ML19225C699
| ML19225C699 | |
| Person / Time | |
|---|---|
| Site: | Fermi  |
| Issue date: | 07/20/1979 |
| From: | James Keppler NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | Hines E DETROIT EDISON CO. |
| References | |
| NUDOCS 7908020333 | |
| Download: ML19225C699 (1) | |
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o GLEN ELLYN, ILLINOIS 60137 lVL 2 01979 Docket No. 50-341 The Detroit Edison Company ATTN:
Mr. Edward Hines, Assictant Vice President and Manager Quality Assurance 2000 Second Avenue Detroit, MI 48226 Centlemen:
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,
% /
/ James G. Keppler
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Director
Enclosure:
lE Bulletin No. 79-14, page 2, Revision 1 cc w/ encl:
Central Files Director, NRR/DPM Director, NRR/ DOR PDR Local PDR NSIC TIC Ronald Callen, Michigan Public Service Cocmission Eugene B. Thocas, Jr.,
Attorney
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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 actuar configura-Seismic Category I systems as defined by Regulatory Guide 1.29, g includes tion of safety-related piping systems. 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 piping 21/2-inches in diameter and greater and to ;eismic Category 1 piping, regardless 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 %W/d safety-related systems, utilizing piping 21/2 inches in diameter _and greater, meets design requirements.
Specifically, each licensee is requested to:
1.
Identify inspection elements to be used in verifying '. hat the seismic analysis input information conforms to the actual configuration of safety-reiated systems.
For each safety-related system, suomit a list of design documents, including title, identification number, revision, and date, which were sources of input information for the seismic analyses. Also submit a description of the seismic a'alysis input infonnation 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 accessiule*, ir.;pect one system in each set of redundant systems and all nonredundant syr. ems for con-romance 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 (excluding 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).
Within 60 days of the date of this bulletin, submit a description of the results of this inspection. Where nonconfonnances are found which affect operability of any system, the licensee will expedite completion of the inspection described in Item 3.
- Normally 5ccessible refers to those areas of the plant which can be entered during reactor operation.
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