ML20093A435

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Final Deficiency Repts 83-13 & 83-15 Re Pacific Scientific Snubber Capstan Springs.Initially Reported on 831028. Independent Metallurgical Evaluation & Vendor Testing Concluded Snubbers Meet Design Spec Requirements
ML20093A435
Person / Time
Site: Byron, Braidwood, 05000000
Issue date: 07/02/1984
From: Swartz E
COMMONWEALTH EDISON CO.
To: James Keppler
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
References
83-13, 83-15, 8925N, NUDOCS 8407100495
Download: ML20093A435 (1)


Text

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'x Commonwe:lth Edison l

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) one First National Plaza Chicago. l!hnois

't 7 Address Reply to. Post Othce Box 767 N

Cnicaco. Illinois 60690 July 2, 1984 Mr. I mes G. Keppler Regicaal Administrator U.S. Nuclear Regulatory Commission Region III 799 Roosevelt Road Glen Ellyn, IL 60137

Subject:

Byron Station Units 1 and 2 Braidwood Station Units 1 and 2 10 CFR 50.55(e) Final Report Pacific Scientific Snubber Capstan Springs NRC Docket Nos. 50-454/455 and 50-456/457 Reference (a):

T. R. Tramm letter to J. G. Keppler dated December 2, 1983

Dear Mr. Keppler:

On October 28, 1983, Commonwealth Edison notified Mr.

R. C.

Knop of your staff of a potential quality problem associated with the capstan springs of the Pacific Scientific Mechanical Shock Arrestors (Model PSA-1 and PSA-3) being installed at our Byron and Braidwood Stations.

Reference (a) provided the thirty day final report concerning this matter.

For your tracking purposes, this deficiency was assigned Number 83-13 for Byron Station and Number 83-15 for Braidwood Station.

In Reference (a), we indicated that the potentially defective snubbers would be replaced, or inspected and repaired as necessary to support our fuel load schedules.

Since that time, the Pacific Scientific Company has provided supplementary information regarding the potentially defective units.

Based on an independent metallurgical evaluation and subsequent Pacific Scientific testing and evaluation of the capstan springs which contained micro cracks, it was concluded that the snubbers in question do in fact meet design specification requirements.

Therefore, the Commonwealth Edison Company considers this matter closed.

Please address any further questions concerning this matter to this office.

Very truly yours, E. Douglas Swa Nuclear Licensing Administrator EDS/ rap cc:

RIII Inspector - By/Bw Director of Inspectior and Enforcement US Nuclear Regulatory Commission Washington, DC 20555 dUL 5 IM4 8925N 8407100495 840702 JC4Eg7 lQ PDR ADOCK 05000454 lj PDR 6