ML19338F920
| ML19338F920 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 09/30/1980 |
| From: | Clark R Office of Nuclear Reactor Regulation |
| To: | Burstein S WISCONSIN ELECTRIC POWER CO. |
| Shared Package | |
| ML19338F921 | List: |
| References | |
| NUDOCS 8010280014 | |
| Download: ML19338F920 (3) | |
Text
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September 30, 1980
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. Docket Nos. 50-266 and 50-301 Mr. Sol Burstein Executive Vice President
. Wisconsin Electric Power Company 231 West Michigan Street
-Milwaukee, Wisconsin 53201
Dear Mr. Burstein:
RE:
POINT BEACH NUCLEAR PLANT Ii4 SERVICE TESTING By letters dated May 20, 1977 and February 26, 1979, you submitted a proposed inservice inspection and testing program description and requests for relief from selected ASME Code requirt.ments pursuant to 10 CFR 50.55a(g). Relief frca those requirements determined by you to oe impractical was granted, on an interim bases, by NRC. letters dated August 26, 1977 (Unit 1) and October 25, 1979 (Unit 2).
5y letters (2) dated July 25, 1980, you submitted a revised pump and valve test program and revised requests for relief from certain Code Require-ments. Although we have not completed our detailed review of your revised pump and valve test program, our preliminary review makes clear to us that your proposed program to implement those ASME Code requirements that you have found to be practical would increase the scope of inservice testing for your facility beyond that currently required by your Technical Spec-ifications.
We have concluded that this upgrading of your inservice testing' program will further enhance safety.
Based on our preliminary review, we agree with your determination that it'
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is impractical within the limitations of design, geometry and materials of construction of components, for you to meet certain of the specified ASME Code requirements and that imposition of those requirements would result in haroships or unusual difficulties without a compensating increase in the level of-quality _or safety. Therefore, pursuant to 10 CFR 50.55a(g)(6)(i),
we hereby grant relief, on an interim basis, pending completion of our detailed review, from those inservice testing requirements of the ASME
. Code that you.have requested.
Moreover, since the scope of the inservice testing will be increased by your proposed program, and the granting of this relief is based only on the impracticality of selected ASME Code
. requirements, we have determined that the relief granted neither increases-l L
8010280014,
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,u4 Mr. Sol Burstein.
. the probability or consequences of accidents previously considered nor decreases safety margins and that, therefore, it does not involve a significant hazards consideration. Therefore, you are authorized to, and should proceed to implement your proposed program (except where your current Technical Specifications are more restrictive).
During the' period between now and the date we complete our detailed review of your submittal, you must comply with both your existing Technical Spec-ifications and your proposed inservice testing program.
In the event conflicting requirements arise for some components, you must comply with the more restrictive requirements (e.g., shorter inspection intervals, increased number of parameters measured).
In other words, the granting of this relief from ASME Code requirements should not be interpreted to give you relief from any of the requirements in your existing Technical Specifications.
When our detailed review of your inservice inspection and testing program is complete, we will:
(1) issue final approval of your program (which may contain modifications resulting from the staff's review), (2) grant relief from ar.y ASME Code requirements that are determined to be impractical for your facility for the duration of the inspection interval, and (3) issue appropriate changes to your Technical Specifications.
A copy of the Federal Reoister Notice related to this actica is enclosed.
Sincerely,
- fgY.h Robert A. Clark, Chief Operating Reactors Branch #3 Division of Licensing
Enclosure:
Federal Recister Notice
.cc'w/ enclosure:
See next page e
9 w
t-Mr. Sol Burstein.
cc w/ enclosure:
Mr. Bruce Churchill, Esquire Shaw, Pittman, Potts and Trowbridge 1800 M Street, N. W.
Washington, D. C.
20036 Document Department University of Wisconsin Stevens Point Library Stevens Point, Wisconsin 54481 f1r. Glenn A. Reed, Manager Nuclear Operations Wisconsin Electric Power Ccrpany Point Beach Nuclear Plant 6610 Nuclear Road Two Rivers, Wisconsin 54241
.