ML20045B235
| ML20045B235 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 06/08/1993 |
| From: | George Thomas DUQUESNE LIGHT CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9306170004 | |
| Download: ML20045B235 (1) | |
Text
., ~. -. -.. _ - -
D-i
.a Beaver Valley Power Station a
SNppingport, PA 15077-0004 H12) 3915206
=
st2> s43-ex9 fax l
l GEORGE S THOMAS June 8,.1993 Diwsion Vice Prmoent Nudear Serv 6ces uve.a< Power oms.on 4
.U.
S.
Nuclear Regulatory Commission l
Attn:
Document Control Desk Washington, DC 20555
- t i
i l[
Subject:
Beaver Valley Power Station, Unit No. 1 Docket No. 50-334, License No. DPR-66 Thirty Percent Steam Generator Tube Plugging Limit s
This letter provides notification that we have performed.an i
evaluation in accordance_ with the requirements of 10 CFR 50.59 to justify an increase in the steam generator tube plugging limit-to' thirty percent.
The number of steam generator tubes to be plugged during the ninth refueling outage was expected to potentially exceed the current analyzed limit.
Therefore, Westinghouse was contracted to perform the analyses required to verify an increased limit.
This has been completed, and the analyses results indicate that increasing the i
steam generator tube plugging limit to thirty percent will not result
[
approached, administrative guidance has-been provided. in the'
~
in exceeding any regulatory limits.
Where design limits were Operating Manual to ensure the design limits are'not s.ceeded.; The i
Westinghouse analyses were performed in accordance with methodologies described in the 'UFSAR accident analyses.and provide verification-that the plant is functionally and structurally capable of continued 1
reliable and safe operation.
In addition, it has been' confirmed that no change to the Cycle 9 COLR and no technical specification' changes-t are required due to the increased steam generator plugging limit.-
i i
The 10 CFR 50.59 safety evaluation for this -item has.been reviewed by the Onsite Safety Committee and the Offsite Review Committee.
It was determined that these changes are safe and-do not j
involve an unreviewed safety question.
Based on the above,-this_
letter is provided for your information only-and NRC review and l
approval is not required.
j Sincerely, I
i 150127
/VM "S l
George-S. Thomas A.;
cc: Mr.
L.
W.
Rossbach, Sr. Resident Inspector Mr. T.
T. Martin, NRC Region I Administrator Mr.
G.
E. Edison, Project Manager i
Mr. M.
L. Bowling (VEPCO) dd.t 1 0 g
9306170004 930608 i'
PDR -ADDCK 05000334 P
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.