ML18016A867

Submits Response to RAI Re Spent Fuel Pool Water Level & Revised Fuel Handling Accident Analyses,Per 990317 Telcon with NRC

ML18016A867
Person / Time
Site:	Harris
Issue date:	03/19/1999
From:	Scarola J CAROLINA POWER & LIGHT CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
HNP-99-053, HNP-99-53, NUDOCS 9903290234
Download: ML18016A867 (5)

Text

CATEGORY 1-REGULA Y INFORMATION DISTRIBUTIO SYSTEM (RIDS)

ACCESSION NBR:9903290234 DOC.DATE: 99/03/19 NOTARIZED: NO DOCKET ¹ FACIf".50-4(0 Shearon Harris Nuclear Power Plant, Unit 1, Carolina 05000400 AUTH..~AME 'UTHOR AFFILIATION SCAROLA,J. Carolina Power 8 Light Co.

RECIP.NAME RECIPIENT AFFILIATION Records Management Branch (Document Control Desk)

SUBJECT:

Submits addi info for proposed SF Pool Water Level &, revised fuel handling accident analyses LAR dtd 980901,per 990317 telcon. A DISTRIBUTION CODE: A001D COPIES RECEIVED:LTR ENCL SIZE:

TITLE: OR Submittal: General Distribution NOTES:Application for permit renewal filed,. 0500040&

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'ECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL' PD2-1 LA PD2-1 PD FLANDERS,S INTERNAL: ACRS ILE CENTER 0 NRR/DE/ECGB/A NRR DE EMCB NRR/DRCH/HICB NRR/DSSA/SPLB NRR/DSSA/SRZB NRR/SPSB JUNG,I NUDOCS-ABSTRACT OGC/HDS2 EXTERNAL: NOAC NRC PDR D

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NOTE TO ALL "RIDS" RECIPIENTS:

PLEASE HELP US TO REDUCE WASTE. TO HAVE YOUR NAME OR ORGANIZATION REMOVED FROM DISTRIBUTION LISTS OR REDUCE THE NUMBER OF COPIES RECEIVED BY YOU OR YOUR ORGANIZATION, CONTACT THE DOCUMENT CONTROL DESK (DCD) ON EXTENSION 415-2083 TOTAL NUMBER OF COPIES REQUIRED: LTTR 15 ENCL

Carolina Power & Ught Company James Scarola PO Box 165 Vice President New Hill NC 27562 Harris Nuclear Plant SERIAL: HNP-99-053 MAR 19 1999 10CFR50.90 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 RESPONSE TO REQUEST FOR ADDITIONALINFORMATION SPENT FUEL POOL WATER LEVEL AND REVISED FUEL HANDLINGACCIDENT ANALYSES

Dear Sir or Madam:

Per telephone conversation with the NRC staff on 3/17/99, Harris Nuclear Plant (HNP) submits additional information for the proposed Spent Fuel Pool Water Level and Revised Fuel Handling Accident Analyses License Amendment request, dated September 1, 1998.

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1. What is the value of the atmospheric dispersion coefficient (X/Q) used in evaluating the Main Control Room dose during a radiological accident?

2. Has the proposed submittal affected the Main Control Room dose with respect to the most limiting accident?

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1. The X/Q value in evaluating Main Control Room dose during a radiological accident is 7.68 x 10 sec/m .

2. The HNP FSAR states that the LOCA event is the most limiting event for control room habitability dose criteria. The increase in dose resulting from the revised fuel handling accident analyses; described in the September 1, 1998 submittal, is small relative to the Main Control o Room dose as a result of a LOCA. The LOCA accident remains the most limiting accident with respect to Main Control Room dose.

Please refer any questions regarding this submittal to Mr. J. H. Eads at (919) 362-2646. 00I 990p290234 9903i9 PDR g ~ ADQCK '",05000400 M . Si cerely, P -. ~p'".t'~" PDR 5413 Shearon Harris Road New Hill, NC Tel 919 362-2502 Fax 919 362-2095

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Mr. J. B. Brady, NRC Sr. Resident Inspector Mr. Mel Fry, Acting Director, N. C. DEHNR Mr. R. J. Laufer, NRC Project Manager Mr. L. A. Reyes, NRC Regional Administrator

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