Letter Sequence Other |
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Results
Other: ML19210D050, ML19211C517, ML19211C520, ML19250B711, ML19253C109, ML19254E457, ML19256F557, ML19256F561, ML19261E812, ML19261E814, ML19268B826
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MONTHYEARML19268B8261979-06-18018 June 1979
Forwards Info in Response to V Stello 790525 Request Re Design Fabrication History & Insp of Feedwater Lines.Sys Meets Code Requirements & Can Continue to Operate Safely
Project stage: Other
ML19275A0521979-08-22022 August 1979
Responds to Bh Grier 790625 Request for Info Re Postulated Increased Likelihood of Feedwater Line Break.Forwards Tables Re Feedwater Sys Piping & Thermal Fatigue Analysis
Project stage: Request
ML19249E1411979-08-25025 August 1979
Safety Evaluation Re Analysis of Interim Operation W/Feedwater Line Crack Indications.Continued Operation Acceptable
Project stage: Approval
ML19249E1391979-08-25025 August 1979
Forwards Safety Evaluation Re Acceptability of Interim Operation W/Feedwater Line Crack Indication.Lists Commitments for Improvements
Project stage: Approval
ML19261E8141979-09-28028 September 1979
Proposed Repair/Replacement Program for Steam Generator Feedwater Nozzle Safe-End-To-Pipe & Pipe-To-Elbow Welds. Oversize Drawings Encl
Project stage: Other
ML19261E8121979-09-28028 September 1979
Forwards Proposed Repair/Replacement Program for Steam Generator Feedwater Nozzle Safe-End-To-Pipe & Pipe-To-Elbow Welds, in Response to
Project stage: Other
ML19254D3351979-10-22022 October 1979
Forwards Addl Info on Applicability of ASME Section XI Re Existing Feedwater Piping Sys Linear Indications,In Response to Request at 791019 Meeting
Project stage: Meeting
ML19254E4571979-10-24024 October 1979
Forwards Response to NRC Questions Re Fatigue Crack Growth & Repair Options Applicable to Feedwater Sys Piping Cracks. Discusses Program to Assess Feedwater Pipe Cracking Phenomena
Project stage: Other
ML19256E4421979-10-25025 October 1979
Summary of 791019 Meeting W/Util in Bethesda,Md Re Feedwater Line Indicators
Project stage: Meeting
ML19250B7111979-10-26026 October 1979
Requests Authorization to Defer Shutdown of Facility Until 791103 to Alleviate Potential Generating Capacity Shortage. Numerous Stations Unavailable for Svc Due to Scheduled Outages & Component Failures
Project stage: Other
ML19253C1091979-11-0505 November 1979
Submits Addl Info Establishing That Util Fulfilled Acceptance Criteria to Allow Continued Operation W/Feedwater Piping Crack Indications.No Crack Growth in through- Thickness Direction Occurred
Project stage: Other
ML19210D0501979-11-13013 November 1979
Requests That Basis for NRC Decision to Require Repair of Feedwater Piping Sys Be Documented.Util Has Confirmed No Further Crack Growth Evidence
Project stage: Other
ML19211C5171979-11-30030 November 1979
Low Temp Testing,Quantification of Secondary Plant Losses
Project stage: Other
ML19211C5201979-11-30030 November 1979
Low Temp Testing,Sar
Project stage: Other
ML19256F5571979-12-0707 December 1979
Forwards Summary Rept of Feedwater Piping Repair Program & Associated Observations & Findings, Re NRC 790928 Request
Project stage: Other
ML19211C5141979-12-27027 December 1979
Application to Amend License DPR-65 to Authorize Performance of Tests at Reduced RCS Inlet Temps.Forwards Low Temp Testing,Quantification of Secondary Plant Losses & Low Temp Testing,Sar. Fee Encl
Project stage: Request
ML19256F5611979-12-31031 December 1979
Summary Rept of Feedwater Piping Repair Program & Associated Observations & Findings
Project stage: Other
ML19309B8471980-03-13013 March 1980
Safety Evaluation Re Interim Actions Taken to Eliminate Feedwater Piping Cracks,Performed in Response to IE Bulletin 79-13.Repair Method,Nondestructive & Visual Insp & Inherent Toughness of Piping Matls Are Adequate
Project stage: Approval
ML19309B8441980-03-13013 March 1980
Forwards Safety Evaluation Re Interim Actions Taken to Eliminate Feedwater Piping Cracks,Performed in Response to IE Bulletin 79-13
Project stage: Approval
ML19309F5721980-04-0404 April 1980
Forwards Comments Re Technical Considerations Leading to Recommendations Given to Util at 791106 Meeting About Steam Generator Feedwater Line Repair.Util Presentation Did Not Provide Conclusive Evidence That Crack Had Not Grown
Project stage: Meeting
B10092, Application to Amend License DPR-65 Authorizing Performance of Tests at Reduced RCS Inlet Temps in Order to Quantify Secondary Plant Performance Losses1980-09-30030 September 1980
Application to Amend License DPR-65 Authorizing Performance of Tests at Reduced RCS Inlet Temps in Order to Quantify Secondary Plant Performance Losses
Project stage: Request
1979-12-31
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December 7, 1979 Docket No. 50-336 Director of Nuclear Reactor Regulation Attn:
Mr. R. Reid, Chief Operating Reactors Branch #4 U. S. Nuclear Regulatory Commission Washington, D. C.
20555
References:
(1)
W. G. Counsil letter to H. R. Denton, dated November 13, 1979.
(2)
W. G. Counsil letter to R. Reid, dated September 28, 1979.
Gentlemen:
Millstone Nuclear Power Station, Unit No. 2 Feedwater System Piping In Reference (1), ticrtheast Nuclear Energy Company (NNECO) documented its commit-ment to perform a repair of the affected welds of the feedwater system piping in accordance with the program docketed in Reference (2).
Subsequently, the Staf f requested that a summary report of the repair program be provided, and further requested that data regarding crack depth be included.
In response to those requests, Attachment 1, A Summary Report of the Feedwater Piping Repair Program and Associated Observations and Findings, is provided.
As stated in the Attachment, the repair program was directed at removal of the indications, and not at quantifying crack depth.
Therefore, the data supplied refers to depth of metal removed and not to crack depth.
The Staff is requested to be cognizant of this fact when evaluating the attached information.
The NRC Staff had also verbally requested that NNECO commit to a re-exaiaimia ci the repaired feedwater piping welds (AC-G-1, 2 and BC-C-1, 2) during the 1980 refueling outage.
In confirmation of NNECO's previous verbal commitment, please be advised that NNECO will perform such an examination during the next refueling outage.
In accordance with the requirements of I&E Bulletin No. 79-13, such (621 082 7912190 g
. an examination would be limited to radiographic inspections if no indications are detected using that technique.
We trust you find the above information responsive to your verbal requests.
Very truly yours, NORTHEAST NUCLEAR ENERGY COMPANY
/
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, l, blM W. G. Counsil Vice President Attachment 1621 083
