ML17024A036
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| ML17024A036 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley, Browns Ferry, Byron, Arkansas Nuclear, Braidwood, Brunswick, Bellefonte  |
| Issue date: | 12/31/2016 |
| From: | Exelon Generation Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| Download: ML17024A036 (298) | |
Similar Documents at Beaver Valley, Browns Ferry, Byron, Arkansas Nuclear, Braidwood, Brunswick, Bellefonte | |
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Category:Report
MONTHYEARBW240069, CFR 50.59 Changes, Tests, and Experiments Summary Report2024-12-13013 December 2024
[Table view]CFR 50.59 Changes, Tests, and Experiments Summary Report 1CAN112401, Safety Analysis Report (SAR) Amendment 32, Technical Requirements Manual (Trm), Technical Specifications (TS) Bases, 10 CFR 50.59 Report, and Commitment Change Summary Report2024-11-11011 November 2024 Safety Analysis Report (SAR) Amendment 32, Technical Requirements Manual (Trm), Technical Specifications (TS) Bases, 10 CFR 50.59 Report, and Commitment Change Summary Report 2CAN112403, Affidavit for Corrosion Evaluation of ANO-2 RVCH CEDM Idtb Weld Nozzle Penetration Repair, Document Number 51-9384397-0012024-10-31031 October 2024 Affidavit for Corrosion Evaluation of ANO-2 RVCH CEDM Idtb Weld Nozzle Penetration Repair, Document Number 51-9384397-001 BYRON 2024-0054, Independent Spent Fuel Storage Installation Annual Radioactive Effluent Release Report2024-10-24024 October 2024 Independent Spent Fuel Storage Installation Annual Radioactive Effluent Release Report ML24295A1232024-10-21021 October 2024 Enclosure 3: Relief Request ANO2-RR-24-001, Revision 0 (Non-Proprietary) 1CAN072401, Request for Review and Approval of Changes to the Safety Analysis Report and to a Confirmatory Order Clarifying an Alternate Means of Compliance for Pressurizer Heaters Emergency Power Supply2024-07-0202 July 2024 Request for Review and Approval of Changes to the Safety Analysis Report and to a Confirmatory Order Clarifying an Alternate Means of Compliance for Pressurizer Heaters Emergency Power Supply ML24179A0282024-06-26026 June 2024 Evaluation of Effects of Out-of-Limits Condition as Described in IWB-3720(a) RS-24-044, License Amendment to Transition to Framatome Gaia Fuel and Exemptions to 10 CFR 50.46 and 10 CFR 50 Appendix K. Attachments 1 to 11 Enclosed2024-05-28028 May 2024 License Amendment to Transition to Framatome Gaia Fuel and Exemptions to 10 CFR 50.46 and 10 CFR 50 Appendix K. Attachments 1 to 11 Enclosed BW240017, EC 640658, Revision 0 Technical Evaluation for NEI 03-08 Deviation of Control Rod Guide Tube Guide Card Wear Measurements2024-04-0303 April 2024 EC 640658, Revision 0 Technical Evaluation for NEI 03-08 Deviation of Control Rod Guide Tube Guide Card Wear Measurements ML24094A2702024-04-0303 April 2024 MDMP Deviation Form ML24071A1152024-03-31031 March 2024 U.S. Department of Energy, Office of Legacy Management, 2023 Annual Site Inspection and Monitoring Report for Uranium Mill Tailings Radiation Control Act Title I Disposal Sites BW240007, Attachment 5: BW-MISC-062 Rev. 0 - Braidwood Station Unit 2 Diesel Driven AFW MAAP Calculations2024-02-29029 February 2024 Attachment 5: BW-MISC-062 Rev. 0 - Braidwood Station Unit 2 Diesel Driven AFW MAAP Calculations ML24057A3062024-02-24024 February 2024 Attachment 4: BW-SDP-006 Rev. 0 - Braidwood 2B AF Pump Fuel Oil Leak SOP Sensitivities ML24047A2092024-02-22022 February 2024 Calendar Year 2023 Baseline Inspection Completion ML24057A3042024-01-22022 January 2024 Attachment 2: EC 640630 Rev. 000 - Documentation of Test Results with Diluted Lube Oil from Fuel In-Leakage - 28 AF Diesel Engine Past Operability ML24057A3052023-12-12012 December 2023 Attachment 3: EC 640287 Rev. 000 - Past