ML17319B502

Forwards Update to Util Activities Re NUREG-0737,Item III.A.2.2, Emergency Preparedness Meteorological Data.

ML17319B502
Person / Time
Site:	Cook
Issue date:	08/31/1982
From:	Hunter R INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:	Harold Denton Office of Nuclear Reactor Regulation
References
RTR-NUREG-0737, RTR-NUREG-737, TASK-3.A.2.2, TASK-TM AEP:NRC:0678B, AEP:NRC:678B, NUDOCS 8209030219
Download: ML17319B502 (7)

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'ACCESSION NSR:8209030219.';;,< DOC,DATE: 82/08/31 NOTARIZED: NO., DOCKET PAOIL':50 315 Donald 0, C<<aok .Nuol ear Power Pl anti Unit 1, Indiana 8 05000315

'50~316 Donal,d 0, ~Cook Nuclear Power Plant<< Uni;t 2, 'Indiana BYNAME 8 05000316 AUTH AUTHOR AFFILIATION HUNTERgR ~ ST Indiana L Michigan Electr ic Co,

<<REICI'P ~ NAME RECIPIENT AFFIL'IATION DENTONgH ~ RE Office of Nuclear 'Reactor <<Regulqtioni Director

'SUBJEOT! Forwards -update,'to,util -aotiVities .ve NUREG 0737cIltem ,

III,A,2'< ."Emergency <<Preparedness Meteorological Data,."

DI'STRlBUTION CODE: A046S ~COPIES <<RECEIVEDeLTR, / ENCL / SIZE~

<<TITLE: Response <<to NUREG 0737/NUREG 0660 1TMI Action 'Plan Rgmts (OL's)

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RECIPIENT I lCOP ES RECIPIENT COPIES ID rCODE/NAME LTTR ENCL ID CODE/NAME LTiTR ENCL NRR ORB i 'BC 01 7 <<7 INTlERNALe ELD/HDS3 1 0 IE/DEP DIR 33 1 1 IE/DEP EPDS 1 1 IE/DEP/EPlB '3 3 NRR/DE DI'R 21 1 1 NRR/DE/ADCSE 22 1 1 NRR/DE/ADMQE '23 1 NRR/OHFS DIR 28 1 1 NRR/DHFS/DEPY29 1 1 NRR/DL DIR 14 1 1 NRR/DL/ADL 16 1 1 NRR/DL/ADOR 1'5 1 1 NRR/DL/ADSA 17 1 1 NRR/DL/DRAB 18 t3 3 NRR/DSI DIR 24 -1 1 NRR/DSI/ADCPS25 1 1 NRR/DSI/ADRP 26 1 1 NRR/DS I/ADRS 27 1 1 NRR/DSI/AEB 1 1 NRR/DS I/ETSB 1 NRR/DS I/RAB 1 1 NRR/DST DIR 30 ~ 1 1 P 31 1 NRR/DST/ADT 32 1 1 REG 04 1 1 RGN3 1 1 IESXTERNALa ACRS 34 10 10 FEMA~REP DI V ,1 1

-INPOgJ,"STARNES 1 1 L'PDR 03 2 2 NRC 'PDR 02 1 1 NSIC 05 1 1 NTIS 1 1

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)TOTAL NUMBER OF 'COPIES REQUIRED: LITTR 54 ENCL 53

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INDIANA IIL MICHIGAN ELECTRIC COMPANY P. O. BOX 18 BOWLING GREEN STATION NEW YORK, N. Y. 10004 August 31,. 1982 AEP:NRC:0678B Donald C. Cook Nuclear Plant Unit Nos. 1 and 2 Docket Nos. 50-315 and 50-316 License Nos. DPR-58 and DPR-74 NUREG&737, ITEM III.A.2.2 EMERGENCY

'REPAREDNESS METEOROLOGICAL DATA Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D. C. 20555

Dear Mr. Denton:

The attachment to this letter provides you with an update on our activities relating to Item III.A.2.2 of NUREG-0737, "Emergency Preparedness<<Meteorological Data" as committed to in our letter No.

AEP:NRC:0678A dated June 28, 1982.

This document has been prepared following Corporate Procedures which incorporate a reasonable set of controls to ensure its accuracy and completeness prior to signature by the undersigned.

Very truly yours, R. S. Hunter Vice President RSH/sag Attachment cc: John E. Dolan Columbus M. P. Alexich R. W. Jurgensen W. G. Smith, Jr - Bridgman R. C. Callen G. Charnoff Joe Williams, Jr.

NRC Resident Inspector at Cook Plant Bridgman

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ATTACHMENT TO AEP:NRC:0678B ITEM III.A.2,2. (EMERGENCY PREPAREDNESS-METEOROLOGICAL DATA)

This item is concerned with three subjects'. (1) Meteorological

.Measurements Program, (2) Class A Dose Assessment Capability, and (3)

Class B Dose Assessment Capability.

METEOROLOGICAL HEASUREMENTS PROGRAM We have been informed that the NRC has recently conducted a series of tests along Lake Michigan at the Kewaunee Nuclear Plant between May 28 and June 8, 1982. It is our understanding that the purpose of these studies was to evaluate different meteorological dispersion models and to determine the optimum number of meteorological stations that would provide usable data for these models. Currently, the NRC requirements for supplementary meteorological information are not clearly defined.

NUREG-0654 and Regulatory Guide 1.23 discuss the subject but do not give direct guidelines to be followed. We plan to review the report on the NRC Kewaunee study when we receive it, We plan to await further clarification and NRC guidance, on this matter prior to considering the desirability of system modifications for the Cook Plant.

CLASS A DOSE ASSESSMENT CAPABILITY Class A dose assessment capability exists through the use of Pickard, Lowe and Garrick's (PL&G) ACRISO program to the extent described in AEP:NRC:0678A. The application of the Class A model to the Cook Plant is limited in'hat it does not account for complex flow patterns that may occur during a lake breeze situation and it account for Plant-specific radiation monitor and accident default does not information.

In order to model complex flow patterns, PL&G is proposing a modified Gaussian plume segment model called MIDRAC which they classify as an enhanced Class A model. We have this proposal under evaluation.

The HIDRAC subroutine would utilize a real-time site-specific algorithm for use in turbulent internal boundary layer and lake breeze calculations (see discussion under Class B Dose Assessment Capability) .

We are also evaluating PL&G's proposal to augment our Class A capability by updating the ACRISO program file to contain in-Plant radiation monitor and accident default information. When we have completed the upgrading of our model, we will provide you with a description of our Class A dose assessment capability.

CLASS B DOSE ASSESSMENT CAPABILITY We are presently evaluating proposals from two consultants to provide us with Class B emergency diffusion and dose calculations. Both consultants have indicated that they do not have a Class B model that fully meets the NRC requirements as defined in Revision 1 of NUREG-0654; however, an enhanced Class A model is available'hich will consider site specific phenomena that affect plume transport. We expect that operational implementation of this dose assessment capability at the Cook Plant will take place by the June 1983 date given in NUREG-0737, and prior to this date we will provide you with a description of our plans for a Class B dose assessment capability.

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