ML19242A819
| ML19242A819 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 07/18/1979 |
| From: | Grier B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | Daltroff S PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC |
| References | |
| NUDOCS 7908060400 | |
| Download: ML19242A819 (1) | |
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'%d KING of PF PENNSYLVANIA 19406 Docket Nos. 50-277 y 8 I873 50-278 Philadelphia Electric Company ATTN:
Mr. S. L. Daltroff Vice President Electric Production 2301 Market Street Philadelphia, Pennsylvania 19101 Gentlemen:
IE Bulletin No. 79-14 that was issued on July 2, 1979, is being revised to limit the scope of work required.
The changes are indicated on the enclosed replacement page No. 2 for the Bulletin.
If you desire additi,nal information regarding this matter, please contact this office.
Sincerely,
/ Afze
~
Boyce H. Grier Director
Enclosure:
1.
In Bulletin No. 79-14 Revision 1 cc w/encls:
W. T. Ullrich, Station Superintendent Troy B. Conner, Jr., Esquire Eugene J. Bradley, Esquire Raymond L. Hovis, Esquire Warren Rich, Esquire L1A ITC y19 JJ/
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ENCLCSURE 1 IE Bulletin No. 79-14 Revision 1 Date:
July 18, 1979 Page 2 of 3 Action to be taken by Licensees and Permit Holders:
All power reactor facility licensees and construction permit holders are re-quested to verify, unless verified to an equivalent degree within the last 12 months, that the seismic analysis applies to the actual configuration of safety-related piping systems.
The safety related piping includes Seismic Category I systems as defined by Regulatory Guide 1.29, " Seismic Design Clas-sification" Revision 1, dated August 1,1973 or as definM in the applicable FSAR.
The action items that follow apply to all safety related piping 2 -inches in diameter and greater and to seismic Category I 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 G did safety-rezated systems, utilizing piping 2\\
inches in diameter and greater, meets design requiremei.ts.
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 safetyrelated system, submit a list of design documents, including title, identification number, revisicn, and date, which were sources of input information 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 normally accessible *, inspect one system in each set of redundant systems and all nonredundant systems for con-formance to the seismic analysis input information set forth in design documents.
Include in the inspection: pipe run geometry; suoport and restraint design, locations, function and clearance (including floor and wall penetration); embedments (excluding those covered in IE Bulletin 7902); pipe attachments; and valve and valve operator locations and weights (excluding those covered in IE Bulletin 7904).
Within 60 days of the date of this bulletin, submit a descriotion of the results of this inspe tion.
Where nonconformances are ound which affect operability of any system, the licensee will expedite completion of the inspection described in Item 3.
^Nor.nu a ly accessible refers to those areas of the plant which can be entered du ing reactor operation.
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