ML18010A924
| ML18010A924 | |
| Person / Time | |
|---|---|
| Site: | Harris  |
| Issue date: | 12/01/1992 |
| From: | Starkey R CAROLINA POWER & LIGHT CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NLS-92-152, NUDOCS 9212010016 | |
| Download: ML18010A924 (4) | |
Text
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ACCESSlgg NBB:9212010016 DOC.DATE: 92/12/Ol NOTARIZED: NO DOCKET FACIL:50-400 Shearon Harris Nuclear Power Plant, Unit 1, Carolina 05000400 AUTH.NAME AUTHOR AFFILIATION STARKEY,R.B.
Carolina Power 6 Light Co.
RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)
SUBJECT:
Clarifies 920116 response to NRC station blackout SE Sections 2.2 6 2.2.5.New procedure will rec(uire that battery room temp be verified at not less than 70 F once per day.
Valve 2MD-V77SB-1 will be manually closed.
D DISTRIBUTION CODE: A050D COPIES RECEIVED'LTRI ENCL 6 SIZE:
I TITLE: OR Submittal: Station Blackout (USI A-44) 10CFR50.63, MPA A-22 NOTES:Application for permit renewal filed.
05000400 RECIPIENT ID CODE/NAME PD2-1 PD INTERNAL: ACRS NRR PD2-4PM TAM NRR/DST/SELB NRR/DST/SRXB8E EXTERNAL: NRC PDR COPIES LTTR ENCL RECIPIENT ID CODE/NAME LEPN AEOD/DSP/TPAB NRR/DET/ESGB 8D NRR/j3SZ-/NPLB8Dl gaEe~W NSIC COPIES LTTR ENCL NOTE TO ALL"RIDS" RECIPIENTS:
PLEASE HELP US TO REDUCE WASTE! CONTACT THE DOCUMENT CONTROL DESK.
ROOM Pl-37 (EXT. 504-2065) TO ELIMINATEYOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!
l TOTAL NUMBER OF COPIES REQUIRED:
LTTR 17 ENCL
lg
CMiL Carolina Power & Light Company P.O. Box 1551
~ Raleigh, N.C. 27602 R. B. STARKEY,JR.
Vice President Nuclear Services Department SERIAL:
NLS-92-152 10 CFR 50.63 United States Nuclear Regulatory Commission ATTENTION:
Document Control Desk Washington, DC 20555 SHEARON HARRIS NUCLEAR POWER PLANT DOCKET NO. 50-400/LICENSE NO. NPF-63 CLARIFICATIONS ON STATION BLACKOUT Gentlemen:
On January 16, 1992, Carolina Power 6 Light Company (CPEL) responded to the NRC's Station Blackout Safety Evaluation (SE) for the Shearon Harris Nuclear Power Plant (SHNPP).
The purpose of this letter is to provide clarifications to that response pertaining to SE Sections 2.2 and 2.2.5.
Carolina Power 5i Light Company's response to SE Section 2.2 stated that an existing procedure would be modified to verify that the battery room temperature is not less than 70 F.
We have subsequently determined that it is more appropriate to create a new procedure, an Operations Performance Testr for this purpose.
The new procedure will require that the battery room temperature be verified as not less than 70 F once per day.
In response to Section 2.2.5, we stated that Valve 2MD-V77SB-1 would be utilized for containment isolation.
However, there is an inboard containment isolation valve, 2MD-V36SA-1, which may also be used to ensure containment isolation.
Therefore, Valve 2MD-V77SB-1 will be manually closed to provide containment isolation of the containment sump discharge through penetration X-74 if containment isolation is required and it cannot be verified from Control Room indication that the penetration is already isolated by at least one valve.
Should you have any questions regarding these clarifications, please contact Mr. R.
W. Prunty at (919) 546-7318.
Yours very truly, LSR/gbw R.
B. Starkey, Jr.
cc:
Mr. S.
D. Ebneter Mr. N. B. Le Mr. J.
E. Tedrow
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