ML17328A190

Forwards Addl Info Re Radiation Monitoring Sys Per NRC Request.Description of How Gaseous Radioactive Monitor Readings Corrected & Calculation to Determine If Monitor Can Survive post-accident Environ,Per Info Notice 86-030,encl

ML17328A190
Person / Time
Site:	Cook
Issue date:	10/05/1989
From:	Alexich M INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:	Murley T NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
RTR-NUREG-0737, RTR-NUREG-737 AEP:NRC:0856X, AEP:NRC:856X, IEIN-86-030, IEIN-86-30, NUDOCS 8910160287
Download: ML17328A190 (12)

Text

3]STKBUTION 'EMONSTRk TIOYi SYSTEM REGULATOIINFORMATION DISTRIBUTION'STEM (RIDE)

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'CCESSION NBR:8910160287 DOC.DATE: 89/10/05 NOTARIZED: NO DOCKET FACIL:50-315 Donald C.

Cook Nuclear Power Plant, Unit 1, Indiana 6

05000315 50-316 Donald C.

Cook Nuclear Power Plant, Unit 2, Indiana 6

05000316 AUTH.NAME AUTHOR AFFILIATION ALEXICH,M.P.

Indiana Michigan Power Co. (formerly. Indiana 6 Michigan Ele RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)

SUBJECT:

Forwards addi info re radiation monitoring sys per Staff request.

DISTRIBUTION CODE:

AOOSD COPIES RECEIVED:LTR J ENCL L SIZE:

TITLE: OR/Licensing Submittal: Appendix I NOTES:

RECIPIENT ID CODE/NAME PD3-1 LA GIITTER,J.

INTERNAL: NRR/DREP DIR10E NUDOCS-ABSTRACT OGC/HDS1

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Indiana Michigan Power Company P.O. Box $ 6631 Coiumbus, OH 43216 8

AEP:NRC:0856X 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 0737, SECTION II.F.1-2 U.S. Nuclear Regulatory Commission ATTN:

Document Control Desk Washington, D.C.

20555 ATTN:

T.

E. Murley October 5, 1989

Dear Dr. Murley:

This letter provides additional information regarding radiation monitoring systems as requested by a member of your staff.

The information supports our previous submittal AEP:NRC:0678Y, dated July 23,

1986, and is provided on the two attachments.

Attachment 1 is a description of how the gaseous radioactive effluent monitor readings are corrected for decay for the purpose of off-site dose calculation.

Attachment 2 is a copy of an internal calculation to determine if the radiation monitor could survive in a post accident environment per IE Information Notice 86-30.

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

Very truly yours, M.

. Al xich Vice President edg Attachments cc:

D. H. Williams, Jr.

A. A. Blind - Bridgman R.

C. Callen NFEM Section Chief G. Charnoff NRC Resident Inspector

- Bridgman A. B. Davis

- Region III 8910160287 891005 PDR ADQCK 05000315 P

PNU

ATTACHMENT 1 AEP:NRC:0856X

Attachment 1 to AEP:NRC:0856X Page 1

The response of the Eberline SPING gaseous effluent radiation monitor (low-, mid-, and high-range channels) was calculated as a function of time for a postulated accident.

The response of the detectors to the post-accident gas mixture was determined by utilizing the primary calibration efficiencies of each detector type.

The result of the analysis provided tables of post-accident decay correction factors which can be applied to the radiation monitoring channels.

These correction factors had been inserted into and made part of our off site dose assessment computer code (DAP).

DAP estimates off site doses to the whole body and thyroid resulting from plant releases.

The user is prompted to input the following information:

meteorological data, radiation monitor reading, time of reactor

shutdown, duration of release, effluent flow rates, and the type of the accident that would be considered.

During the process of calculating the estimated

doses, the computer code automatically retrieves the gas mixture decay factor, which is a dimensionless multiplier, for the appropriate monitor reading.

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