ML20206G591

Forwards Supplemental Matl to Quarterly Dose Assessment Repts &/Or Semiannual Radioactive Effluent Release Repts for 1984 & 1985.Future Repts Will Be Updated Only If Sr-90 Activity in Effluent Exceeds Unidentified Beta Activity

ML20206G591
Person / Time
Site:	Three Mile Island
Issue date:	06/13/1986
From:	Standerfer F GENERAL PUBLIC UTILITIES CORP.
To:	Murley T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
Shared Package
ML20206G594	List: ML20206G591 ML20206G746 ML20206G757 ML20206G768 ML20206G784 ML20206G799 ML20206G819 ML20206G839 ML20206G858
References
4410-86-L-0100, 4410-86-L-100, NUDOCS 8606250379
Download: ML20206G591 (3)

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1. Middletown, Pennsylvania 17057-0191 717 944 7621 TELEX 84 2386 Writer's Direct Dial Number:

(717) 948-8461 4410-36-L-0100 Document ID 0311A June 13, 1986 Office of Inspection and Enforcement Attn: Dr. T. E. Murley Regional Administrator US Nuclear Regulatory Commission Region I 631 Park Avenue King of Prussia, PA 19406

Dear Dr. Murley:

Three Mile Island Nuclear Station, Unit 2 (TMI-2)

Operating License No. DPR-73 Docket No. 50-320 Quarterly Dose Assessment Report - Second Quarter 1985 Semi-Annual Radioactive Effluent Release Report Pursuant to discussions with the TMI-2 Cleanup Project Directorate (CPD),

attached are page revisions to the Quarterly Dose Assessment Report and the Semi-Annual Radioactive Effluent Release Report for the years 1984 through 1985. These revisions conservatively report all previously reported unidentified beta activity as Sr-90 activity.

In 1984, GPU Nuclear initiated a sump composite sampling program. The quarterly samples were sent offsite to be analyzed for Sr-90 activity.

However, due to the length of time required to obtain the results from the

, offsite analysis, the specific Sr-90 activity could not be included in the quarterly report for the period represented by the sample. Therefore, GPU Nuclear noted that the Sr-90 activity in liquid effluent would be verified by composite sampling. GPU Nuclear also committed to update the reports once the results of the offsite analysis were obtained.

During the period Sr-90 was not reported (i.e., 1984-1985), all unidentified beta activity detected by onsite methods was assumed to be Sr-90 for dose calculation purposes. The results of the offsite analysis demonstrated that the above assumption is conservative; the Sr-90 activity was consistently less than the unidentified beta activity. f 8606250379 860613 PDR R ADOCK 05000320 ],[ b pyg /{

GPU Nuclear Corporation is a subsidiary of the General Public Utilities Corporation

Dr. T. E. Murley June 13,1986 4410-86-L-0100 Since the assumption that unidentified beta activity is attributable to Sr-90 is conservative, GPU Nuclear has concluded that updating reports to reflect the results of the offsite analysis is unnecessary. As discussed with the TMICPD, future reports will conservatively assume all unidentified beta activity in liquid effluents as Sr-90 activity. This assumption will be verified by continuance of the quarterly composite sample analysis program.

Report updates will be submitted only in the unlikely event the Sr-90 activity in liquid effluents is greater than the unidentified beta activity.

Sincerely,

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. R. Standerf Vice President / Director, TMI-2 FRS/CJD/eml cc: Director - TMI-2 Cleanup Project Directorate, Dr. W. D. Travers i

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ATTACHMENT 4410-86-L-0100

[ Page 1 of 22 l;

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The attached pages listed below replace the existing pages in the corresponding Quarter Dose Assessment Report and/or Semi-Annual Radioactive Effluent Release Report.

Attached Page Number Corresponding Report 2 First Quarter 1984 Dose Assessment Report, 4410-84-L-0087, May 31, 1984 3, 4 Second Quarter 1984 Dose Assessment Report; Semi-Annual Radioactive l Effluent Release Report, 1 4410-84-L-0145, August 29, 1984 j 5, 6 Third Quarter 1984 Dose Assessment .

Report, 4410-84-L-0215, November 29, I 1984

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7, 8, 9, 10 Fourth Quarter 1984 Dose Assessment Report; Semi-Annual Radioactive l Effluent Release Report; 4410-85-L-0034, February 27, 1985 11, 12 First Quarter 1985 Dose Assessment Report, 4410-85-L-0120, May 30, 1985 13, 14, 15,16 Second Quarter 1985 Dose Assessment Report; Semi-Annual Radioactive Effluent Release Report; 4410-85-L-0175, August 29, 1985 17, 18 Third Quarter 1985 Dose Assessment {

Report, 4410-84-L-0238, November 27, i 1985 19, 20, 21, 22 Fourth Quarter 1985 Dose Assessment Report; Semi-Annual Radioactive Effluent Release Report; 1 4410-86-L-0038, February 28, 1986

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