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Category:Letter type:L
MONTHYEARL-24-025, Submittal of the Updated Final Safety Analysis Report, Revision 352024-09-25025 September 2024
Submittal of the Updated Final Safety Analysis Report, Revision 35
L-24-188, Submittal of Quality Assurance Program Manual, Revision 302024-08-27027 August 2024
Submittal of Quality Assurance Program Manual, Revision 30
L-24-186, Response to RAI for Exemption Request from 10 CFR 50.71(e)(4) Final Safety Analysis Update Schedule2024-08-15015 August 2024
Response to RAI for Exemption Request from 10 CFR 50.71(e)(4) Final Safety Analysis Update Schedule
L-24-032, Cycle 23 and Refueling Outage 23 Inservice Inspection Summary Report2024-07-15015 July 2024
Cycle 23 and Refueling Outage 23 Inservice Inspection Summary Report
L-24-063, License Amendment Request to Remove the Table of Contents from the Technical Specifications2024-07-0808 July 2024
License Amendment Request to Remove the Table of Contents from the Technical Specifications
L-24-024, Annual 10 CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models2024-06-19019 June 2024
Annual 10 CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models
L-23-214, Submittal of Relief Request for Impractical American Society of Mechanical Engineers Boiler and Pressure Vessel Code Section XI Examination Requirements2024-06-0505 June 2024
Submittal of Relief Request for Impractical American Society of Mechanical Engineers Boiler and Pressure Vessel Code Section XI Examination Requirements
L-24-019, Unit No.1 - Report of Facility Changes, Tests, and Experiments2024-05-22022 May 2024
Unit No.1 - Report of Facility Changes, Tests, and Experiments
L-24-072, Combined Annual Radiological Environmental Operating Report and Radioactive Effluent Release Report - 20232024-05-15015 May 2024
Combined Annual Radiological Environmental Operating Report and Radioactive Effluent Release Report - 2023
L-24-111, Response to Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations2024-05-15015 May 2024
Response to Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations
L-24-031, Unit No.1 - Steam Generator Tube Circumferential Crack Report - Spring 2024 Refueling Outage2024-05-14014 May 2024
Unit No.1 - Steam Generator Tube Circumferential Crack Report - Spring 2024 Refueling Outage
L-24-069, Occupational Radiation Exposure Report for Year 20232024-04-30030 April 2024
Occupational Radiation Exposure Report for Year 2023
L-24-018, Submittal of Core Operating Limits Report, Cycle 24, Revision 02024-04-16016 April 2024
Submittal of Core Operating Limits Report, Cycle 24, Revision 0
L-24-013, Annual Notification of Property Insurance Coverage2024-03-26026 March 2024
Annual Notification of Property Insurance Coverage
L-23-264, Request for Exemption from 10 CFR 50.71(e)(4) Final Safety Analysis Report Update Schedule2024-02-23023 February 2024
Request for Exemption from 10 CFR 50.71(e)(4) Final Safety Analysis Report Update Schedule
L-24-050, Retrospective Premium Guarantee2024-02-22022 February 2024
Retrospective Premium Guarantee
L-23-260, Corrections to the 2022 Combined Annual Radiological Environmental Operating Report and Radioactive Effluent Release Report for the Davis-Besse Nuclear Power Station2023-12-0707 December 2023
Corrections to the 2022 Combined Annual Radiological Environmental Operating Report and Radioactive Effluent Release Report for the Davis-Besse Nuclear Power Station
L-23-243, Independent Spent Fuel Storage Installation - Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-12-0606 December 2023
Independent Spent Fuel Storage Installation - Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation
L-23-215, Changes to Emergency Plan2023-10-19019 October 2023
Changes to Emergency Plan
L-23-205, Supplement to Application for Order Consenting to Transfer of Licenses and Conforming License Amendments2023-09-12012 September 2023
Supplement to Application for Order Consenting to Transfer of Licenses and Conforming License Amendments
L-23-172, Quality Assurance Program Manual2023-08-31031 August 2023
Quality Assurance Program Manual
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
L-23-175, Submittal of Fifth Ten Year Inservice Testing Program2023-08-0101 August 2023
Submittal of Fifth Ten Year Inservice Testing Program
L-23-034, 2022 Annual 10 CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models2023-06-13013 June 2023
2022 Annual 10 CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models
L-23-135, Response to Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations2023-05-31031 May 2023
Response to Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations
