ML19254F247

Supplements 790315 License Change Application 50 Incorporating 10CFR50,App I,Radiological Effluent Tech Specs.Includes Spec Implementing 40CFR50.Util to Implement 10CFR190 Until Application 50 Approved & Issued as Amend

ML19254F247
Person / Time
Site:	Trojan File:Portland General Electric icon.png
Issue date:	10/31/1979
From:	Goodwin C PORTLAND GENERAL ELECTRIC CO.
To:	Gammill W Office of Nuclear Reactor Regulation
References
TAC-07721, TAC-7721, NUDOCS 7911070423
Download: ML19254F247 (3)

Text

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pC October 31, 1979 Trojan Nuclear Plant Docket 50-344 License NPF-1 Director of Nuclear Reactor Regulation ATTN:

Mr. W. P. Cammill, Acting Assistant Director for Operating Reactor Projects Division of Operating Reactors U.S. Nuclear Regulatory Commission Washington, D. C. 20555

Dear Sir:

On March 15, 1979, PGE submitted License Change Application (LCA) 50 incorporating 10 CFR 50, Appendix I, as presented in NIJREG-0472, Radio-logical Environmental Technical Specifications (RETS).

LCA 50 is currently being reviewed by the NRC Staff.

Included in LCA 50 is the specification implementing the EPA Uranium Fuel Cycle Standard, 40 CFR 190.

In a letter dated September 17, 1979, NRC requested PGE to commit to implementation of the EPA Standard by November 1, 1979, which will be prior to implementation of LCA 50.

The EPA Standard limits the dose to any real person from all uranium fuel cycle sources to less then 25 mreu/yr to the whole body or any organ (except thyroid) and to less than 75 mrem /yr to the thryoid.

In response to the NRC request, PGE will implement 40 CFR 190 using the same methodology as in the RETS until such time as LCA 50 is approved and issued as an amendment to the Trojan Operating License. The RETS methodology requires a special dose assessment should the design dose objectives be exceeded by a factor of two.

This special dose assessment will be performed in accordance with Regulatory Guide 1.109 (Rev. 1, 10/77) should any of the current Trojan Technical Specification design dose objectives shown in the attached table be exceeded by a factor of two.

This special dose assessment will be included in a Special Report, as required by RETS Technical Specification 3.11.4 and will be submitted to the NRC within 30 days following the submittal of the Semiannual Effluent Release Report required by the current Trojan Technical Specifi-caticn 5.5.1. b.

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~ ; :. ' ". ' 1 Mr. W. P. Gammill October 31, 1979 Page two We believe that the above method will adequately fulfill the requirements of 40 CFR 190.

Sincerely,h l'

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C. Goodwin, Jr.

Assistant Vice President Thermal Plant Operation and Maintenance CG/MQH/4kk3A13 Attachment c:

Mr. Lynn Frank, Director State of Oregon Department of Energy Mr. A. Schwencer, Chief Operating Reactors Branch #1 Division of Operating Reactors U.S. Nuclear Regulatory Commission

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a ATTACIUd.EN_T 2.4.1 Objective To ensure that the releases of radioactive material above back-ground to unrestricted areas be as low as are reasonably achiev-able, the following design objectives apply:

For liquid wastes:

a.

The annual dose above background to the total body or any organ of an individual from all reactors at a site should not exceed 5 mrem in an unrestricted area.

For gaseous wastes:

c.

The annual total quantity of noble gases above back-ground discharged from the site should result in an air dose due to gamma radiation of less than 10 mrad, and an air dose due to beta radiation of ' ss than 20 mrad, at any location near ground level which could be occupied by individuals at or beyond the boundary of the site.

d.

The annual total quantity, above background, of all radioiodines and radioactive material in particulate forms with half-lives greater than 8 days, from all reactors at a site should not result in an annual dose to any organ of an individual in an unrestricted area from all pathways of exposure in excess of 5 mrem.

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