ML19225C763
| ML19225C763 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 07/19/1979 |
| From: | Engelken R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | Johari Moore SOUTHERN CALIFORNIA EDISON CO. |
| References | |
| NUDOCS 7908020408 | |
| Download: ML19225C763 (1) | |
Text
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o UNITED STATES
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NUCLEAR REGULATORY COMMISSION
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REGION V
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cf 1990 N. CAL'FORNI A BCULEVARD r, ' f SUIT E 202, i;ALNUT CR E E K PL AZ A 6g ' br j
- ,,,e WALNUT CREEK, CALIFORNI A 94595 July 19, 1979 Docket fics. 50-351 50-362 Southern California Edison Ccmpany P. O. Box 800 2244 Walnut Grove Avenue Rosemead, California 91770 Attention:
Mr. J. B. Mcore Vice President Gentlemea:
Attached is a corrected copy of Revision 1 to IE Bulletin tio. 79-14 mailed to you cn July 13, 1979. A sentence was inadvertently cmitted from the previous copy.
Sincerely, nf$W%~ydL R. H. Engelken Director Encicsure:
IE Bulletin tio. 79-14, Revision 1 -- Corrected Ccpy cc w/ enclosure:
J. H. Crake, SCE
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7908050408
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IE Bulletin. 0.
79-14 July 18, 1979 1
Revision 1 Page 2 of 3 Action to be taken by Licen;ees and Permit Hciders:
All cower reactor facility licensees and constructi:n permit holders are recuested to verify, unless verified to an equivalent degree within the last 12 months, that the seismic analysis applies to the actual configura-tien of safety-related piping systems.
The safety elated piping includes Seismic Category I systems as defined by Regulatory G;ide 1.29, " Seismic Design Classification" Revision 1, dated August 1,1973 or as defined in the a,cplicable FSAR.
The action items that folicw acoly to all safety related cioina 21/2-inches in ciameter and creater anc to seismic Catecory I cioina, regarcless of size waicn was dynamically analyzed by c;mouter. For older plants, wnere Seismic Category I requirements cid not exist at the time of licensing, it must be shown that tne actual configuration of tXH4 safety-related systems, utilizing cicing 21/2 inches in diar.eter 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 infor ation conforms to the actual configuration of safety-related systems.
For each safety-related syster., submit a list of design documents, including title, identification number revisicn, and date, which were sources of input information for the seismic analyses. Also submit a description of the seismic analysis inpuc information wnich is contained in each document.
Identify systems or ;ortions of systems which are planned to be irspected 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 normally accessible *, inspect one system in each set of redundant systems and all ncnredundant systems for con-formance to the seismic a. alysis incut information set forth in design dccaments.
Include in the inspection: pipe r 1 geometry; suppcrt and restraint design, locati:ns, functicn and cle ance (including ficor and wall penetration); -mcecments (exclucing these ccvered in IE Ealletin 79-C2), cipe a tachemer 7; and valve and valve operator locations and weights (excludi %
'cse covered in IE Sulletin 79-M).
Within Q days of the date of this uulletin, suhit a description of the results of this inspecticr.
Where r.cnconformnces are fourd dich affect operability Of ary systea, the licensee will expedite ccm letion of the inspecticn descriced in Item 3.
%cr aily accessible refers to those areas of the plant whith can be entered during reactor cperation.
C0RRiCTED C0PY 7907250430 s
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