ML20100C211

Comments on Des (NUREG-1074).Dose-design Objectives of 10CFR50 Concerning Operating Stds of EPA 40CFR190 & Radwaste Mgt Sys Provide Adequate Assurance That Radiation Doses Meet Protection Stds

ML20100C211
Person / Time
Site:	Millstone
Issue date:	09/14/1984
From:	Rosenstein M FOOD & DRUG ADMINISTRATION
To:	Youngblood B Office of Nuclear Reactor Regulation
References
RTR-NUREG-1074 NUDOCS 8412050346
Download: ML20100C211 (3)

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. DEPARTMENT OF HEALTH at HUMAN SERVICES Public H;alth Servica

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Food and Drug AdrNnistra' ion

.gg Rockville MD 20857 Mr. B. J.1Youngblood Licensing Branch No. 1 Division of' Licensing.

U.S. Nuclear Regulatory Conmission Washington, D.C.

20555

Dear Mr. Youngblood:

The Center for Devices and Radiological Health staff hcs reviewed the Draft Envirormental Statement'(DES) related to the operation of Millstone Nuclear Pbwer Station, Unit No. 3, NUREG-1064, dated July 1984.

It is recognized,;in reviewing the DES, that this is an administrative action'for issuance of an operating license. We note that as of June 25, 1984, the construction of Unit 3 was about.86.5 percent complete. Our

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staff has evaluated the public health and safety impacts associated with the pw+csed operation of the plant and have the following consents to 1

offer:

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1. It appears that the dose-design objectives of 10 CFR 50, Appendix I, the operating standards of EPA's 40 CFR 190, and -the-facility's radio-active waste management system provide adequate assurance that the potential individual and population radiation doses meet current radia-ation protection standards.

2. The environmental pathways identified in Section 5.9 and Figure 5.4, page 5-77, cover all possible emission pathways that could inpact on the population in the environs of the facility. The dose cmputational methodology and models (Appendix B and Appendix D) used in the estimation of radiation doses to individuals near the plant and to populations within 80 km of the plant have provided the means to make reasonable estimates of

. the doses resulting from normal operations and accident situations at the facility. Results of these calculations are shown in Appendix D, Tables D-6a, D-6b, D-7 and D-8 and confirm that the calculated doses meet the ~

design objectives.

3. The discussion in Section 5.9.4 on environmental impact of postulated accidents is considered to be an adequate assessment of the radiological exposure pathways and the dose and health impacts of atmospheric releases.

We are pleased to. note that Section 5.9.4.4 (3) on emergency preparedness has been nodified t6 incorporate certain cmmants we have submitted on this section previously. The lessons learned from the accident; at Three Mile Island :-- Unit 2'on March 28, 1979, identified the need for an emergency operations facility (EOF) at operating nuclear plants. Section 5.13 indi-cates that such a facility has been established and will function to meet the operational emergency needs of Unit 3, as well as Units 1 and 2.,

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!Mr. B.LJ.<Youngblood - Page 2

4. The radiological environmental nonitoring program outlined in Sections 5.9.2, 5.9.3.3, and 5.9.3.4,' and stenarized in Tables 5.11 and 5.12 pro-vides adequate sampling and analysis of' environmental media for specific radionuclides to ;(1) verify the effectiveness-of in-plant systems used to

' control releases of rM ioactive material, (2) ensure that unanticipated buildups of radioactivity will not occur-in the environment, and (3) verify that such emissi6ns meet the' applicable radiation protection standards.- As indicated in Section_5.9.3.4.2,-.the operational radiological monitoring

. program is conducted as a continuance of the pre-operational program with periodic adjustmerit _of sampling frequencies'in critical exposure pathways based on experience obtained from nonitoring Units.1 and 2.

Since radio-logical monitoring is an inportant program in protecting public health, we would like to be informed about the specifics of. the final operational -

. monitoring program that will be incorporated into the operating license Radiological ilechnical Specifications.

5. Section 5.10 and Appendix C contain a description of the envirorsnental impact maaaaanant of the uranium fuel cycle related to the Millstone 3 facility. The environnental effects presented are a reasonable assessnent of the population dose cm mitments and health effects associated with releases of radon-222 from the uranium fuel cycle.

Thank you for the opport' unity to consnent on this draft environmental statement.

Sincerely yours,.

L4' a:

Marvin Rosenstein, Ph.D.

Director Office of Health Physics Center for Devices and Radiological Health.

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