ML19339B379

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Hazards Analysis Supporting Proposed Change 5 to License DPR-3
ML19339B379
Person / Time
Site: Yankee Rowe
Issue date: 05/25/1961
From: Case E
US ATOMIC ENERGY COMMISSION (AEC)
To:
Shared Package
ML19339B377 List:
References
NUDOCS 8011060830
Download: ML19339B379 (1)


Text

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HAZARDS A'IALYSIS BY THE RESEARCH AND POWER REACTOR SAFETY BRANCH DIVISION OF LICENSING AND REGULATION IN THE MATTER OF YANKEE ATOMIC ELECTRIC COMPANY PROPOSED CHANGE NO. 5 Yankee Atomic Electric Company has submitted Proposed Change No. 5, dated May 1,1961, which requests a modification in the technical specifications of License No. DPR-3.

This modification was requested pursuant to the provisions of paragraph 3. A. of the license and pro-vides for changing the first sentence of paragraph E.2.f.(3) of Appendix A to read as follows:

"As determined at the point of discharge from the primary vent stack and averaged over a period not exceeding one year, the concentrations of radioactive gaseous wastes dis-

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charged shall not be in excess of 1,000 times the limits specified in Appendix B, Table II, 10 CFR 20."

The dilution f actor for radioactive gaseous wastes is unchanged from that previously provided for in the technical specifications, except in regard to the noble fission gases. The limit stated for noble fission gases in the technical specifications was based on an earlier.

edition of Title 10 CFR Part 20 which has since been revised. The proposed change provides limitations in accordance with the latest revirion.

Based on a review of meteorological data which has been presented by Yankee, including the results of smoke tests performed at the site, we have concluded that an cssumed dilution factor of 1000 from the outlet of the 149 foot primary vent stack to the nearest unrestricted area is conservative for radiocctive noble fission ' gases. Although the previous limitations on the discharge of these gases was more restricti've, we believe that the proposed new limits will result in concentrations of radioactive noble gases at the site boundary well within those permitted by Commission regulations, and this modifi-cation does not present significant hazards considerations not described or implicit in the license application.

We have further concluded that there is reasonable assurance that the health and safety of the pqblic will not be endangered by this modification in the technicci specifications.

Edson G. Case, Chief Re_ search and Power Reactor Safety Branch Date L%Y : 519&t 8013gg.g g3 g

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