ML19247A801
| ML19247A801 | |
| Person / Time | |
|---|---|
| Site: | La Crosse File:Dairyland Power Cooperative icon.png |
| Issue date: | 07/20/1979 |
| From: | James Keppler NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | Linder F DAIRYLAND POWER COOPERATIVE |
| References | |
| NUDOCS 7908020330 | |
| Download: ML19247A801 (1) | |
Text
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799 ROOSEVELT ROAD j'
cLEN ELLYN, ILLINGIS 60137 v
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Jul. 2 01979 Docket No. 50-409 Dairy 1 cad Power Cooperative ATTN:
Mr. F. W. Linder General Manager 261S East Avenue - South La Crosse, WI 54601 Gentlemen:
IE Bulletin No. 79-14 is revised to limit the scope of work 1 quired.
The changes are indicated on the enclosed replacement page for the bulletin. If you desire additional information regarding this.atter, please contact this office.
Sincerely,
. d.
LJames G. Keppler Director
Enclosure:
IE Bulletin No. 79-14, page 2, Revision 1 cc w/ encl:
Mr. R. E. Shimshak, Plant Superintendent entral Files leirector, NRR/DPM Director, NRR/ DOR PDR Local PDR NSIC TIC Anthony Roisman, Esq.,
Attorney
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IE Bulletin No. 79-14 July 18,1979 Revision 1 Page 2 of 3 Action to be taken by Licensees and Pemit Holders:
All power reactor facihty licensees and construction permit holders are requested to verify, unl ms verified to an equivalent degree within the last 12 months, that the seismic analysis applies to the actuar configura-Seismic Category I systems as defired by Regulatory Guide 1.29. g includes tion of safety-related piping systems. The safety related pipin Seismic Design Classificati0n" Revision 1, dated August 1,1973 or as defined in the applicable FSAR. The action items that follo's apply to all safety related pipinc 21/2-inches in diameter and greater an_d 'cFeiLmic Category 1 piping, regarclass of size which was dynamically analyzed by computer. For older plants, where Seismic Category I requirements did not exist at the time of
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licensing, it must be shown that the actual configuration of %5ffd safety-related systems, utilizinq piping 21/2 inches in diameter and greater, meets design requirements.
Specifically, cach licensee is requested to:
1.
Identify inspection esements to be used in verifying that the seistnic analysis input information conforms to the actual configurttion 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 information for the seismic analyses. Also submit 3 description of the seismic analysis input infomation which is contained in each document.
Identify systems or portions of systems which are planned to br: inspected during each sequential inspection identified in items 2 and 3. Submit all of this information 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 recundant systems and all nonredundant systans for con-fomance to the seismic analysis input infomation set forth in design documents.
IN1ude in the inspection: pipe run geometry; support and restraint desir., loc tions, function and clear 3nce (including floor 6nd wait peaetration) embedments (excluding those covered in IE Bulletir 79-02); pipe attachements; and valve and valve operator locat4ns 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 licensee will expedite completion
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of the inspection described in Item 3.
- Nomally accessible refers to those areas of the plant which can be entemd during reactor operation.
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