ML19225B477
| ML19225B477 | |
| Person / Time | |
|---|---|
| Site: | Zimmer |
| Issue date: | 07/20/1979 |
| From: | James Keppler NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | Borgmann E CINCINNATI GAS & ELECTRIC CO. |
| References | |
| NUDOCS 7907250224 | |
| Download: ML19225B477 (1) | |
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799 ROOSEVELT ROAD GLEN E LLYN,lLLINolS 60137 JUL 2 01979 Docket No. 50-358 Cincinnati Gas ar.d Electric Company ATTN:
Mr. Earl A. Borgmann Vice President Engineering Services and Electric Production 139 East 4th Street Cincinnati, OH 45201 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 information regarding this matter, please contact this office.
Sincerely,
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vJames G. Keppler Director
Enclosure:
II: Bulletin No. 79-14, page 2, Revision 1 cc w/ encl:
Mr. J. R. Schott, Plant Superintendent Central Files Director, NRR/DPM Director, NRR/ DOR PDR Local PDR 1,
NSIC TIC Harold W. Kohn, Power Siting Commission Citizens Against a Radioactive Environment Helen W. Evans, State of 7.g }
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r IE Bulletin No. 79-14 July 18,1979 Revision i Page 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 analysis applies to the actuar configura-tion of safety-related piping systems. The safety related pipin includes Seismic Category I systems as defined by Regulatory Guide 1.29, g' Seismic Design Classification" Revision 1, dated August 1,1973 or as defined in the applicable FSAR.
The_ action items that follcw apply to all safety related pipint 2 1/2-inches in diameter and greater af
.o seismic Category 1 piplaq7 regarcless of size which was dynamically analyteu by computer.
For older plants, where Seismic Category I requirements did not exist at the time of licensing, it must be shown that the actual configuration of $Fdid safety-related systems, utilizinq 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 confoss 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 information 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 information within 30 days of the date of this bulletin.
2.
For portiors of systems which are nomally accessible *, inspect one system in each set of redundant systems and all nonredundant systems for con-formance to the seismic analysis input infomation set forth in design documents.
Include in the inspection: pipe run geometry; support and restraint design, locations, function and clearance (including floor 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 nonconfomances are found which affect operability of any system, the licensee will expedite completion of the inspection described in Item 3.
- Normally accessible refers to those areas of the plant which can be entered during reactor operation.
398 205 P00R OR.G M