ML20054F570

Forwards Addl Info Re Safety Evaluation Concerning Implementation of IE Bulletin 80-11, Masonry Wall Design. Results of Confirmatory Plate Analysis After Mods on Walls 19,111-1,111-3N,113 & 114 Encl

ML20054F570
Person / Time
Site:	Point Beach
Issue date:	06/11/1982
From:	Burstein S WISCONSIN ELECTRIC POWER CO.
To:	Clark R, Harold Denton Office of Nuclear Reactor Regulation
References
REF-SSINS-6820, REF-SSINS-SSINS-6 IEB-80-11, TAC-42896, TAC-42896Q, TAC-42897, NUDOCS 8206170114
Download: ML20054F570 (3)

Text

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Wisconsin Electnc rom couem 231 W. MICHIGAN, P.O. BOX 2046. MILWAUKEE, WI 53201 June 11, 1982 Mr. H.

R. Denton, Director Office of Nuclear Reactor Regulation U.

S. NUCLEAR REGULATORY COMMISSION Washington, D. C.

20555 Attention:

Mr.

R. A. Clark, Chief Operating Reactors Branch 3 Gentlemen:

DOCKET NOS. 50-266 AND 50-301 ADDITIONAL INFORMATION IE BULLETIN NO. 80-11, MASONRY WALLS POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2 By your letter of May 11, 1982, you transmitted thee Safety Evaluation Report on the above referenced bulletin work and informed Wisconsin Electric that IE Bulletin 80-11 was considered fully implemented at Point Beach Nuclear Plant subject to the completion of all modifications and the review and acceptance of confirmatory plate analysis after modifications on wall Nos. 19, 111-1, lll-3N, 113, and 114.

Attached for your review are the results of the requested plate analysis.

The allowable stresses given in the attached table are those agreed to in a June 1981 meeting between Wisconsin Electric and the NRC staff.

We have determined that it is not necessary to perform the previously proposed modification to wall No. 133.

During the original field survey this wall was identified as having a possible safety impact on cable Nos. 2-2042A and 2-2042B.

These cables provide control signals for the Unit 2 "A" and "B"

steam generator blowdown isolation valves, located outside containment.

We had previously proposed re-routing these cables.

However, additional steam generator blowdown isolation valves are being installed inside containment as a part of the modifications required by the block wall analysis.

Control cables to the new valves will be routed in such a manner that block wall No. 133 will have no impact on these control cables.

Therefore, it is not necessary to re-route the existing cables. Cf O

8206170114 820611 PDR ADOCK 05000266 O

PDR

M r. II.

R.

Denton June 11, 1982 With the exception of the addition of the steam generator blowdown isolation valves inside containment, all other modifications associated with our block wall analysis have been completed.

The installation of the steam generator blowdown isolation valves is scheduled during the fall 1982 Unit 1 refueling outage and during the spring 1983 Unit 2 refueling outage in accordance with our previous commitments.

Please contact us if you have any further questions.

Very truly yours, O

M t--

T I

l WY. -&

Executive Vice President Sol Burstein Attachment Copy to NRC Resident Inspector J

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