ML19225C710
| ML19225C710 | |
| Person / Time | |
|---|---|
| Site: | 05000580, 05000581 |
| Issue date: | 07/20/1979 |
| From: | James Keppler NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | Ziants C OHIO EDISON CO. |
| References | |
| NUDOCS 7908020349 | |
| Download: ML19225C710 (1) | |
Text
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8 UNITED STATES l'
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'n NUCLEAR REGULATORY COMMISSION 710
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cLEN E LLYN,ILLIP OIS 60137 Pre-CPP The Ohio Edison Company ATTN:
Mr. Charlie Ziants Chief Nuclear QA Engineer 76 South Main Street Akron, OH 44308 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, M/
z.
LJames G. Keppler Director
Enclosure:
IE Bulletin No. 79-14, page 2, Revision I cc w/ encl:
Central Files Director, NRR/DPM Director, NRR/ DOR PDR Local Pun NSIC TIC Harold W. Kohn, Power Siting Commission 1
7908020349 442 334
IE Bulletin No. 79-14 July 18,1979 Revision 1 Page 2 of 3 Action to be taken by Licensees and Pennit Holdars:
All pwer 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 app 1'es 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 itens that follow apply to all safety related pipine 21/2-inches in diameter and greater and_ to seismic Category 1 piping, regarcl_ess 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 ffM safety-related systems, utilizinq piping 21/2 inches in diameter and greater meets 2
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 information for the satsmic analyses. Also submit a description of the seismic analysis input infonnation which is contained in eacn 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 normally accessible *, inspect one system in each set of redundant systems and all nonredundant systems for con-fonnance to the seismic analysis input infonration set forth in design documents.
Include in the inspection; pipe run geometry; support and restraint design, locations, functicn and clearance (including floor and wall penetration); embedments (excluding those covered in IE Bulletin 79-02); pipe attachements; and valve v valve operator locations and weights (excluding those covered in IE ti "atin 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.
- Nonully accessible refers to those areas of the plant which can be entered during reactor operation.
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