ML19225C719
| ML19225C719 | |
| Person / Time | |
|---|---|
| Site: | Callaway  |
| Issue date: | 07/20/1979 |
| From: | James Keppler NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | Bryan J UNION ELECTRIC CO. |
| References | |
| NUDOCS 7908020358 | |
| Download: ML19225C719 (1) | |
Text
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UNITED STATES E'
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JUL 2 01979 Docket No. 50-4S3 Docket No. 50-486 Union Electric Company AT1N:
Mr. John K. Bryan Vice President - Nuclear P. O. Box 149 St. Louis, MO 63166 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, s
1 James G. Keppler Director
Enclosure:
IE Bulletin No. 79-14, page 2, Revision 1 cc w/ encl:
Mr. W. H. Weber, Manager, Nuclear Construction Central Files Director, NRR/DPM Director, NRR/ DOR PDR Iccal PDR NSIC R ion I & IV 2
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Ms. K. Drey Hon. C. J. Frass, Chairman Missouri Public Service Con.nission 3
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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 Pennit 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 e-tuar 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.
T_he_ action items that follow apply to all safety related pipinc 21/2-inches in diameter and greater and to seismic Category I piping, regarcless of size which was dynamically analyzed 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 f#ffd safety-related systems, utilizino piping 21/2 inches in diameter and areater, meets design requirements.
Specifically, each licensee is requested to:
1.
Identify inspection elements to be used in verifying that 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 infonnation for the seismic analyses. Also submit a description of the seismic analysis input information 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 portions of systems which are nomally accessible *, inspect or.e system in each set of redundant systems and all nonredundant systems for con-fomance to the seismic analysis input infonnation 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 Hluding those covered in IE Bulletin 79-02); pipe attachements; to 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.
- Normally accessible refers to those areas of the plant which can be entered during reactor operation.
442 305 7 907250430