ML19317H000
| ML19317H000 | |
| Person / Time | |
|---|---|
| Site: | Crystal River, Arkansas Nuclear  |
| Issue date: | 04/11/1978 |
| From: | Goller K Office of Nuclear Reactor Regulation |
| To: | ARKANSAS POWER & LIGHT CO., FLORIDA POWER CORP. |
| Shared Package | |
| ML19317H001 | List: |
| References | |
| NUDOCS 8004020659 | |
| Download: ML19317H000 (1) | |
Text
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g' t, UNITED STATES NUCLEAR REGULATORY COMMISSION i
WASHINGTON. D. C. 20555
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April 11, 1978
. Docket No.: 50-302 To All Pcwer Reactor Licensees Gentlemen:
Enclosed for your information and possible future use is the current NRC guidance on radiological environmental monitoring for nuclear power plants.
10 CFR Parts 20 and 50 require that radiological environmental monitoring programs be established to provide data on measurable levels of radiation and radioactive materials in the site environs.
In addition, Appendix I to 10 CFR Part 50 requires that the relationship between quantities of radioactive material released in effluents during normal operation, includ-ing anticipated operational occurrences, and resultant radiation doses to individual.s from principal pathways of exposure be evaluated.
Regulatory Guide 4.8, Environmental Technical Specifications for Nuclear Power Plants, was issued for coment in December 1975. The enclosed tech-nical position on the radiological portion of environmental monitoring was formulated by an NRC working group whict considered the comments received on Regulatory Guide 4.8.
This positicn sets forth guidance for developing an acceptable minimum radiological monitoring program to meet the regula-tory requirements of 10 ';FR Parts 20 and 50. Local site characteristics need to be examined to determine if pathways not covered by this guide may significantly contribute to an individual's dose and should,be included in the sampling program. The acceptability of changes to radiological environ-mental monitoring programs at operating reactors will be evaluated based on this guidance as well as on a review of past operating data.
We are devaloping technical specifications which incorporate the Appendix I gdidance set forth in the enclosed position. These specifications will be implemented on all oper.ing reactors in the future. This position is be-ing provided to you at the present time for information only and no action is required on your part. More specific guidance on technical specifications relating to the implementation of Appendix I to 10 CFR 50 will be provided to you in the future.
Karl R. Goller, Assistant Director for Operating Reactors Division of Operating Reactors Office of Nuclear Reactor Regulation 8004020[6
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