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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Text
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DOCKFT No. 50-336 ATTACIMENT 1 MILLSTONE NUCLEAR POWER STATION, UNIT No. 2 LOW TDiPERATURE TESTING QUANTIFICATION OF SECONDARY PLANT LOSSES 1742 032 NOVDiBER,1979 8 00111 o f(:, /
QUANTIFICATION OF SECONDARY PLANT LOSSES During operation of Cycle 3 of Millstone Nuclear Power Station, Unit Ib. 2, tests at reduced reactor coolant inlet temperatures will be performed to quantify secondary plant losses.
Northeast Nuclear Energy Company (NNECO) has determined that this test cons:itutes an unreviewed safety question and proposes to amend Facility Operating License No. DPR-65 by administratively restricting certain plant parameters to assure that transients or accidents initiated during the test will be less limiting than the current scfety analyses.
Accordingly, NNEC0 hereby proposes to amend Facility Operating License No. DPR-65 by adding a new paragraph 2.C(6) to read as follows:
(6) Northeast Nuclear Energy Company is authorized to perform a test during operation of Cycle 3 at reduced reactor coolant inlet temperature.
The duration of the test shall not exceed twenty four (24) hours. During the conduct of the test, the following operating conditions will be administratively maintained :
a) minimum reactor inlet temperature shall be maintained
> 537"F.
b) maximum linear heat rate shall be maintained
$ 14.2 Kw/ft.
c) the pressurizer level shall be maintained at normal operating levels with the reduced average coolant temperature.
I742 033
