Letter Sequence Other |
|---|
|
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, ML101230640
|
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
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
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: Approval
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: Approval
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
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
2009-05-27
[Table View] |
Text
FENOC 5501 North State Route 2 FirstEnergy Nuclear 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,
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
