Letter Sequence Other |
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Results
Other: L-09-268, Calculation, 0800777.309, Rev. 0, Sensitivity Study of Temperbead Surface Area Limitations for Large Bore Weld Overlay Repairs Over Ferritic Materials (from 500 to 1,000 Square Inches)., L-10-132, 0800368.408, Revision 0, Summary of Weld Overlay Ultrasonic Examinations for Reactor Coolant Pump Suction and Discharge Nozzle Welds, Core Flood Nozzle Welds, and Cold Leg Drain Nozzle Welds, L-10-133, Summary of Design and Analysis of Weld Overlays (Mode 4 Report), ML093360324, ML093360325, ML093360326, ML093360327, ML093360328, ML093360329, ML093360330, ML093360331, ML100271531, ML101230640
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MONTHYEARL-09-020, 10 CFR 50.55a Requests for Alternative Dissimilar Metal Weld Repair Methods for Reactor Vessel Nozzles, Reactor Coolant Pump Nozzles, and Reactor Coolant Piping2009-01-30030 January 2009
10 CFR 50.55a Requests for Alternative Dissimilar Metal Weld Repair Methods for Reactor Vessel Nozzles, Reactor Coolant Pump Nozzles, and Reactor Coolant Piping
Project stage: Request
ML0933603252009-04-0808 April 2009
Calculation, 0800368.311, Rev. 0, Design Loads for the 28 I.D. Reactor Coolant Pump (RCP) Suction and Discharge Nozzles.
Project stage: Other
ML0933603242009-04-21021 April 2009
Calculation, 0800368.301, Rev 0, Material Properties for Davis-Besse Unit 1, RCP Suction, RCP Discharge, Cold Leg Drain and Core Flood Nozzles Preemptive Weld Overlay Repairs.
Project stage: Other
ML0933603272009-05-22022 May 2009
Calculation, 0800368.322, Rev. 1, Finite Element Models of the Reactor Coolant Pump Discharge Nozzle with Weld Overlay Repair.
Project stage: Other
ML0933603282009-05-23023 May 2009
Calculation, 0800368.323, Rev. 1, Thermal and Unit Mechanical Stress Analyses for Reactor Coolant Pump Discharge Nozzle with Weld Overlay Repair.
Project stage: Other
ML0933603262009-05-27027 May 2009
Calculation, 0800368.320, Rev. 1, Optimized Weld Overlay Sizing for the 28 I.D. Outlet/Discharge Reactor Coolant Pump Nozzle.
Project stage: Other
ML0915301512009-06-11011 June 2009
Request for Additional Information Related to Relief Requests for Alternative Dissimilar Metal Weld Repair Methods for Reactor Vessel Nozzles, Reactor Coolant Pump Nozzles, and Reactor Coolant Piping
Project stage: RAI
ML0915504232009-06-15015 June 2009
Request for Additional Information Related to Relief Requests for Alternative Dissimilar Metal Weld Repair Methods for Reactor Vessel Nozzles, Reactor Coolant Pump Nozzles, and Reactor Coolant Piping
Project stage: RAI
ML0933603292009-07-10010 July 2009
Calculation, 0800368.324, Rev. 0, Residual Stress Analysis of Reactor Coolant Pump Discharge Nozzle with Weld Overlay Repair.
Project stage: Other
L-09-179, Response to Requests for Additional Information Related to Alternative Dissimilar Metal Weld Repair Methods2009-07-13013 July 2009
Response to Requests for Additional Information Related to Alternative Dissimilar Metal Weld Repair Methods
Project stage: Response to RAI
ML0933603312009-07-20020 July 2009
Calculation, 0800368.326, Rev. 0, Crack Growth Evaluation of Reactor Coolant Pump Discharge Nozzle with Weld Overlay Repair.
Project stage: Other
L-09-227, License Amendment Request to Update the Leak-Before-Break Evaluation for the Reactor Coolant Pump Suction and Discharge Nozzle Dissimilar Metal Welds2009-09-28028 September 2009
License Amendment Request to Update the Leak-Before-Break Evaluation for the Reactor Coolant Pump Suction and Discharge Nozzle Dissimilar Metal Welds
Project stage: Request
ML0927205912009-10-0808 October 2009
RAI Related to Relief Requests for Alternative Dissimilar Metal Weld Repair Methods
Project stage: RAI
L-09-268, Calculation, 0800777.309, Rev. 0, Sensitivity Study of Temperbead Surface Area Limitations for Large Bore Weld Overlay Repairs Over Ferritic Materials (from 500 to 1,000 Square Inches).2009-11-0202 November 2009
Calculation, 0800777.309, Rev. 0, Sensitivity Study of Temperbead Surface Area Limitations for Large Bore Weld Overlay Repairs Over Ferritic Materials (from 500 to 1,000 Square Inches).
