ML19254F220
| ML19254F220 | |
| Person / Time | |
|---|---|
| Site: | Fort Calhoun  |
| Issue date: | 10/30/1979 |
| From: | William Jones OMAHA PUBLIC POWER DISTRICT |
| To: | Reid R Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 7911070388 | |
| Download: ML19254F220 (2) | |
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.r1 Omaha Public Power District 1623 HARNEY OMAHA. NESRASKA 68102 TELEPHONE 536-4000 A7EA CODE 402 October 30, ' ' 9 Director of Nuclear Reactor Regulation ATTU:
Mr. Robert W. Reil Chief t
Operating Reactors Branch No. h~
U. S. Nuclear Regulatory Co==ission Washington, D. C.
20555
Reference:
Docket No. 50-285 Gentlemen:
The Omaha Public Power District received a letter from the Commission dated September 17, 1979, requesting that the District provide a method of demonstrating compliance with h0 CFR Part 190.
Accordingly, the following information is provided.
In June of 1976, the design of Radvaste Processing System for Fort Calhoun Station Unit No.1 was evaluated in accordance with the dose design objectives of Appendix I to 10 CFR Part 50.
It was determined that during normal reactor operation, including anticipated operational occurrences, the doses to individuals were well below the design objectives cet forth in Section II of Appendix I.
This evaluation, along with other related data, was submitted to the Cornission under a report entitled " Evaluation of Fort Cal-houn Station Unit No. 1 in Accordance With 10 CFR Part 50, Appendix I".
This report consisted of, among other things:
1.
Information to evaluate the =eans employed for keeping levels of radioactivity in effluents to unrestricted areas as lov as is reasonably achievakle, including all such information as is required by S : tion 50.3h(a), (b),
and (c) of 10 CFR Part 50 not alreac contained in the original application for a construction permit.
2.
Proposed Technical Specifications (also submitted to the Commission under an Application for Amendment of Operating License on March 21, 1978) developed for the purpose of keeping releases of radioactive materials to unrestricted areas during normal reactor operation, including expected operational occurrences, as low as is reasonably achievable.
Later, in March of 1979, the District submitted revised Tech-nical Specifications in accordance with the provisions of NUREG-
[
0k72 and in response to a letter from the Commission dated July 11, 90 1978.
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Director of nuclear Reactor Regulation Octocer 30, 1979 Page Two The above-referenced information, which demonstrates ccmpliance with 10 CFR Part 50, Appendix I, dose design objectives, also con-servatively demonstrates cc=pliance with h0 CFR Part 190.
This is because the Fort Calhoun Station is the only significant dose con-tributor to the population within the station's general vicinity.
Accordingly, we believe that based upon the results of Fort Cal-houn Station's evaluation in accordance with Appendix I to 10 CFR Part 50, current operating philoscphy in accordance with ALARA and existing applicable Technical Specf fications reasonable assurance is provided for complying with h0 CFR Part 190.
Sincerely, W. C. Jones Division Manager Production Operations WCJ/KJM/BJH:jnm ec: LeBoeuf, Lamb, Leiby & LhcRae 1333 New Hampshire Avenue, N. W.
Washington, D. C.
20036 19'2 127