ML19225C753
| ML19225C753 | |
| Person / Time | |
|---|---|
| Site: | Cooper  |
| Issue date: | 07/18/1979 |
| From: | Seyfrit K NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | Pilant J NEBRASKA PUBLIC POWER DISTRICT |
| References | |
| NUDOCS 7908020398 | |
| Download: ML19225C753 (1) | |
Text
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July 18, 1979 Doche t ';o.
50-298 t'ebraska Public Power District ATIN:
J. M. Pilant, Director Licensing & Quality Assurance Post Office Box 499 Columbus, Nebraska 68601 Gentlemen:
IE Eulletin 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 infor: ardon regarding this natter, please contact this office.
Sincerely, l
qw nf(; w n' KzfrlV.Seyfrit Director
Enclosure:
IE Eq1 M in No. 79-14 Revision 1 cc:
L. C. Lessor, Superintendent Cooper Nuclear Station Post OfE1ce Box 98 Brownville, Nebraska 63321 r
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7908020398 455 pc L.
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IE Bulletin No. 79-14 Revision 1 Date: Ju?y 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 requested to verify, unless verified to an equivalent degree within the last 12 months, that
..e seismic analysis applies to the actual 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 cpply to all safety-related piping 2-1/2-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 /E/// safety-related systems, utilizing piping 2-1/2 inches in diameter and greater, meets design require-ments.
Specifically, each licensee is requested to:
1.
Identify inspection elements to be used in verifying that the seis.nic 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 seismic analyses. Also submit a description of the seismic analysis input information which is contained in each Jocument.
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 infonnation within 30 days of the date of this bulletin.
2.
For portions of systems which are normally accessibled, 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 ano restraint design, locations, function and clearance (including floor and.;all penetration); embedments (excluding those covered in IE Bulletin 79-02); pipe attachments and valve and valve operator locations and weights (excluding those covered ii IE Bulletin 79-04).
Within 60 days of the date of tais bulletin, submit a description of the results of this inspection.
Where nonconformances are found which af fect operability of any system, the licensee will expedite completion of the inspection described in Item 3.
INormally accessible refers t< those areas of the plant which can be entered during reactor operation.
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