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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NORTHEU4.Tr INILITIES 3
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En"foEo7 CONNECTICUT 06101
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L J =::' OT;,'=.'Jrl October 26, 1979 Docket No. 50-336 Director of Nuclear Reactor Regulation Attn:
Mr. R. Reid, Chief Operating Reactors Branch #4
. S. Nuclear degulatory Commission Washington, D. C.
20555
References:
(1)
R. Reid letter to W. G. Counsil dated August 25, 1979.
(2)
W. G. Counsil letter to R. Reid dated October 22, 1979.
(3)
W. G. Counsil letter to R. Reid dated October 24, 1979.
Centlemen:
Millstone Nuclear Power Station, Unit No. 2 Feedwater System Piping In Reference (1), the NRC Staff documented its requirement to:
"By October 31, 1979, commence an approach to cold shutdown to perform ultrasonic examination of the four affected welds using the same methods, techniques, and conditions as were used to previously characterize the indications."
Recent developments regarding system generating capacity in the New England area render it highly desirable to operate Millstone Unit No. 2 for an additional three days beyond October 31 to facilitate alleviation of the potential generating capacity shortage.
Numerous generating stations in the New England system are unavailable for service as a result of scheduled outages, outages longer in duration than originally anticipated, or component failures. The major base load units out of service and their associated approximate capacity include:
1280
.311
@ F2 i rou oio
UNIT CAPACITY, MW Bridgeport 3 400 Middletown 3 240 Norwalk 1 165 Brayton Point 3 650 Canal 2 585 New Boston 2 380 Salem Harbor 4 460 Yarmouth 4 620 Vermont Yankee 525 Maine Yankee 830 Yankee Rowe 175 Total 5,030 In addition, several other unita in the New England area cannot achieve full pover operation at this time for various reasons.
Smaller (< 100 MW) units currently out of service are not included in the above listing.
Currently, New England Power Exchange (NEPEX) is purchasing power from both the New Brunswick and New York areas.
The transmission system has also been reconfigured to locally improve short-term reliability at the expense of system wide long-term reliability. Despite the above measures, the available reserve capacity is well below the optimum amount.
The situation is further compounded by the unseasonably cold weather in the Northeast region at this time, resulting in higher than normal power demands for this time of year.
The above considerations summarize Northeast Nuclear Energy Company's (NNECO) basis for requesting authorization to defer the shutdown of Millstone Unit No. 2 until November 3,1979. The additional time results in the following advantages:
(1) Additional time to complete outages on units currently unavailable.
The low demand on weekends effectively alleviates the shortage until November 5, 1979.
(2) Additional time to prepare for maximum utilization of the Housatsnic River System for hydroelectric power.
It is currently anticipated that this system will be utilized in a mode which has not occurred since approximately 1950. The resulting drain of the affected lakes /
reservoirs could substantially impact the residents of the immediate area. Northeast Utilities plans to issue public announcements, such as full-page ads in local newspapers, to advise the communities and allow them sufficient time to prepare.
(3) Reduction of the potential for utilizing gas turbines and peaking units thereby eliminating generating reserve capacity.
(4) Substantial favorable economic impact to the NU system and its customers.
NNECO has reviewed the above request with respect to safety implications, and has determined that the proposed three-day deferral is thoroughly justified. The basis for this determination is summarized in References (2) and (3).
1280 11?
_3_
It is our current understanding that Ref erence (1) would require amending on or before October 31, 1979 to authorize our request. Your timely and favorable action would be greatly appreciated.
Very truly yours, NORTHEAST NUCLEAR ENEROY COMPANY
/$tst W.' G. Counsil 8
Vice President 1280
~:12
