ML19210B046
| ML19210B046 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 04/11/1978 |
| From: | Galler K NRC OFFICE OF STANDARDS DEVELOPMENT |
| To: | METROPOLITAN EDISON CO. |
| Shared Package | |
| ML19210B047 | List: |
| References | |
| RTR-REGGD-04.008, RTR-REGGD-4.008 NUDOCS 7911010778 | |
| Download: ML19210B046 (1) | |
Text
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W.\\SHINGTON. D. C. 20555 d<
s., m April 11, 1978
, Docket No.: 50-289 To All Power 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 5'O 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 individuals from principal pathways of exposure be evaluated.
Regulatory Guide 4.8, Environmental Technical Specifications for Nuclear Power Plants, was issued for coninent in December 1975. The enclosed tech-nical position on the radiological portion of environmental monitoring was formulated by an NRC working group which considered the connents received on Regulatory Guide 4.8.
This position sets forth guidance for developing an acceptable minimum radiological monitoring program to meet the regula-tory requirements of 10 CFR 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 developing technical specifications which incorporate the Appendix I guidance set forth in the enclosed position.
These specifications will be implemented on all operating 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 relat1'g 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 1566?321
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191101o 7 '78 p
March 19h8 Branch Technical Position
Background
Regulatory Guide 4.8, Environmental Technical Specifications for Nuclear Power Plants, issued for comment in December 1975, is being revised based on comments received. The Radiological Assessment Branch has developed the following Branch Position on the radiological portion of the environ-mental monitoring program.
The position was formulated by an NRC working group which considered comments received after the issuance of the Regulatory Guide 4.8.
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 radio-active material released in effluents during normal operation, including anticipated operational occurrences, and resultant radiation doses to in-dividuals from principals pathways of exposure be evaluated.
These pro-grams should be conducted to verify the effectiveness of in-plant measures used for controlling the release of radioactive materials.
Surveillance should be established to identify changes in the use of unrestricted areas (e.g., for agricultural purposes) to provide a basis for modifications in the monitoring programs for evaluating doses to individuals from principal pathways of exposure.
NRC Regulatory Guide 4.1, Rev.1, " Programs for Monitoring Radioactivity in the Environs of Nuclear Power Plants," provides an acceptable basis for the design of programs to monitor levels of radia-tion and radioactivity in the station environs.
This position sets forth an example of an acceptable minimum radiological monitoring program.
Local site characteristics must 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.
1566 522