ML19225C703
| ML19225C703 | |
| Person / Time | |
|---|---|
| Site: | Bailly |
| Issue date: | 07/20/1979 |
| From: | James Keppler NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | Shorb E NORTHERN INDIANA PUBLIC SERVICE CO. |
| References | |
| NUDOCS 7908020340 | |
| Download: ML19225C703 (1) | |
Text
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GLEN ELLYN ILLINOIS 60137 JUL 2 01979 Docket No. 50-367 Notthern Indicaa Public Service Company ATTN:
Mr. Eugene M. Shorb Senior Vice President 5265 Hohman Avenue Hammond, IN 46325 Gentiemen:
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, b.
V y
/
L James G. Keppler Director
Enclosure:
IE Bulletin No. 79-14, page 2, Revision 1 cc w/ encl:
Central Files Di".ctor, NRR/DPM L1 rector, iiRR/ DOR PDR Loccl PDR NSIC TIC Mr. Te n Hansell, Office of Assir : ant Attorne-f General 790802 0340 455 gag
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t IE Bulletir No. 79-14 July 18,1979 Revision 1 Page 2 of 3 Action t: bc 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 actuaT 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 apply to all safety related piping 21/2-inches in diame er and greater an_d to seismic Category I piping, regardless of size which was dynamically analyzed by computer.
For older plants, where Seismic C6tegory I requirements did not exist at the time of licensing, it must be shown that the actual configuration of SAfd 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 that the seismic analysis input information confoms tn the actual configuration of safety-related systems.
For each safety-related s, tam, submit a list of design docurents, including title, identification nur >er, revision, and date, which were sources of input information for the seismic analyses. Also submit a description of the seismic analysis input infonnation which is contained in cach 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 informatior, within 30 days of the date of this bulletin.
2.
For portions of systems which are nonnally accessible *, inspect one system in each set of radundant systems and all nonredundant systems for con-formance 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 (1acluding floor and wall penetration); embedments (excluding Gose 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 nonconformances are found which affect nerability 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, q 9 '70 0
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