ML20127F291
| ML20127F291 | |
| Person / Time | |
|---|---|
| Site: | Maine Yankee |
| Issue date: | 06/20/1985 |
| From: | Frizzle C Maine Yankee |
| To: | NRC OFFICE OF ADMINISTRATION (ADM), Office of Nuclear Reactor Regulation |
| References | |
| 5977L-GDW, CDF-85-33, MN-85-124, NUDOCS 8506250104 | |
| Download: ML20127F291 (3) | |
Text
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MNRE HARHEE A10MICPOM/ERCOMPARUe nuougr,K,?,la%
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(207) 623-3521 O
June 20, 1985 MN-85-124 COF 33 Director of Nuclear Reactor Regulation United States Nuclear Regulatory Commission Washington, D. C.
20555 Attention:
Document Control Desk
References:
(a) License No. 03R-36 (Docket No. 50-309)
(b) MYAPCo Letter to USNRC dated June 11, 1985 (MN-85-ll5)
(c) MYAPCo Letter to USNRC dated March 5,1985 (MN-85-51)
Subject:
Steam Generator Tube Surveillance Requirements Proposed Change No. 108, Supplement 1 Gentlemen:
Based on discussions with members of your staff, we agreed to modify our Proposed Change No.108, Supplement 1, Reference (b), to clearly reference the reporting requirements of 10 CFR 50.72.
Therefore, please replace Table 4.10-2 of Reference (b) with the attached Table 4.10-2.
The attached table specifically requires that degraded or defective conditions found during steam generator tube inspections be evaluated in accordance with 10 CFR 50.72 and 50.73. Conditions found to be reportable would be reported to the NRC in accordance with the provisions of those-sections.
The requested change is administrative in nature since the requirements of 10 CFR 50.72 and 50.73 already apply to the results of steam generator inspections and therefore, does not consititue a significant hazards consideratio,n.
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8506250104 050620 PDR ADOCK 05000309
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5977L-COW
L MAINE YANKEE ATOMIC POWER COMPANY 3
United States Nuclear Regulatory Commission Page Two Attention: Document Control Desk RJ-85-124 A State of Maine representative is being notified of this matter by a copy of this letter.
Very truly yours, MAINE YANKEE ATOMIC POWER COWANY
/
Charles D. Frizzle Assistant Vice President /
Manager of Operations COF/bjp Attachment (1 Page) cc: Mr. Edward J. Butcher, Jr.
Dr. Thomas E. Murley Mr. Cornelius F. Holden Mr. Clough Toppan STATE OF MAItE
)
)ss COUNTY OF LINCOLN
)
Then personally appeared before me, Charles D. Frizzle, who being duly sworn did state that he is an Assistant Vice President of Maine Yankee Atomic Power Company, that he is duly authorized to execute and file the foregoing response in the name and on behalf of Maine Yankee Atomic Power Company, and that the statements therein are true to the best of his knowledge and belief.
- h. '
Notary Public Of Y PUP I ' IN MY COMMCW IXPK0 IECRUARY 9,1991 59TIL-GDW
r i
TABLE 4.10-2 STEAM GENERATOR TUBE INSPECTION I
ll ll l
l 1st SA WLE INSPECTION ll 2nd SARE INS)ECTION 11 3rd SA R E INSPECTION l
l ll ll l
l l
1 ll l
ll l
l l Sample size l Result l Action Required ll Result l
Action Required ll Result l Action Required l
1 1
I ll l
ll l
l 1
1 I
ll l
ll l
l IA minimum of I C-1 i
None ll N/A l
N/A ll N/A l
N/A l
lS% Tubes l
l ll l
ll l
l
))
Iper S. G.
l 1
ll 1
ll l
l l
l C-2 l Plug defective tubes ll C-1 l
None ll N/A l
N/A I
I l
land inspect additionalil l Plug defective tubes ll C-1 l
None l
l l
l25% tubes in this ll C-2 l and inspect additional ll C-2 l Plug defective tubes l
))
l l
lS. G.
ll l 4S% tubes in this ll l Perrorm action for l
))
l l
l ll l S. G.
ll C-3 l C-3 result of first i
I I
I ll l
ll l sample I
i l
l ll l Perform action for ll l
l l
l l
ll C-3 l C-3 result of first ll N/A I
N/A I
I I
I ll l sample ll l
l l
l C-3 l Inspect all tubes in ll All other l ll l
l l
l l this S.G., plug de-ll S.G.s are l None ll N/A l
N/A l
l l
l fective tubes and ll C-1 l
ll l
l l
l l Inspect 25% tubes ll Some S.G.sl Perform action for ll l
l
))
l l
l each S.G.
l l C-2 but nol C-2 result of second I
N/A N/A l
l l
l additionali sample ll l
l l Report to NRC ll S.G. are l ll l
l
))l l
l l pursuant to ll C-3 l
ll l
l
))]
l l
l 10 CFR 50.72(b)(2) ll Additionall Inspect all tubes in ll l
l
))]
l l
l ll l each S.G. and plug ll l
l
))
I I
l 11 I defective tubes.
ll l
l l
l l
ll l
ll N/A l
N/A l
l l
l ll l Report to NRC pursuant ll l
l
))]
l l
l ll l to 10 CFR 50.72(b)(2) ll l
l
))]-
l l
l 11 I
ll l
l
))]
S = 3 N/n Percent where N is the number of steam generators in the unit, and n is the number of steam generators inspected
))
during an inspection 06/20/85 5977L-GD#