ML17249A245

Responds to Request for Committment to Conform to EPA U Fuel Cycle Std by 791101.Continued Application of Plant Operational & Surveillance Requirements Will Assure Compliance

ML17249A245
Person / Time
Site:	Ginna
Issue date:	11/01/1979
From:	White L ROCHESTER GAS & ELECTRIC CORP.
To:	Ziemann D Office of Nuclear Reactor Regulation
References
NUDOCS 7911070428
Download: ML17249A245 (4)

Text

7 REGULATORY, INFORMATION DISTRIBUTION SYSTEM (RIDS)

ACCESSION NBR:7911070428 DOC DATE: 79/11/01 NOTA

'ZED:

NO DOCKET FAG?Li50-240 Robert-Emmet Ginna Nuclear Planti Unit" ii Rochester G

05000204 AOTH BYNAME AUTHOR AFFILIATION WHITEELRDB Rochester-Gas 'L Electric Corp, RECIP,"NAME REC'IPIE'NT AFFILIATION 2 IEAANNE D ~ L, Operating Reactors Branch 2

SUBJECT:

Responds to, request fo,r committment to conform to EPA U fuel.

cycle std by 791101,Continued application of plant opei ati onal 8 surveillance requirements will assure compliance'ISTRIBUTION CODE:

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ROCHESTER GAS AND ELECTRIC CORPORATION o

89 EAST AVENUE, ROCHESTER, N.Y. 14649 LEON D. WHITE. JR.

VICE PRESIDENT TELEPHONE AREA CODE Tla 546-2700 November 1, 1979 Division of Operating Reactors Attention:

Mr. Dennis L. Ziemann, Chief Operating Reactors Branch No.

2 U.

S. Nuclear Regulatory Commission Washington, D.C.

20555

Subject:

Compliance with EPA Uranium Fuel Cycle Standard (40 CFR Part 190)

R. E. Ginna Nuclear Power Plant

~

Docket No. 50-244

Dear Mr. Ziemann:

This in response to a letter from Mr..William P. Gammill dated September 17 which requests a commitment. to conform to the EPA Uranium Fuel Cycle Standard, 40 CFR Part 190 by November 1, 1979.

Although the Radiological Effluent Technical Specifications for Ginna Station have not been issued by the NRC, it is our view that the continued application of current plant operational and sur-veillance requirements will assure compliance with 40 CFR Part. 190.

Specifically, in the June 4, 1976 submittal to the Commission entitled "Dose Calculations to Conform with Appendix I Require-ments - Ginna Station", substantial margin was demonstrated between the maximum exposures calculated from routine effluent releases and the 10 CFR Part 50 Appendix I design objectives.

Furthermore, con-siderable margin exists between the dose levels associated with the Appendix I design objectives and the 40 CFR Part 190 standards.

Recognizing that significantly higher annual release quantities of radioactive effluent would have to occur prior to exceeding the EPA radiation standard, we will continue our routine review of effluent and environmental sampling data to confirm that no significant or unusual release levels are occurring.

Very truly yours, Leon D. Whi

, Jr.

LDW:np

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