Operability Test Plan Acceptance Related to 2AF01PB-K BW230054, EC 639996 (Byron), Revision 1 and 640160 (Braidwood), Revision 0, Technical Evaluation for NEI 03-08 Deviation of Baffle-Former Bolts Volumetric Examinations for Byron and Braidwood2023-11-17017 November 2023 EC 639996 (Byron), Revision 1 and 640160 (Braidwood), Revision 0, Technical Evaluation for NEI 03-08 Deviation of Baffle-Former Bolts Volumetric Examinations for Byron and Braidwood ML23321A0462023-11-17017 November 2023 Attachment 2: MDMP Deviation Form RS-23-094, Relief Request I4R-24, Alternative for Post-Peening Reexamination Frequency for Reactor Pressure Vessel Head Penetration Nozzle Number 752023-09-29029 September 2023 Relief Request I4R-24, Alternative for Post-Peening Reexamination Frequency for Reactor Pressure Vessel Head Penetration Nozzle Number 75 L-23-188, Energy Harbor Nuclear Corp., Supplement to Application for Order Consenting to Transfer of Licenses and Conforming License Amendments2023-08-0707 August 2023 Energy Harbor Nuclear Corp., Supplement to Application for Order Consenting to Transfer of Licenses and Conforming License Amendments ML23192A4472023-07-31031 July 2023 Staff Assessment of Updated Seismic Hazards at TVA Sites Following the NRC Process for the Ongoing Assessment of Natural Hazards Information 1CAN062304, Supplement Related to License Amendment Request to Remove Technical Specification Condition Allowing Two Reactor Coolant Pump Operation2023-06-29029 June 2023 Supplement Related to License Amendment Request to Remove Technical Specification Condition Allowing Two Reactor Coolant Pump Operation ML23180A1082023-06-20020 June 2023 ANO Unit 1 SAR Amendment 31, TRM, TS Bases, 10 CFR 50.59 Report, and Commitment Change Summary Report 1CAN062302, Enclosure 2: ANO-1 SAR Amendment 31 - Redacted Version2023-06-20020 June 2023 Enclosure 2: ANO-1 SAR Amendment 31 - Redacted Version 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 ML23025A0752023-01-25025 January 2023 American Society of Mechanical Engineers, Section XI, Third 10 Year Inspection Interval, Inservice Inspection, System Pressure Test, Containment Inspection, and Repair and Replacement Programs, Owner’S Activity Report Cycle . ML23088A2172022-12-31031 December 2022 Relief Request for Half-Nozzle Repair of Reactor Vessel Closure Head Penetration 46 - Technical Report, ANP-4023NP, Revision 0, December 2022 ML22363A3922022-12-28028 December 2022 Cycle 14 Mellla+ Eigenvalue Tracking Data CNL-22-090, Request to Use a Later Edition of the American Society of Mechanical Engineers Operation and Maintenance Code and Alternative Requests for the Fifth Inservice Testing Interval2022-12-12012 December 2022 Request to Use a Later Edition of the American Society of Mechanical Engineers Operation and Maintenance Code and Alternative Requests for the Fifth Inservice Testing Interval CNL-22-100, To Request for License Amendment Regarding Application of Advanced Framatome Methodologies, and Adoption of TSTF-564 Revision 2 for Browns Ferry Nuclear Plant Units 1, 2, and 3,in Support of Atrium 11 Fuel Use at Browns Ferry (TS-535)2022-12-0909 December 2022 To Request for License Amendment Regarding Application of Advanced Framatome Methodologies, and Adoption of TSTF-564 Revision 2 for Browns Ferry Nuclear Plant Units 1, 2, and 3,in Support of Atrium 11 Fuel Use at Browns Ferry (TS-535) BW220062, Pressure and Temperature Limits Report (Ptlr), Revision 92022-10-20020 October 2022 Pressure and Temperature Limits Report (Ptlr), Revision 9 BYRON 2022-0071, Materials Reliability Program: Topical Report for Primary Water Stress Corrosion Cracking Mitigation by Surface Stress Improvement (MRP-335, Revision 3-A) Final Causal Report and Description of Corrective Action Assignment2022-10-13013 October 2022 Materials