ML20210L044

Final Deficiency Repts 86-02 for Byron & 86-04 for Braidwood Re Failures of Diesel engine-generator Rocker Arm.Initially Reported on 860327 by Util & 860311 by Cooper Industries Under Part 21

ML20210L044
Person / Time
Site:	Byron, Braidwood, 05000000
Issue date:	04/22/1986
From:	Miosi A COMMONWEALTH EDISON CO.
To:	James Keppler NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
References
REF-PT21-86, REF-PT21-86-155-000 1612K, 86-02, 86-04, 86-2, 86-4, PT21-86-155, PT21-86-155-000, NUDOCS 8604290158
Download: ML20210L044 (2)

Text

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ConunonweeNh Edison

• C's ' ~[C') One First Natioruf Plaza. Chicagoc ill. ors

\ v Addrzss Reply to: Post Othee Box 767, Chicago, liknois 60690 .

. l April 22, 1986 Mr.' James G.-Keppler

. Regional Administrator '

U.S. Nuclear Regulatory Commission Region III 799 Roosevelt Road 'I Glen Ellyn, IL. 60137  :

l

Subject:

.Braidwood Station Units-1 and 2 Byron S*ation Unit 2 10CFR 50.55(e) No. 86-02 Byron and 86-04 Braidwood 30 Day Report Diesel Engine-Generator Rocker Arm Failures NRC Docket Nos. 50-455 and 50-456/457

Reference:

(a): March 11, 1986 R.E. Querio Letter to J.G. Keppler (b): March 11, 1986 F.B.-Stolba Letter to H.R. Denton l

Dear Mr. Keppler:

On March 27, 1986 CECO (D. Elias) notified Mr. N.L. Forney of a deficiency reportable pursuant to 10CFR 50.55(e) regarding the subject failures.- 'these f ailures had previously been reported to the NRC Director of Inspection and Enforcement by Cooper Industries (the engine manufacturer) on March 11, 1986 under 10CFR21 requirements. This letter fulfills the thirty day reporting requirements of 10CFR 50.55(e) regarding the matter, and is considered a final report.

Cooper's March 11, 1986 letter included the following three attachments.

1. Service News Bulletin No. 678 dated October 18, 1984

- KSV Engines, Cylinder Liner Installation.

2. Service News Bulletin No. 698 dated March 10, 1986 -

KSV Engines, Power Head Assembly.

3. Report - Ref. QCP-2292, March 3, 1986 - Rocket Arm  ;

Failures.

8604290158 860422 " a n n n '7 anoc PDR ADOCK 05000455- AFR 4 0 100U S PDR. ,

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These three documents, and in particular the trip report QCF-2292, provide the Description of Deficiency, the root Cause of Failure and Corrective Action Taken to prevent recurrence. This information has l been distributed to both Byron and Braidwood stations and appropriate actions are being performed on all engines.

Analysis of Safety Implications This type of failure would not have prevented the diesel engine-generator sets from providing emergency A.C. power. Rocker arm breakage will not cause additional mechanical damage. The only effect on the engine will be loss of power from the affected cylinder. There is sufficient margin in these engines such that the loss of one cylinder will not prevent the engine from producing full power.

Please address any questions that you or your staff may have concerning this matter to this office.

Very truly yours, 4

A. D. si Nuclear Licensing Administrator l

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/klj cc: NRC Resident Inspector-Byron NRC Resident Inspector-Braidwood Director of Inspection & Enforcement U.S. Nuclear Regulatory Commission Washington, D.C. 20555 1612K

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