ML19247A829
| ML19247A829 | |
| Person / Time | |
|---|---|
| Site: | Rancho Seco |
| Issue date: | 07/18/1979 |
| From: | Engelken R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | Mattimoe J SACRAMENTO MUNICIPAL UTILITY DISTRICT |
| References | |
| NUDOCS 7908020507 | |
| Download: ML19247A829 (1) | |
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=,,,e" WALNUT CREEK, CALIF O3NI A 91596 July 18, 1979 Cocket No. 50-312 Sacramento Municipal Utility District P. O. Box 15830 Sacramento, California 95313 Attention:
Mr. John J. Mattimoe Assistant General Idanager Gentlemen:
IE Bulletin t;o. 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,
/ /
i NOWr/
/R. n Engelken
/ Director Enclosure.
IE Bulletin No. 79-14, Revision 1 cc w/ enclosure:
R. J. Rodriguez, SMUD L. G. Schwieger, 5: DUD 490 112 79 0802(6TJ2
IE Bulletin lio. 79-14 July 18,1979 Revision 1 Page 2 of 3 Action to be taken by Licensees and Permit 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 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 acoly to all safety related pioita 21/2-inches in clameter and greater anc to seismic Category I pioing, regardless of size wnich was d:namically analyzed oy comouter.
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 4MM safety-related systems, utilizing oicing 21/2 inches in diameter and greater, meets design requirements.
Specifically, each licensee is requested to:
1.
Identify inspection eleents to be used in verifying that the seismic analysis input infcrmation confc ms to the actaal configuration of safety-related systems.
For each safetz-related system, submit a list of design documents, including title, identification numW, revisicn, and date, which were sources of input inf~mation for the seismic analyses. Also contained in each dccument.
Ide tify systems or portions of systems which are planned to be inspected during each sequential inspection identified in Items ? and 3.
Somit all of this information with 30 days of the date of this bulletin.
2.
For porticns of systems which are normally accessible *, inspect one system in each set of redundant systems and all ncneedundant systems for con-for ance to the seismic analysis input information set forth in design documents.
Ir.clude in the inspecticn; pipe run geometry; support and restraint design, locations, function and clearance (including ficce and wall penetration); embedents (excluding those covered in IE Euiletin 79-02); pipe attachments; and valve and valve operatcr locations and weights (exclucing these covered in IE Bulletin 73-C4).
Within c0 days of the date Of this bulletin, submit a description of the results of tnis inspection. Where nonccr.formances are found which affect operability of any systa, the licensee will expedite completion of the inspection described in Item 3.
- iornally accessible refers to these areas uf the pl m which can be entered during reactor operation.
490 113 7 907250430
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