ML19242A807
| ML19242A807 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 07/18/1979 |
| From: | Grier B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | Woolever E DUQUESNE LIGHT CO. |
| References | |
| NUDOCS 7908060368 | |
| Download: ML19242A807 (1) | |
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UNITED STATES g yp..,( [,.g NUCLEAR REGULATORY COMMISSION W'
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KING OF PRUSSIA, PENNSYLVANIA 19406
., jg Docket No. 50-412 Duquesne Light Company ATTN:
Mr. E. J. Woolever Vice President 435 Sixth Avenue Pittsburgh, Pennsylvania 15219 Gentlemen:
IE Bulletin No. 79-14 that was issued on July 2, 1979, is being revised to limit the scope of work required.
The ;5anges are indicated on the enclosed replacement page No. 2 for the Bulletin.
If you desire additional information regarding this matter, please contact this office.
Sincerely,
/
t W
oyce H. Grier Director Enclosure.
1.
IE Bulletin No. 79-14 Revision 1 cc w/encls:
R. J. Washabaugh, Quality Assurance Manager
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ENCLOSURE 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 @ gree within the last 12 months, t. hat the seismic analysis applies to the actual configuration of safety-related piping s/ stems.
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 defined 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 dScamically analyzed by computer. For older plants, where Seismic Category I requirements did not ex tt at the time of licensing, it must be snown that the actual configuration of M did safety related systems, utilizing piping 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 conforms to the actual configuration of safety-related systems.
For each safetyrelated system, subrait a list of design documents, including title, identification number, revision, and date, which were sources of input information for the ceismic analyses.
Also submit a des:ription 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; support and restraint design, locations, function and clearance (including floor and wall penetration); embedments (excluding those cu ered 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 description of the results of this inspection.
Where nonconformances are found whit affect operability of any syste.a, 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.
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