ML20206K659

Responds to NRC 720223 & 0412 Ltrs Re QA Audit of GE Fuel Fabrication Facility in Wilmington,Nc on 711129-30.Review of Offgassing & Final End Plug Welding Records Completed to Ensure Quality of Fuel Rods

ML20206K659
Person / Time
Site:	Pilgrim, 05000000
Issue date:	05/02/1972
From:	Staszesky F BOSTON EDISON CO.
To:	James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
Shared Package
ML20204E974	List: 05000000/LER-1975-004, :on 750112 & 13,analysis of Reactor Bldg Vent Process Radiation Monitoring Sys Revealed Release of Radioactive Effluents Exceeding Tech Spec Limit by 55%. Caused by High Iodine Activity in Reactor Coolant 05000000/LER-1975-005, :on 750127,analysis of Reactor Bldg Vent & Main Stack Charcoal & Particulate Filters Revealed Release Rates of Halogens & Particulates w/half-lives Greater than 8 Days, Exceeding Tech Spec Limits by 24% 05000000/LER-1975-014, :on 750519,analysis of Reactor Bldg Vent & Main Stack Charcoal & Particulate Filters for Wk of 750513-20 Revealed Release Rates of Halogens & Particulates Exceeding Tech Spec Limits by 23% BECO-82-194, Responds to Confirmatory Action Ltr 82-19 Re Identification of Spent Resin on Roof Tops & Pavement within Protected Area on 820611.Condensate Demineralizer Sys Identified as Resin Source & Secured.Related Documentation Encl IR 05000293/1975002 ML20204E969 ML20204J237 ML20206F330 ML20206K250 ML20206K259 ML20206K286 ML20206K305 ML20206K341 ML20206K353 ML20206K363 ML20206K365 ML20206K385 ML20206K423 ML20206K439 ML20206K444 ML20206K449 ML20206K480 ML20206K485 ML20206K494 ML20206K504 ML20206K510 ML20206K520 ML20206K526 ML20206K530 ML20206K548 ML20206K555 ML20206K564 ML20206K579 ML20206K598 ML20206K616 ML20206K635 ML20206K639 ML20206K659 ML20206K688 ML20206K693 ML20206K698 ML20206K704 ML20206K709 ML20206K731 ML20206K743 ML20206K748 ML20206K754
References
FOIA-86-58 NUDOCS 8606300153
Download: ML20206K659 (1)

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GOSTON EDISON COMPANY DEcurnc arricts 000 DaytstaN StaEtY UoGTON, M ASSACHUGcTTS O2199 FRAN CIS M. STAGZESK1' 2, 1972 E nt CWT evC veCL #WL6@&NT Mr. J. P. O'Reilly Director, Region I AEC Division of Compliance 970 Broad Street Newark, New Jersey 07102

Dear Mr. O ' Reilly:

This letter is in reply to your letters of February 23, 1972 and April 12, 1972 concerning the quality assurance audit of the General Electric Company's fuel fabrication f acility in Wilmington, North Carolina on November 29 -

30, 1971.

In response to yout first question concerning the elapsed time between fuel rod offgassing and final end plug welding, the following action has been taken to assure the quality of the subject f ue l rod s._ The offgassing and final end plug welding records have been reviewed by Boston Edison to detemine i.f the elapsed time requirements have been met.

In all cases, the

requirements were met This review was completed as a part of the hoston Edison Quality Assurance Auditing program.

T In-Wswer to your second queMon concerning the technical basis for accepting p g p to 60% of the end plug weld su rf ace area with a bluish tint, the follow-ing in f o rma t ion is provided:

The bluing which occurs is cosmetic and does not in itself affect the properties of the material in the end plug weld zone.

Bluing is related to exposure of the material to oxygen at elevated temperature.

By the nature of the welding process where the pin i.s turned within the welding atmosphere, the first part of the weld has cooled below the bluing temperature before removal from the welding atmosphere, lloweve r, the last part of the weld may not have cooled below the bluing temperature. Considering the rates of cooling which occur, 50% bluing could be expected in an end plug weld. A criteria of 60% bluing of the weld surface area has been specified based on engineering judgment. Where greater than 60% bluing is found, the weld is subjected to further review to assure its quality and integrity.

Very truly yours, 8606300153 e60613 hgg 6-Se PDR

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1. ,i l_ Q', &'Wi t

cc: Messrs. C. A. Pursel, R. C. Ilaynes

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L.D. Weislogel

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