Project stage: Other
ML0933603302009-11-23023 November 2009
Calculation, 0800368.325, Rev. 0, ASME Code, Section Iii Evaluation of Reactor Coolant Pump Discharge Nozzle with Weld Overlay Repair.
Project stage: Other
ML0933603232009-11-23023 November 2009
Davis-Besse, Response to Requests for Additional Information Related to Alternative Dissimilar Metal Weld Repair Methods
Project stage: Response to RAI
ML1000400162009-12-15015 December 2009
Relief Request A-32 and A-33 - Request for Additional Information - Supplemental Information
Project stage: Supplement
ML1000805732010-01-21021 January 2010
Unit, Relief Request RR-A33 for the Application of Full Structural Weld Overlays on Dissimilar Metal Welds of Reactor Coolant Piping
Project stage: Acceptance Review
ML1002715312010-01-29029 January 2010
Relief Request RR-A32 for the Application of Full Structural Weld Overlays on Dissimilar Metal Welds of Reactor Coolant Piping
Project stage: Other
L-10-132, 0800368.408, Revision 0, Summary of Weld Overlay Ultrasonic Examinations for Reactor Coolant Pump Suction and Discharge Nozzle Welds, Core Flood Nozzle Welds, and Cold Leg Drain Nozzle Welds2010-04-25025 April 2010
0800368.408, Revision 0, Summary of Weld Overlay Ultrasonic Examinations for Reactor Coolant Pump Suction and Discharge Nozzle Welds, Core Flood Nozzle Welds, and Cold Leg Drain Nozzle Welds
Project stage: Other
ML1012306402010-04-29029 April 2010
Davis-Besse, Summary of Weld Overlay Ultrasonic Examinations
Project stage: Other
L-10-133, Summary of Design and Analysis of Weld Overlays (Mode 4 Report)2010-06-18018 June 2010
Summary of Design and Analysis of Weld Overlays (Mode 4 Report)
Project stage: Other
2009-06-11
[Table View] |
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Category:Letter type:L
MONTHYEARL-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-23-131, Readiness for Resumption of NRC Supplemental Inspection2023-05-12012 May 2023
Readiness for Resumption of NRC Supplemental Inspection
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-23-092, 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-22-153, Readiness for NRC Supplemental Inspection Required for a White Finding2022-06-22022 June 2022
Readiness for NRC Supplemental Inspection Required for a White Finding
L-22-098, Withdrawal of Proposed Inservice Inspection Alternative RR-A22022-06-22022 June 2022
Withdrawal of Proposed Inservice Inspection Alternative RR-A2
L-22-136, Steam Generator Tube Circumferential Crack Report - Spring 2022 Refueling Outage2022-06-0707 June 2022
Steam Generator Tube Circumferential Crack Report - Spring 2022 Refueling Outage
L-22-102, Report of Facility Changes, Tests, and Experiments2022-05-16016 May 2022
Report of Facility Changes, Tests, and Experiments
L-22-092, Combined Annual Radiological Environmental Operating Report and Radiological Effluent Release Report for the Davis-Besse Nuclear Power Station - 20212022-05-16016 May 2022
Combined Annual Radiological Environmental Operating Report and Radiological Effluent Release Report for the Davis-Besse Nuclear Power Station - 2021
L-22-124, Response to Request for Additional Information Regarding License Amendment Request to Revise the Design Basis for the Shield Building2022-05-12012 May 2022
Response to Request for Additional Information Regarding License Amendment Request to Revise the Design Basis for the Shield Building
L-22-047, Unit No.1 - Core Operating Limits Report, Cycle 23, Revision O and Revision 12022-05-10010 May 2022
Unit No.1 - Core Operating Limits Report, Cycle 23, Revision O and Revision 1
L-22-127, Readiness for NRC Supplemental Inspection Required for a Greater than Green Finding2022-05-0606 May 2022
Readiness for NRC Supplemental Inspection Required for a Greater than Green Finding
L-22-089, Occupational Radiation Exposure Report for Year 20212022-04-12012 April 2022