Reliability Program: Topical Report for Primary Water Stress Corrosion Cracking Mitigation by Surface Stress Improvement (MRP-335, Revision 3-A) Final Causal Report and Description of Corrective Action Assignment CNL-22-066, Request for License Amendment Regarding Application of Advanced Framatome Methodologies, and Adoption of TSTF-564 Revision 2 for in Support of Atrium 11 Fuel Use Supplement 3, Response to Request for Additional Information2022-07-18018 July 2022 Request for License Amendment Regarding Application of Advanced Framatome Methodologies, and Adoption of TSTF-564 Revision 2 for in Support of Atrium 11 Fuel Use Supplement 3, Response to Request for Additional Information L-22-154, Pressure and Temperature Limits Report Revision2022-07-0606 July 2022 Pressure and Temperature Limits Report Revision NMP1L3469, Constellation Energy Company, LLC, Request for Use of Honeywell Mururoa V4F1 R Supplied Air Suits2022-06-30030 June 2022 Constellation Energy Company, LLC, Request for Use of Honeywell Mururoa V4F1 R Supplied Air Suits RA-22-0165, Inservice Inspection Program Owners Activity Report for Refueling Outage 242022-06-0909 June 2022 Inservice Inspection Program Owners Activity Report for Refueling Outage 24 RS-22-071, License Renewal Response to Commitment 10 - 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Attachments 1 to 11 Enclosed ML24094A2702024-04-0303 April 2024 MDMP Deviation Form ML24047A2092024-02-22022 February 2024 Calendar Year 2023 Baseline Inspection Completion ML24057A3052023-12-12012 December 2023 Attachment 3: EC 640287 Rev. 000 - Past Operability Test Plan Acceptance Related to 2AF01PB-K BW230054, EC 639996 (Byron), Revision 1 and 640160 (Braidwood), Revision 0, Technical Evaluation for NEI 03-08 Deviation of Baffle-Former Bolts Volumetric Examinations for Byron and Braidwood2023-11-17017 November 2023 EC 639996 (Byron), Revision 1 and 640160 (Braidwood), Revision 0, Technical Evaluation for NEI 03-08 Deviation of Baffle-Former Bolts Volumetric Examinations for Byron and Braidwood ML23321A0462023-11-17017 November 2023 Attachment 2: MDMP Deviation Form L-23-188, Energy Harbor Nuclear Corp., Supplement to Application for Order Consenting to Transfer of Licenses and Conforming License Amendments2023-08-0707 August 2023 Energy Harbor Nuclear Corp., Supplement to Application for Order Consenting to Transfer of Licenses and Conforming License Amendments ML23025A0752023-01-25025 January 2023 American Society of Mechanical Engineers, Section XI, Third 10 Year Inspection Interval, Inservice Inspection, System Pressure Test, Containment Inspection, and Repair and Replacement Programs, Owner’S Activity Report Cycle . CNL-22-090, Request to Use a Later Edition of the American Society of Mechanical Engineers Operation and Maintenance Code and Alternative Requests for the Fifth Inservice Testing Interval2022-12-12012 December 2022 Request to Use a Later Edition of the American Society of Mechanical Engineers Operation and Maintenance Code and Alternative Requests for the Fifth Inservice Testing Interval RA-22-0165, Inservice Inspection Program Owners Activity Report for Refueling Outage 242022-06-0909 June 2022 Inservice Inspection Program Owners Activity Report for Refueling Outage 24 RS-22-071, License Renewal Response to Commitment 10 - Evaluation of Possible PWSCC Crack Initiation and Propagation in the Steam Generator Channel Head Assembly and Tube-to-Tubesheet Welds2022-06-0707 June 2022 License Renewal Response to Commitment 10 - Evaluation of Possible PWSCC Crack Initiation and Propagation in the Steam Generator Channel Head Assembly and Tube-to-Tubesheet Welds RS-22-047, Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors2022-04-0808 April 2022 Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors