ML19225A457
| ML19225A457 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 06/12/1979 |
| From: | Utley E CAROLINA POWER & LIGHT CO. |
| To: | James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| References | |
| NG-3513(B), NUDOCS 7907190368 | |
| Download: ML19225A457 (2) | |
Text
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%u Carolina Power & Light Company June 12, 1979 FILE: NG-3513 (B)
SERIAL: GD-79-1545 %
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M' O Mr. James P. O'Reilly, Director c.o United States Nuclear Regulatory Commission c
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- S Region II 101 Marietta Street, Suite 3100 f
'f Atlanta, GA 30309 BRUNSWICK STEAM ELECTRIC PLANT, UNIT NOS. 1 AhT 2 DOCKET NOS. 50-325 AND 50-324 LICENSE NOS. DPR-71 AhT DPR-62 RESPONSE TO IE BULLETIN 79-01 7
Dear Mr. O'Reilly:
Your letter of February 8, 1979, requested information on the environmental qualification of safety-related electrical equipment at the Brunswick Plant. The attached report contains the information we have been able to obtain thus far.
Carolina Power & Light Company's original response to IE Bulletin 78-04 on, March 29, 1978, indicated that none of the stem-mounted limit switches of concern at that time were installed on safety-related equipment.
Subsequent checking on the additional switches listed in IE Bulletin 79-01 has confirmed that none of these switches ere in use on safety-related equipment.
Therefore, Brunswick has no concerns with NAMCO stem-mounted limit switches.
The attached report.
epresent all of the data we wt.
.e to collate by your requested submittal date.
For several t
- of equipment; we expect to be able to find additional information.
Carolina Power & Light Company will issue a revision to this report when more information becomes available but not later than September 14, 1979. If at any time in our continued investigation we discover any equipment which has testing information which shows that it is not qualified, you will be notified immediately in compliance with Bulletin 79-01. The revision will also include CP&L's proposals for corrective action for those items for which insuf ficient test data is found.
To date the only tested but unqualified equipment identified has been the nylon insulating sleew portion of the AMP termination lugs, and both your office and the Office of Nuclear Reactor Regulation (ONRR) were notified on May 25, 1979, of this issue. Subsequent communication with ONRR has developed acceptable interim corrective e
ling
, l 7 f o on]gt refue actions until a permanent fix can be installed at the Q
outages.
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1 411 Fa yettawe Stree!
- P O Box 1551 e Ra'ep N C2%2 s=n._., _ _ c._
.pCIAL COPY
a Mr. James P. O'Reilly June 12, 1979 The C"eral Electric portion of the attached report identifies that no information is available for a Barksdale differential pressure transmitter and the MSIV limit switches, and they provide justification for no qualification on this equipment.
If you have any questions, please do not hesitate to contact my staff.
Yours very truly, d
d E. E. Utley Executive Vice President Power Supply & Customer Services CSB/j nh*
f 420 118 d