L-23-065, Annual Financial Report2023-05-22022 May 2023
Annual Financial Report
L-23-101, Combined Annual Radiological Environmental Operating Report and Radioactive Effluent Release Report for the Davis-Besse Nuclear Power Station - 20222023-05-12012 May 2023
Combined Annual Radiological Environmental Operating Report and Radioactive Effluent Release Report for the Davis-Besse Nuclear Power Station - 2022
L-23-131, Readiness for Resumption of NRC Supplemental Inspection2023-05-12012 May 2023
Readiness for Resumption of NRC Supplemental Inspection
L-23-092, Occupational Radiation Exposure Report for Year 20222023-04-27027 April 2023
Occupational Radiation Exposure Report for Year 2022
L-23-061, Submittal of the Decommissioning Funding Status Reports2023-03-31031 March 2023
Submittal of the Decommissioning Funding Status Reports
L-23-037, and Perry Nuclear Power Plant - Independent Spent Fuel Storage Installation Changes, Tests, and Experiments2023-03-29029 March 2023
and Perry Nuclear Power Plant - Independent Spent Fuel Storage Installation Changes, Tests, and Experiments
L-23-066, Annual Notification of Property Insurance Coverage2023-03-21021 March 2023
Annual Notification of Property Insurance Coverage
L-23-059, Response to Apparent Violation in NRC Inspection Report 05000346/2022091; EA 23-0022023-03-0909 March 2023
Response to Apparent Violation in NRC Inspection Report 05000346/2022091; EA 23-002
L-22-212, CFR 50.55a Request RP-5 Regarding Inservice Pump Testing2023-03-0606 March 2023
CFR 50.55a Request RP-5 Regarding Inservice Pump Testing
L-23-048, Response to Request for Additional Information Regarding Technical Specification 5.6.6 Steam Generator Tube Inspection 180-Day Report2023-03-0101 March 2023
Response to Request for Additional Information Regarding Technical Specification 5.6.6 Steam Generator Tube Inspection 180-Day Report
L-23-057, Energy Harbor Nuclear Corp Retrospective Premium Guarantee2023-02-20020 February 2023
Energy Harbor Nuclear Corp Retrospective Premium Guarantee
L-22-253, Submittal of Pressure and Temperature Limits Report, Revision 52023-01-10010 January 2023
Submittal of Pressure and Temperature Limits Report, Revision 5
L-22-284, Request for Notice of Enforcement Discretion for Technical Specification 3.7.9, Ultimate Heat Sink (UHS)2022-12-28028 December 2022
Request for Notice of Enforcement Discretion for Technical Specification 3.7.9, Ultimate Heat Sink (UHS)
L-22-211, Technical Specification 5.6.6 Steam Generator Tube Inspection 180-Day Report2022-09-29029 September 2022
Technical Specification 5.6.6 Steam Generator Tube Inspection 180-Day Report
L-22-216, Submittal of Pressure and Temperature Limits Report. Revision 42022-09-27027 September 2022
Submittal of Pressure and Temperature Limits Report. Revision 4
L-22-213, Occupational Radiation Exposure Report for Year 2021 - Correction2022-09-23023 September 2022
Occupational Radiation Exposure Report for Year 2021 - Correction
L-22-129, Submittal of the Updated Final Safety Analysis Report, Revision 342022-09-20020 September 2022
Submittal of the Updated Final Safety Analysis Report, Revision 34
L-22-194, Submittal of Supplemental Information for the Reanalysis for Protection Against Low Temperature Reactor Coolant System Overpressure Events2022-09-19019 September 2022
Submittal of Supplemental Information for the Reanalysis for Protection Against Low Temperature Reactor Coolant System Overpressure Events
L-22-203, Submittal of Evacuation Time Estimates2022-09-12012 September 2022
Submittal of Evacuation Time Estimates
L-22-050, Summary of Changes to the Energy Harbor Nuclear Corp. Quality Assurance Program Manual2022-08-0909 August 2022
Summary of Changes to the Energy Harbor Nuclear Corp. Quality Assurance Program Manual
L-22-152, Response to Request for Additional Information Regarding a License Amendment Request That Revises the Davis-Besse Nuclear Power Station Emergency Plan2022-07-0505 July 2022
Response to Request for Additional Information Regarding a License Amendment Request That Revises the Davis-Besse Nuclear Power Station Emergency Plan
L-22-068, Cycle 22 and Refueling Outage 22 Inservice Inspection Summary Report2022-06-30030 June 2022
Cycle 22 and Refueling Outage 22 Inservice Inspection Summary Report
L-22-037, 2021 Annual 10 CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models2022-06-30030 June 2022
2021 Annual 10 CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models
L-22-149, Post Accident Monitoring Report2022-06-23023 June 2022
Post Accident Monitoring Report
L-22-098, Withdrawal of Proposed Inservice Inspection Alternative RR-A22022-06-22022 June 2022
Withdrawal of Proposed Inservice Inspection Alternative RR-A2
2024-09-25