Occupational Radiation Exposure Report for Year 2021
L-22-056, Energy Harbor Nuclear Corp., Annual Notification of Property Insurance Coverage2022-03-22022 March 2022
Energy Harbor Nuclear Corp., Annual Notification of Property Insurance Coverage
L-22-059, Response to Request for Additional Information on Proposed Inservice Test Alternative RP-32022-03-21021 March 2022
Response to Request for Additional Information on Proposed Inservice Test Alternative RP-3
L-22-074, Response to Regulatory Issue Summary 2022-01, Preparation and Scheduling of Operator Licensing Examinations2022-03-15015 March 2022
Response to Regulatory Issue Summary 2022-01, Preparation and Scheduling of Operator Licensing Examinations
L-22-061, Ile Post Exam Letter L-22-0612022-02-24024 February 2022
Ile Post Exam Letter L-22-061
L-22-023, Retrospective Premium Guarantee2022-02-17017 February 2022
Retrospective Premium Guarantee
L-21-266, Response to Request for Additional Information on Proposed Inservice Inspection Alternative RR-A22022-01-27027 January 2022
Response to Request for Additional Information on Proposed Inservice Inspection Alternative RR-A2
L-20-289, Emergency Plan Amendment Request2022-01-19019 January 2022
Emergency Plan Amendment Request
L-21-290, Response to NRC Inspection Report 05000346/2021091, EA-21-1762021-12-21021 December 2021
Response to NRC Inspection Report 05000346/2021091, EA-21-176
2023-09-12
[Table view] |
Text
FENOC 5501 North State Route 2 FirstEnergyNuclear Operating Company Oak Harbor,Ohio 43449 Barry S. Allen 419-321-7676 Vice President - Nuclear Fax: 419-321-7582 June 18, 2010 L-1 0-133 10 CFR 50.55a ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001
SUBJECT:
Davis-Besse Nuclear Power Station Docket No. 50-346, License No. NPF-3 Summary of Design and Analysis of Weld Overlays (Mode 4 Report) - Davis-Besse Nuclear Power Station (TAC Nos. ME0477 and ME0478)
By correspondence dated January 30, 2009 (Accession No. ML090350070); with supplements dated July 13, 2009 (Accession No. ML091950627); November 23, 2009 (Accession No. ML093360333); and electronic mail dated December 15, 2009 (Accession No. ML100040016); FirstEnergy Nuclear Operating Company (FENOC) requested alternatives to requirements associated with reactor vessel nozzle, reactor coolant pump nozzle, and reactor coolant piping weld repairs for the Davis-Besse Nuclear Power Station.
By correspondence dated January 21, 2010 (Accession No. ML100080573), Nuclear Regulatory Commission (NRC) staff approved 10 CFR 50.55a Request RR-A33 for the full structural weld overlay alternative. By correspondence dated January 29, 2010 (Accession No. ML100271531), NRC staff approved 10 CFR 50.55a Request RR-A32 for the optimized weld overlay alternative.
The January 30, 2009 correspondence contained commitments to submit, prior to entry into Mode 4, summaries 'of:
- the residual stress profile in the nozzles,
- that the application of the weld overlays does not impact the conclusions of the existing nozzle stress reports.
The Enclosure contains the aforementioned summaries.
Davis-Besse Nuclear Power Station Letter L-1 0-133 Page 2 of 2 There are no new regulatory commitments contained in this submittal. If there are any questions or additional information is required, please contact Mr. Thomas A. Lentz, Manager- Fleet Licensing, at (330) 761-6071.
Sincerely, Barry S. Allen
Enclosure:
Structural Integrity Associates, Inc., "Summary of Design and Analyses of Weld Overlays for Reactor Coolant Pump Suction and Discharge, Cold Leg Drain, and Core Flood Nozzle Dissimilar Metal Welds for Alloy 600 Primary Water Stress Corrosion Cracking Mitigation," Report No. 0800368.407, Revision 0, June 2010.
cc: NRC Region III Administrator NRC Resident Inspector NRC Project Manager Utility Radiological Safety Board
