ML19274F794
| ML19274F794 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 07/18/1979 |
| From: | Engelken R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | Johari Moore SOUTHERN CALIFORNIA EDISON CO. |
| References | |
| NUDOCS 7908020500 | |
| Download: ML19274F794 (1) | |
Text
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UNITED STATES
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WALNUT CREEK, CALIFORNIA 94596 July 18, 1979 Docket Mos. 50-361 50-362 Southern California Edison Company P. O. Box 800 2244 Walnut Grove Avenue Rosemead, California 91770 Attention: Mr. J. B. Moore Vice President 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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R A Ehgelken Director
Enclosure:
IE Bulletin No. 79-14, Revision 1 cc w/ enclosure:
J. H. Drake. SCE 1908020708
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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 facility licensees and construction pemit holders are requested to verify, unless verified to an equivalent degree within the last 12 months, that the seismic analysis applies to the acutal configura-tion of safety-related piping systems. The safety related piping includes Seismic Category I systems as defined by Regulatory Guide 1.29, " Seismic Design Classification" Revision 1, dated August 1,1973 or as defined in the applicable FSAR. The action items that follow aoply to all safety related pioino 2 1/2-inches in diameter and greater and to seismic Category I pioing, regardless of size which was dynamically analyzed by cenouter.
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 %MM safety-related systems, utilizing pioino 21/2 inches in diameter and creater, meets design requirements.
Specifically, each licensee is requested to:
1.
Identify inspection elements to be used in verifying tilat the seismic analysis input information conforms 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 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 with 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 systems for con-formance to the seismic analysis input information set forth in design documents.
Include in the inspection; pipe run geometry; support and restraint design, locations, function and clearance (including ficor and wall penetration); embedments (excluding those covered in IE Bulletin 79-02); pipe attachments; 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 licensee will expedite completion of the inspection described in Item 3.
- Nomally accessible refers to those areas of the plant which can be entered
'during reactor operation.
7 907250430
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