ML20028E319

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Interim Deficiency Rept 82-09 Re Mechanical Snubber Bracket Interference.Initially Reported on 821203.Design Drawings & Vendor Production Info Under Review to Identify Suspect Snubber Assemblies.Next Rept Expected by 830215
ML20028E319
Person / Time
Site: Byron, Braidwood, 05000000
Issue date: 01/10/1983
From: Tramm T
COMMONWEALTH EDISON CO.
To: Kepler J, James Keppler
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
References
10CFR-050.55E, 10CFR-50.55E, 5740N, 82-09, 82-9, NUDOCS 8301210218
Download: ML20028E319 (2)


Text

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['D Commonwealth Edison

) One First N1tional Plaza. Chicago, lihnois O

T ") Address Reply to: Post Office Box 767

\\G Ohicago, Illinois 60690 January 10, 1983 Mr. James G. Keppler, Regional Administrator Directorate of Inspection and Enforcement - Region III U.S. Nuclear Regulatory Commission 799 Roosevelt Road Glen Ellyn, IL 60137

Subject:

Byron Station Units 1 and 2 Braidwood Station Units 1 and 2 Mechanical Snubber Bracket Interference NRC Docket Nos. 50-454, 50-455, 50-456, and 50-457

Dear Mr. Keppler:

On December 3, 1982 Commonwealth Edison notified Mr. Mark Holzmer of your office of a deficiency reportable pursuant to 10 CFR 50.55(e) regarding potential bracket interference in mechanical snubber assemblies provided by ITT Grinnell.

This interim report fulfills the 30-day reporting requirement.

Another interim report will be issued by February 15, 1983.

For your tracking purposes this deficiency is numbered 82-09 for Byron Station and 82-09 for Braidwood Station.

Description of Deficiency ITT Grianell has informed us that certain Figure 306/307 mechanical snubber assemblies may contain parts which interfere with pipe movement in certain applications.

Assemblies produced prior to April 1980 may have the deficiencies.

Size 3 assemblies may have pipe clamp interference problems and size 35 assemblies may have end brackets which could interfere with the snubber.

Analysis of Safety Implications Improper snubber operation could induce unexpected piping loads.

A case-by-case analysis would be required to determine if these additional loads would be detrimental to reactor safety.

Corrective Action Taken Design drawings and ITT Grinnell production information Js being reviewed to identify suspect snubber assemblies.

The assemblies vill be inspected before a repair program and schedule is established.

3 final report will be issued to docuraent the results of these inspections, the repairs required to restore design margins, and the schedule for completion of the repairs.

8301210218 830110 PDR ADOCK 05000454 S

PDR yQ

-JAN 1 4 SE

J. G. Keppler January 10, 1983 Please direct further questions regarding this matter to this office.

Very truly yours, 7/ [L / [M5*" ~

T. R. Tramm Nuclear Licensing Administrator 1

1m cc:

Director of Inspection and Enforcement 5740N

.