ML19225C752
| ML19225C752 | |
| Person / Time | |
|---|---|
| Site: | Waterford  |
| Issue date: | 07/18/1979 |
| From: | Seyfrit K NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | Aswell D LOUISIANA POWER & LIGHT CO. |
| References | |
| NUDOCS 7908020397 | |
| Download: ML19225C752 (1) | |
Text
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h UNITED STATES
? '.";,,,,,': 1 NUCLEAR REGULATORY COT / MISSION
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E REGION IV
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011 RY A*J PL A Z A o AlVE, SUITE 1000
' t, AR LINGTON, TE X AS 76C 12 July IS, 1979 In Reply R fer To:
RIV Donket No.
30-332/IE Eulletin Sc. 79-14 Revision 1 Lcuisiana Power and Light Co.
ATT'* -
M_r. D. L. Aswell Vice President of Power Production 142 Delarcade Street New Orleans, Louisiana 70174 Gentlemen:
IE 3ulletia 79-14 is revised to li=1t the scope of work required.
The changes are indicated on the enclosed replacement page for the bulletir.
If you desire additional information regarding this =atter, please contact this office.
Sincerely,
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Karl V. Seyfrit Director
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Enciasure' IE Eulletin 50. 79-14 Revision 1 er~
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IE Eulletin No. 79-14 Revision 1 Date:
July 13, 1979 Page 2 of 3 Action to be ta'<en by Licensees and Permit Holders:
All power reactor facility licensees and coastruction permit holders are requested to "-rify, unless verified to an equivalent degree within the last 12 conths, that the 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 F3AR.
The action items that follow acply to all safetv-related piping 2-1/2-inches in diameter and greater and to seisaic Category I piping, re2 rdless of sice which was dynamically analyzed oy cc:puter.
ror older plants >
--where Seisaic Category I requirements did not exist at the tice of licensing, it. must be shown that the actual configuration of f'ss/ safety-related systems, i
utilizing piping 2-1/2 inches in diaceter and greater, meets design require-cents.
Specifically, each licensee is requested to:
1.
Identify inspection elecents 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 seisaic analyses.
Also submit a description of the seismic analysis input information which is contained ia each document.
Identify systems or portions of systems which are pla-aal *o 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 porticas of systems which are nor= ally accessible *, inspect cne system in each set of redundant systeas and all nonredundant systeas for con-forcance ta the seismic analysis input inforeatica set forth in desig documents.
Include in the inspection: pipe run ge:cetry- ;upport and restraint design, loca,i: s, function and clearance (includ: g floor and wall penetration), embed ents (excluding those cavere! in IE Eulletin 79-02); pipe a:tachments and valve and valve ope: 2;or locations and weights (excludin; those covered in :E Eulletin 79-04).
Within c0 days of the date of this bulletin, submit a ces:ription of the results of this int actim Where ncnconformances are found which af fect operability of any system, the license' will expedite cc:pletion of the inspection described in Ites 3.
wNorcall, accessible refers to those areas of the plant which can be entered during reactor operation.
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