ML19225C720
| ML19225C720 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 07/20/1979 |
| From: | James Keppler NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | Burstein S WISCONSIN ELECTRIC POWER CO. |
| References | |
| NUDOCS 7908020359 | |
| Download: ML19225C720 (1) | |
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GLEN ELLYN, ILLINOIS 60137 JUL 2 01979 Docket No. 50-266 Docket No. 50-301 Wisconsin Electric Power Company ATTN:
Mr. Sol Burstein Executive Vice President Power Plants 231 West Michigan Milwaukee, WI 53201 Gentlemen:
IE Bulletin No. 79-14 is revised to limit the scope of work required.
The changes are indicated on the enclosed replacement page for the bulletin.
If you desire additional informa! vr regarding this matter, please contact this office.
Sincerely, w[
60 James G. Keppler Director
Enclosure:
IE Bulletin No. 79-14, page 2, Revision 1 cc w/ enc 1:
Mr. G. A. Reed, Plant Manager Central Files Director, NRR/DPM Director, NRR/ DOR C. M. Tremmel, ORB /NRR PDR Local PDR NSIC
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Sandra A. Bast, Lakeshore
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Citizens for Safe Energy 790802 0359 442 302
IE Bulletin No. 79-14 July 18,1979 Revision 1 Face 2 of 3 Action to be taken by Licensees and Pemit Holders:
All power reactor facility licensees and construction permit holders are requested to verify, unless verified to an equivalent degree within the last 12 months that the seismic anasysis applies to the actuar configura-tion of safety-related piping systems. The safety related pipin Seismic Category I systems as defined by Regulatory Guide 1.29. g includes Seismic Design Classification" Revision 1, dated August 1,1973 or as defined in the applicable FSAR.
The_ action items that follow apply to all safety related pipinc 21/2-inches in diameter and greater and to seismic Category I piping, regarcless of size which was dynamically analyzed by computer. For older plants, where Seismic Category I requirements did nr t exist at the time of licensing, it must be shown that the actual configu?
Jn of #ffd safety-related systems, ut811 zing piping 21/2 inches in diameter and greater,_ meets design requirements.
Specifically, each licensee is requested to:
1.
Identify inspection elements to be used in verifying that the seismic analysis input information confoms to the actual configuration of safety-related systems. For each safety-related system, submit a list of design documents, including title, identification number. revision, and date, which were sources of input infomation for the seismic analyses. Also submit a description of the seismic analysis input infomation which is contained in each document.
Identify systems or portions of systems which are planned to be inspected during each sequential inspection identified in Items 2 and 3. Submit all of this infomation within 30 days of the date of this bulletin.
2.
For portions of systems which are nomally accessible *, inspect one system in each set of redundant systems and all nonredundant systens for con-fomance to the seismic analysis input infonnation set forth in design documents.
Include in the inspection: pipe run geometry; support and restraint design, locations, function and clearance (including floo-and wall penetration); embedments (excluding those covered in IE Bulletin 79-02); pipe attachements; and valve and valve operator locations and weights (excluding those covered in IE Bulletin 79-04).
Within 60 days of the date of this bulletin, submit a description of the results of this inspection. Where nonconformances are found which affect operability of any system, the licensec will ex;iedite completion of the inspection described in Item 3.
- Normally accessible refers to those areas of the plant which can be entered during reactor operation.
442 303 7907250430