ML20210N656
| ML20210N656 | |
| Person / Time | |
|---|---|
| Site: | Braidwood  |
| Issue date: | 09/26/1986 |
| From: | Miosi A COMMONWEALTH EDISON CO. |
| To: | James Keppler NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| References | |
| 85-06, 85-6, NUDOCS 8610060606 | |
| Download: ML20210N656 (2) | |
Text
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} Commonwealth Edison c
72 Wet Adams Stred, Chicago. llknois
-,m"' 7 Address Reply to: Post Office Box 767 Chicago, luinois 60690 - 0767 September 26, 1986 Mr. James G.
Keppler Regional Administrator Region III U.S. Nuclear Regulatory Commission 799 Roonevelt Road Glen Ellyn, IL 60137
Subject:
Braidwood Station Units 1 and 2 10 CFR 50.55(e) No. 85-06 Final Report Failure of Dienol Generators to Sustain Adequate Prime NRC Docket Nos. 50-456/451
References:
(a) August 22, 1985 A.D. Mioni Letter to J.G. Koppler (b) October 21, 1985 A.D. Miosi Letter to J.G.
Keppler
Dear Mr. Keppler:
The above references provided your office with information j
relative to a pot.ential deficiency reportable pursuant to 10 CFR 50.55(e) regarding 1A and 1B diesel generator's failure to sustain adequate prime during testing at our Braidwood Stat. ion.
This letter provides additional information concerning this matter and is considered a final report.
As previously reported, modifications to the fuel oil I
nynt.em were finalized in October 1984.
Modifications were completed by March 1985.
Preliminary testing, following a shutdown period of 18 days of both 1A and 1B diesel generators indicated the modificat.ionn were able t.o uustain fuel oil prine.
However, it was det.ormined that an adequate " proof of design" would be a successful start (under 10 seconds) following a shutdown period of at least 31 days.
The diesel generators were required to support other plant testing, so these modifications could not be tested to the 31-day shutdown criteria.at that time.
On August 4, 1986, following a shutdown period of 82 days, diesel generator 1B wan nLarted in under 10 seconds (5.5 seconds).
This successful start following a shutdown period of 2.5 times i
greater than the normal maximum shutdown period, verifies the adequacy of the design change to the fuel system.
8610060606 860'726 PD9 AUCCK 05000456.
S PDR.
'0 IE 7
, Based on a review of this innue and the modifications made.
Commonwealth Edison has determined this issue not to be reportable pursuant 10 CFR 50.55(e).
Very truly yours, 5
Mf A.D. Miosi Nuclear Licensing Administrator ADM/pav Enclosure cc:
NRC Resident Inspector - Braidwood Director of Inspection and Enforcement U.S. Nuclear Regulatory Commission Washington, DC 20555 2180K
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