Letter Sequence Approval |
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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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UNITED STATES s
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NUCLEAR REGULATORY COMMISSION t,
- l WASMNGTON, D. C. 20655
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March 13, 1980 Docket No. 50-336 Mr. W. G. Counsil, Vice President Nuclear Engineering & Operations Northeast Nuclear Energy Company P. O. Box 270 Hartford, Connecticut 06101
Dear Mr. Counsil:
The Comission is issuing the enclosed Safety Evaluation to document our review of your feedwater piping system inspections and repair performed in response to our I&E Bulletin 79-13 at Millstone Nuclear Power Station.
Unit No. 2.
Our I&E inspectors have verified that your staff performed the inspections required by the bulletin and repaired the indication of cracking in the feedwater piping in an acceptable manner.
We find that the repair method, the subsequent nondestructive and visual inspections performed by your staff and consultants and the inherent toughness of the piping materials are adequate to ensure that the feedwater piping integrity will be maintained.
Sincerely, Robert W. Reid, Chief Operating Reactors Branch #4 Division of Operating Reactors
Enclosure:
i Safety Evaluation cc w/ enclosure:
See next page l
l t
9 8004070
4 Northeast Nuclear Energy Company cc w/ enclosure (s):
William H. Cuddy, Esquire Day, Berry & Howard Counselors at Law Mr. John T. Shedlosky One Constitution Plaza U. S. Nuclear Regulatory Commission P. O. Drawer KK Hartford, Connecticut 06103 Niantic, CT D6357 Anthony Z. Roisman Natural Resources Defense Council 917 15th Street N.W.
Washington. D.C.
20005 Connecticut Energy Agency Mr. Lawrence Bettencourt. First Selectman ATTN: Assistant Director, Research Town of Waterford and Policy Development Hall of Records - 200 Boston Post Road Department of Planning and Energy Waterford, Connecticut 06385 Policy 20 Grand Street Northeast Nuclear Energy Company Hartford, Connecticut 06106 ATTN:
Superintendent Millstone Plant Post Of fice Box 128 Waterford, Connecticut 06385 Director, Technical Assessment Division i
Office of Radiation Programs (AW-459)
U. S. Environmental Protection Agency Crystal Mall #2 Arlington, Virginia 20460 U. S. Environmental Protection Agency Region I Of fice ATTN:
EIS C00RDINATOR John F. Kennedy Federal Building Boston, flassachusetts 02203 Waterford Public Library Rope Ferry Road, Route 156 Waterford, Connecticut 06385 Northeast Utilities Service Company ATTN: Mr. James R. Himmelwright Nuclear Engineering and Operations P. O. Box 270 l
Hartford, Connecticut,,,06101 i
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