ML19225C712
| ML19225C712 | |
| Person / Time | |
|---|---|
| Site: | Marble Hill |
| Issue date: | 07/20/1979 |
| From: | James Keppler NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | Coughlin J PSI ENERGY, INC. A/K/A PUBLIC SERVICE CO. OF INDIANA |
| References | |
| NUDOCS 7908020352 | |
| Download: ML19225C712 (1) | |
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UNITED STATES J{
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j cLEN ELLYN, ILLINOIS 60117 JUL 2 01979 Docket No. 50-546 Docket No. 50-547 Public Service of Indiana ATTN-Dr. James Coughlin Vice President, Nuclear 1000 East Main Street Plainfield, IN 46168 Gentlemen:
IE Bulletin No. 79-14 is revised to limit th2 scope f work required.
The changes are indicated on the enclosed replacement page far the bulletin.
If you desire additional information regarding this matter, please contact this office.
Sincerely,
?
0.
w 'r ames G. Keppler !
Director
Enclosure:
IE Bulletin No. 79-14, page 2, Rcvision 1 cc w/ encl:
Mr. R. M. Brown, Construction Project Superintendent Central Files Director, NRR/DPM Direc tor, 14RR/ DOR PDR Local PDR NSIC TIC LeBoeuf, Lamb, Leiby 6 :tacRae
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3 IE Bulletin flo. 79-14 July 18,1979 Revision 1 Page 2 of 3 Action to be taken by Licensees and Pemit Holders-All pruer reactor facility licensees and construction permit holders ar e requested to verify, unless verified to an equivalent degree within the last 12 months, that the seismic analysis applies to the actuaT configura-Seismic Category I systems as defined by Regulatory Guide 1.29. g includes tion of safety-related piping sys.tems. The safety related pipin Seismic Design Classification" Revision 1 dated August 1, 1973 or as defined in the applicable FSAR.
The_ action items that follow apply to all safety related pipino. 21/2-inches in oiameter and greater and_ to seismic Category 1 piping, regardless of size which was dynamically analyzed by computer. For older plants, where seismic category I requirements did not exist 7t the time of licensing, it must be shown that the actual configuration of #ftd safety-related systems, utilizing piping 21/2 inches in diameter and greater, meets design requirements.
Specifically, er:h licensee is requested to:
1.
Identify inspection elements to be used in verifying that the seismic analysis input infcrmation 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 infomation 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 infomation within 30 days of the date of this bulletin.
2.
For portions of systems which are nomally acccssible*, inspect one system in each set of redundant systems and all nonredundant systras for con-fomance to the seismic analysis input infomation set forth in design documents.
Include in the inspection: pipe run geometry; support and restraint design, !ccations, function and clearance (including floor and wall penetration); cmbedments (excludino 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).
Witnin 60 days of the date of this bulletin, submit a description of the results of this inspection. Where nonconfomances are found tthich affect operability of any system, the licensee will ex;iedite completion of the inspection described in Itcu 3.
- Normally accessible refers to those areas of the plant which can he entered during reactor operation.
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