ML20004D948
| ML20004D948 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 06/03/1981 |
| From: | Ippolito T Office of Nuclear Reactor Regulation |
| To: | Jackie Jones CAROLINA POWER & LIGHT CO. |
| Shared Package | |
| ML20004D949 | List: |
| References | |
| NUDOCS 8106100382 | |
| Download: ML20004D948 (3) | |
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UNITED STATES
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NUCLEAR REGULATORY COMMISSION 3c,!h.;),.q
.E WASHINGTON, D. C. 20555 o, RnB;W"hj' !
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June 3,1981 Oocket Nos. 50-325 and 50-324 Mr. J. A. Jones Senior Executive Vice President Carolina Power & Light Company 336 Fayetteville Street Raleigh, North Carolina 27602
SUBJECT:
ENVIROMMENTAL QUALIFICATION OF SAFETY-RELATED ELECTRICAL EQUIPMENT RE:
BRUHSWICK STEAM ELECTRIC PLANTS 1 AND 2, LICENSE NO. DPR-71 A!1D DPR-62 Reference (a) - Order for Modification of License Concerning the Environmental Qualification of Safety-Related Electrical Equipment dated October 24, 1980
Dear Mr. Jones:
This letter transmits the Safety Evaluation for the Environmental Qualification of Safety-Related Electrical Equipment at your facility. This evaluation was based on your submittals dated September 19 and Hovember '
1980. Our letter of March 27, 1981, which forwarded our preliminary results, indicated that an item-by-item re-evaluation would be required at a later date. This safety evalu-ation identifies the specific information required by the staff and the actions, on your part, necessary to comply with Reference (a). We request that you provide the informction identified in sections 3 and 4 of this Safety Evaluation to us within 90 days.
This Safety Evaluation addresses only the safety-related electrical equipment exposed to a harsh environment resulting from an accident (i.e., the IEB 79-018 review). Reference (a) requires that all safety-related electrical equipment be qualified by June 30. 1982. The HRC review effort for the equipment in mild environments will be addressed by separate correspondence.
Your response may present alternatives to the staff positions in the evaluation.
The staff will consider alternative approaches if these methods are within the DDR Guidelines or NUREG-0588, as appropriate. For example, an acceptable alternative to the NRC staff's temperature criterion used for the service conditions (i.e. Sectio-3.3) must base that service condition on the FSAR analysis or other NRC approved analysis, orovided that the specific analysis, together with reference to the previous NRC acceptance of that analysis, accompanies the 90 day response. In addition, some of the information in the Safety Evaluation may re-uire clarification. Contact your project manager for assistance in these matters.
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. It ' remains-your responsibility to assure that-the qualificat on deadline is i
met for all safety-related electrical equipment. The staff's review of your response to this letter should not delay-any action which is required in order to meet the deadline.
Sincerely.
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Thomas ppolito, Chief Operating Reactors Branch #2 Division of Licensing
Enclosures:
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SER 2.
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Mr. J.:A. Jones L
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Richard E. Jones, Esquire:
Carolina Power & Light: Company 336 Fayetteville Street Raleigh, North Carolina. 27602 George: F.; Trowbridge, Esquire o
Shaw,.Pittr.an, Pctts & Trowbridge.
1800 M-Street, N. W.
Washington, D.-.C.
20036 John J. Burney, Jr., Esquire-Burney,, Eurney, Sperry & Barefoot 110 North Fifth Avenue Wilmington, North Carolina 28401-Resident Inspector U. S. Nuclear Regulatory Commission l
-P. O. Box 1057
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Southport, North Carolina 28461 L
Southacrt - Brunswick County Libra-v 109 W. Moore Street' Southscrt, North Carolina 28461 I
'<r. Charles R. Dietz-l Plant Manager l
P. 0.' Box 458 Southport,. North Carolina 2E461 4
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