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FENOC 5501 North State Route 2 Oak Harbor, Ohio 43449 Mark B. Bezilla 419-321-7676 Vice President - Nuclear Fax: 419-321-7582 April 27, 2018 L-18-123 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001
SUBJECT:
Davis-Besse Nuclear Power Station, Unit No. 1 Docket No. 50-346, License No. NPF-3 Steam Generator Tube Circumferential Crack Report - Spring 2018 Refueling Outage In accordance with Davis-Besse Nuclear Power Station (DBNPS) License Condition 2.C(7), "Steam Generator Tube Circumferential Crack Report," FirstEnergy Nuclear Operating Company (FENOC) is required to submit an evaluation within 3 months following the completion of steam generator tube inservice inspection. The DBNPS SGs were replaced in 2014 with new Babcock and Wilcox Replacement Once Through Steam Generators (OTSG), and as a result, DBNPS is no longer licensed to perform repair reroll. Structural and accident induced leakage integrity are evaluated analytically based on the degradation mechanism's characteristics, including circumferential extent, axial length, and percent through-wall depth. All indications of tube degradation were evaluated against the large-break loss-of-coolant accident (LBLOCA) loading for leakage integrity. All reported indications met condition monitoring criteria, and there were no indications of circumferential cracking identified, demonstrating reasonable assurance that the performance criteria for LBLOCA loading will continue to be satisfied throughout the next operating cycle. Therefore, it is bounded by current analyses, does not result in a significant increase of radionuclide release in excess of 10 CFR 100 limits, and demonstrates that adequate margin and defense-in-depth continue to be maintained. This letter satisfies License Condition 2.C(7) for evaluating that the primary-to-secondary leakage following a LBLOCA continues to be acceptable.
There are no regulatory commitments contained in this letter. If there are any questions of if additional information is required, please contact Mr. Thomas A. Lentz, Manager - Nuclear Licensing & Regulatory Affairs, at (330) 315-6810.
s#i{f!J4£( , I Mark B. Bezilla (/
Davis-Besse Nuclear Power Station, Unit No. 1 L-18-123 Page 2 of 2 cc: NRC Region Ill Administrator NRC Resident Inspector NRC Project Manager Utility Radiological Safety Board
FENOC 5501 North State Route 2 Oak Harbor, Ohio 43449 Mark B. Bezilla 419-321-7676 Vice President - Nuclear Fax: 419-321-7582 April 27, 2018 L-18-123 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001
SUBJECT:
Davis-Besse Nuclear Power Station, Unit No. 1 Docket No. 50-346, License No. NPF-3 Steam Generator Tube Circumferential Crack Report - Spring 2018 Refueling Outage In accordance with Davis-Besse Nuclear Power Station (DBNPS) License Condition 2.C(7), "Steam Generator Tube Circumferential Crack Report," FirstEnergy Nuclear Operating Company (FENOC) is required to submit an evaluation within 3 months following the completion of steam generator tube inservice inspection. The DBNPS SGs were replaced in 2014 with new Babcock and Wilcox Replacement Once Through Steam Generators (OTSG), and as a result, DBNPS is no longer licensed to perform repair reroll. Structural and accident induced leakage integrity are evaluated analytically based on the degradation mechanism's characteristics, including circumferential extent, axial length, and percent through-wall depth. All indications of tube degradation were evaluated against the large-break loss-of-coolant accident (LBLOCA) loading for leakage integrity. All reported indications met condition monitoring criteria, and there were no indications of circumferential cracking identified, demonstrating reasonable assurance that the performance criteria for LBLOCA loading will continue to be satisfied throughout the next operating cycle. Therefore, it is bounded by current analyses, does not result in a significant increase of radionuclide release in excess of 10 CFR 100 limits, and demonstrates that adequate margin and defense-in-depth continue to be maintained. This letter satisfies License Condition 2.C(7) for evaluating that the primary-to-secondary leakage following a LBLOCA continues to be acceptable.
There are no regulatory commitments contained in this letter. If there are any questions of if additional information is required, please contact Mr. Thomas A. Lentz, Manager - Nuclear Licensing & Regulatory Affairs, at (330) 315-6810.
s#i{f!J4£( , I Mark B. Bezilla (/
Davis-Besse Nuclear Power Station, Unit No. 1 L-18-123 Page 2 of 2 cc: NRC Region Ill Administrator NRC Resident Inspector NRC Project Manager Utility Radiological Safety Board
