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
ML19208B8831979-08-17017 August 1979
Notification of 790821 Meeting W/Northeast Nuclear Energy Co in Bethesda,Md to Discuss Observed Feedwater Line Crack Indicators
Project stage: Meeting
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
ML19276H0361979-08-24024 August 1979
Provides Info to Fulfill Commitment in Util Re Feedwater Piping Sys.Discusses Instrumentation Package for Monitoring Equipment to Be Installed on Steam Generator 2
Project stage: Other
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
ML19211C5201979-11-30030 November 1979
Low Temp Testing,Sar
Project stage: Other
ML19211C5171979-11-30030 November 1979
Low Temp Testing,Quantification of Secondary Plant Losses
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
1979-12-07
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,o, UNITED STATES 8j,$o j
NUCLEAR REGULATORY COMMISSION
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f August 25, 1979 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 Ccenission is issuing the enciosed Safety Evaluation to document our analysis of the acceptability of interim opera.'on of the Millstone Unit No. 2 with the feedwater line crack indicatio.is as described in your presentation to the NRC Staff on August 21, 1979 and in subsequent documentation dated August 22, 1979 and August 24,1979 (two submittal s).
Based on ur review, we conclude that the facility may be operated at the 1icen:ed power 1eyel until Octcber 31, 1979.
This conci asion is based on your commitments to:
1.
Install monitoring equipment for temperature and stress measurements on the steam generater no. 2 feedwater line.
2.
Establish action points from en-site and off-site acceptance criteria as presented in the August 24, 1979 letter for initiating controlled plant shu'.down if the limits are exceeded.
3.
Initiate a controlled shutdcwn ra perfom an ultrasonic examination of tha most severe indications on the affected lines in the event of a TcM.. ' =r ficw instability (water-hammer);
4 By October 1,1979, submit a thorough program for repairing the affected welds. The program will address the modifications required in the steam generator shield wall section.
5.
By October 31, 1979, commence an approach to cold shutdown to perfom ultrasonic examination of the four affected welds using the same methods, techniques and conditions as was used to previously characteri:e the indications.
6.
Prior to startup, install local leak monitoring equipment capable of detecting 3 0.5 gal / minute leak on both steam generator laces in the vicinity of the cracks.
1029 056
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Mr. W. G. Counsil August 25, 1979 7.
Initiate a controlled shutdown and inspect the affected welds should combined dynamic stress greater than 40 ksi be measured by the on-site monitoring equipnent.
Sincerely, A VI.
Robert W. Reid, Chief Operating Reactors Branch #4 Division of Operating Reactors
Enclosure:
Safety Evaluation cc: w/ enclosure See next page 1029 057
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Nortneast Nuclear Energy Company cc w/ enclosure (s):
William H. Cuddy, Esquire U. S. Nuclear Regulatory Commission Day, Berry & Howard Region I Counselors at Law Office of Inspeccion and Enforcement One Constitution Plaza ATTN: Mr. John T. Shediosky Hartford, Connecticut 06103 631 Park Avenue King of Prussia, Pennsylvania 19406 Anthony Z. Roisman Natural Resources Defense Council 917 15 th Street, N.W.
Jashington, D.C.
20005 Connecticut Energy Agency Mr. Lawrence Bettencourt. First Selectman ATIN: Assistant Director, Research Town of Waterford and Policy Development Hall of Recorcs - 200 Boston Post Road Depart ent 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 Sox 128 Waterford, Connecticut 06385 Director, Technical Assessment Division Off. ice of Radiation Programs (AW-459)
U. S. Environmental Protection Agency Crystal Mall 42 Arlington, Virginia 20460 U. S. Envi. onmental Protection Agency Decinn ! ^f fice ATT'!:
EIS CO.'RDINATOR John F. Kennecy Federal Building Boston,!'assacnuset;s 02203 Waterfora Puolic Liorary Rope Ferry Road, Route 156
!!aterford, Connecticut 06335 Northeast Utilities Service Comcany ATTN: Mr. James R. Himmelwrignt Nuclear Engineering and Operations
?. O. Box 270 Hartford, Connecticut C6101 1 02.9 Ofi8
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