ML21349A1062021-12-15015 December 2021 Justification for the Deviation from MRP 2019-008, Technical Evaluation 635273 RS-21-112, Updated 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors2021-10-22022 October 2021 Updated 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors CNRO-2021-00023, Entergy Operations, Inc. - 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Copy ML20303A1752020-10-23023 October 2020 Proposed Relief Request from Section XI Repair/Replacement Documentation for Bolting Replacement of Pressure Retaining Bolting L-20-257, Request for One-Time Exemption from 10 CFR 50, Appendix E, Biennial Emergency Preparedness Exercise Requirements Due to COVID-19 Pandemic2020-09-22022 September 2020 Request for One-Time Exemption from 10 CFR 50, Appendix E, Biennial Emergency Preparedness Exercise Requirements Due to COVID-19 Pandemic 1CAN032001, Supplemental Information Related to License Amendment Request to Revise Loss of Voltage Relay Allowable Values2020-03-19019 March 2020 Supplemental Information Related to License Amendment Request to Revise Loss of Voltage Relay Allowable Values RA-19-0479, Supplement to Request for License Amendment Regarding Application of Advanced Framatome Methodologies2019-12-31031 December 2019 Supplement to Request for License Amendment Regarding Application of Advanced Framatome Methodologies 0CAN121901, Summary of Lost Specimens Investigation Report2019-12-0303 December 2019 Summary of Lost Specimens Investigation Report RA-19-0223, Annual Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models Pursuant to 10CFR 50.462019-05-30030 May 2019 Annual Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models Pursuant to 10CFR 50.46 L-19-053, Emergency Response Data System Data Point Library Update2019-02-20020 February 2019 Emergency Response Data System Data Point Library Update L-19-022, Report of Facility Changes, Tests and Experiments2019-02-13013 February 2019 Report of Facility Changes, Tests and Experiments ML18192C1522018-07-18018 July 2018 Review of Fall 2017 Steam Generator Tube Inservice Inspection Report L-18-037, Annual 10 CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models2018-06-18018 June 2018 Annual 10 CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models CNL-18-060, Completion of Required Action for NRC Order EA-13-109, Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions2018-05-31031 May 2018 Completion of Required Action for NRC Order EA-13-109, Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions BSEP 18-0044, Application of Dissimilar Metal Weld Full Structural Overlay - Reactor Pressure Vessel Nozzles N4A and N4D2018-04-11011 April 2018 Application of Dissimilar Metal Weld Full Structural Overlay - Reactor Pressure Vessel Nozzles N4A and N4D L-18-017, Request to Extend Enforcement Discretion Provided in Enforcement Guidance Memorandum 15-002 for Tornado-Generated Missile Protection Non-Conformances Identified in Response to Regulatory Issue Summary 2015-06, Tornado2018-03-15015 March 2018 Request to Extend Enforcement Discretion Provided in Enforcement Guidance Memorandum 15-002 for Tornado-Generated Missile Protection Non-Conformances Identified in Response to Regulatory Issue Summary 2015-06, Tornado ML18053A0232018-02-22022 February 2018 Compilation of Industry Provided Information on Anchor Darling Double Disc Gate Valve Population Affected by Flowserve, Part 21 Issue of Wedge Pin Failure on an Anchor Darling Double Disc Gate Valve in Report Format with Valve Count ML17214A0292018-02-12012 February 2018 Staff Assessment of Flooding Focused Evaluation ML17355A5612017-12-21021 December 2017 Ltr. 12/21/17 Response to Disputed Non-Cited Violation Documented in Byron Station, Units 1 and 2 - 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