027 June 2020 Bwd 2020 Ile Post-Exam Package Cover BW200038, Independent Spent Fuel Storage Installation Annual Radioactive Effluent Release Report2020-05-15015 May 2020 Independent Spent Fuel Storage Installation Annual Radioactive Effluent Release Report BW200035, Annual Dose Report for 20192020-04-29029 April 2020 Annual Dose Report for 2019 BW190114, Ile Outline Submittal Letter2019-12-16016 December 2019 Ile Outline Submittal Letter 2024-09-06
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Exelon Generation Company, LLC
~+ Exelon Generation Bralctwood Nuclear Power Station 35100 South R.oute 53, Suite 84 Braceville, IL 6040Nl619 www.exe!oncorp,com NEI 03-08 December 15, 2021 BW210082 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Braidwood Station, Unit 1 Renewed Facility Operating License No. NPF-72 NRG Docket No. STN 50-456
Subject:
Notification of Deviation from Electric Power Research Institute (EPRI) Materials Reliability Program (MRP) 2019-008, "Interim Guidance for NEI 03-08 Needed Requirements for US PWR Plants for Management of Thermal Fatigue in Non-lsolable Reactor Coolant System Branch Lines" In accordance with Appendix B, Section 8.1.c of Nuclear Energy Institute (NEI) 03-08,
. "Guideline for the Management of Materials Issues," Revision 4, Exelon Generation Company, LLC (EGG) is notifying the U.S. Nuclear Regulatory Commission (NRG) that Braidwood Station, Unit 1 has processed a deviation from "Needed" interim guidance (IG)#2 in EPRI Document MRP 2019-008, "Interim Guidance for NEI 03-08 Needed Requirements for US PWR Plants for Management of Thermal Fatigue in Non-lsolable Reactor Coolant System (RCS) Branch Lines,"
with appropriate justification and documentation.
MRP 2019-008 "Needed" requirements IG#2 requires a one-time examination of the Residual Heat Removal (RHR) suction lines that branch off the Reactor Coolant System (RCS) hot legs (1A and 1C) . The one-time examination for the RHR suction line from the 1A RCS hot leg will not be performed by the required time frame of within two refueling outages after August 1, 2019. The examination has been deferred to refueling outage A 1R23 (Fall 2022).
NEI 03-08 allows deviation from "Needed" elements with the appropriate justification and documentation. The deviation has been documented in accordance with EGC's corrective action program and approved by the appropriate levels of EGG management. The Attachment provides the EGG Braidwood Unit 1 technical justification for the deviation from MRP 2019-008.
In accordance with NEI 03-08, this letter is being transmitted for information only. EGG is not requesting any action from the NRG.
December 15, 2021 BW210082 Page2 This letter contains no new regulatory commitments.
If you have any questions concerning this letter, please contact Richard Schliessmann, acting Regulatory Assurance Manager, at (815) 417-2820.
Respectfully, Keenan JQ h n P* DN:cn=Keenan,John Dig. ita. lly signed by Keenan, John P.
P.
1 Date: 2021.12.14 06:21 :39-06'00' John Keenan Site Vice President .
Braidwood Nuclear Generating Station
Attachment:
Braidwood Unit 1 Justification for the Deviation from MRP 2019-008, Technical Evaluation 635273 cc: NRC Regional Administrator, Region Ill NRC Senior Resident Inspector- Braidwood Station NRC Project Manager - Braidwood Station Illinois Emergency Management Agency- Division of Nuclear Safety