ML19344D657

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Submits Info Re Fire Barrier Penetration Seals & Supervision of Valve Control Circuits,In Response to .Valve Control Circuit Mod Completed & Tested for Unit 2.Unit 1 Will Be Completed by 800615.Forwards Tech Spec Changes
ML19344D657
Person / Time
Site: Brunswick  Duke Energy icon.png
Issue date: 04/22/1980
From: Utley E
CAROLINA POWER & LIGHT CO.
To: Ippolito T
Office of Nuclear Reactor Regulation
Shared Package
ML19344D658 List:
References
NO-80-603, NUDOCS 8004250410
Download: ML19344D657 (2)


Text

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ML Carolina Power & Light Company I

April 22, 1980 i

FILE: NG-3514(B)

SERIAL NO:

NO-80-603 Office of Nuclear Reactor Regulation i

ATTENTION:

Mr. T. A. Ippolito, Chief l

Operating Reactors Branch No. 3 t

i United States Nuclear Regulatory Commission i

Washington, D. C.

20555 BRUNSWICK STEAM ELECTRIC PLANT, UNIT NOS. 1 AND 2 DOCKET NOS. 50-325 AND 50-324 LICEN'iE NOS. DPR-71 AND DPR-62 i

FIRE PROTECTION i

Dear Mr. Ippolito:

In response to your February 14, 1980 letter concerning fire barrier f

penetration seals and supervision of valve control circuits, Carolina Power &

i Light Company (CP&L) submits the following information for the Brunswick Steam Electric Plant (BSEP) Unit Nos. 1 and 2.

i i

CP&L has prepared the attached proposed technical specifications for fire barrier penetration seals in accordance with the format guidance provided i

in the GE STS transmitted by your February 14, 1980 letter. However, we have i

made several technical changes which wa feel will enhance the usefulness of the tech. specs. provides the justifications for our changes to the STS.

J No license amendment application fee is required since this submittal is in response to a written Commission request as described in footnote-2 to 10 CFR 170.22.

The second item of your February 14, 1980 letter required that CP&L upgrade the valve control circuits to include electrical supervision for the t

valves that are normally closed but would have to be remotely operated from l

the control room to supply water to the reactor building standpipe system.

I This modification on the BSEP-2 valve control circuit has been completed and acceptance tested satisfactorily. The modification on BSEP-1 is in progress i

and should be completed by June 15,-1980.

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8004250 4/O 411 Fayetteville Street

  • P. O Box 1551
  • Raleigh, N. C. 27602 A

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. If you have any questions concerning this information, please contact my staff.

Yours very truly,

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E. E. Utley Executive Vice President Power Suppl. & Customer Services JAM /tl Attachrents Sworn to and subscribed before me this 22nd day of April 1980 h)lLthfw Notary Public My commission expires: October 4, 1981 1%\\\\Itfitpg,

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