ML20127J856

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Forwards Semiannual Radioactive Effluent Release Rept, Jul-Dec 1983 & Meteorology Data for Joint Frequencies for 1983.During Reporting Period Several Radioactive Gaseous & Liquid Effluent Monitoring Instruments Inoperable
ML20127J856
Person / Time
Site: McGuire, Mcguire  Duke Energy icon.png
Issue date: 02/29/1984
From: Tucker H
DUKE POWER CO.
To: James O'Reilly
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
Shared Package
ML20127J860 List:
References
NUDOCS 8505210606
Download: ML20127J856 (2)


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DmCE POWER Goxiusy P.O. DOX 33100 CHARLOTTE, N.C. 20242 m n. m n February 29, 1984 vocerenommar (704) o'73-4531 i

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Mr. James P. O'Reilly, Regional Administrator U. S. Nuclear Regulatory Commission Region II 101 Marietta Street, Suite 2900 Atlanta, Georgia 30303

Subject:

McGuire Nuclear Station Docket Nos. 50-369, 50-370 Semi-Annual Radioactive Effluent Release Report

Dear Mr. O'Reilly:

Pursuant to Technical Specification 6.9.1.7 attached is the Radioactive Effluent Release report for the period July - December 1983. Attachment 1 includes sum-maries of liquid and gaseous effluent releases and solid waste shipments.

Attach-ment 2 is the 1983 meteorology data for joint frequencies.

During this reporting period several radioactive gaseous and liquid effluent monitoring instruments were inoperable. Attachment 3 describes the instruments and why they were not restored to operable status within the time limits specified in Technical Specifications 3.3.3.8 and 3.3.3.9 Reporting of these events in the semi-annual Radioactive Effluent Release report is required by the Action statements of these technical specifications.

Please note that Revision 2 of McGuire's Offsite Dose Calculation Manual was submitted to ONRR on October 7, 1983. This was done in advance of the require-ment to submit such changes with the semi-annual Radioactive Effluent Release report. As a result, these changes are not included in this submittal.

As a result of radiation releases from McGuire Nuclear Station, no member of the public received an annual calculated dose exceeding those set forth in 40 CFR Part 190.

This determination was made considering that there are no other fuel cycle facilities nearby which would significantly increase the dose to any member of the public.

Very truly yours, l f-g Hal B. Tucker WuM:gib j Attachments cc: Mr. H. R. Denton, Director Mr. W. T. Orders Office of Nuclear Reactor Regulation NRC Resident Inspector U. S. Nuclear Regulatory Commission McGuire Nuc1 car Station Washington, D. C.

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