ML17309A340

Forwards Effluent & Waste Disposal Semiannual Rept,Jan-June 1984 & Corrected Pages to Effluent & Waste Disposal Semiannual Rept,Jul-Dec 1983.

ML17309A340
Person / Time
Site:	Ginna
Issue date:	09/05/1984
From:	Kober R ROCHESTER GAS & ELECTRIC CORP.
To:	Murley T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
Shared Package
ML17309A341	List: ML17309A340 ML17309A342 ML17309A343
References
NUDOCS 8409260133
Download: ML17309A340 (4)

Text

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ROCHESTER GAS AND ELECTRIC CORPORATION o 89 EAST AVENUE, ROCHESTER, N.Y. 14649-0001 ROGER IN. KO8ER VICC PRESIDENT TELEPHONE CIECTRIC & STCAM PRODUCTION AREA CODE 7IIS 546.2700 September 5, 1984 Dr. Thomas E. Murley, Regional Administrator U. S. Nuclear Regulatory Commission Region I 631 Park Avenue King of Prussia, Pennsylvania 19406

Subject:

Docket No. 50-244 Semiannual Radioactive Effluent Release Report January June, 1984

Dear Dr. Murley:

The enclosed information is being forwarded to you in accordance with the requirements of Technical Specification Sections 6.9.1.4 and

4. 12.

Several typographical errors in the sign of the exponent were included in the gaseous effluent portion of the July December, 1983 Semiannual Radioactive Effluent Release Report. Corrected pages are included with this report.

A listing is included of those batch releases for which the LLD of SE-07 was not obtained with a brief explanation as required by Table 4.12-1 subnote (a) of the Technical Specification. The LLD value is determined by counting one liter of sample for one hour. The normal LLD values for samples having little or no activity are <3E-07.

y truly yours, ger W. Kober Enc.

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September 5, 1984 Dr. Thomas E. Murley, Regional Administrator U. S. Nuclear Regulatory Commission Region 1 631 Park Avenue King of Prussia, Pennsylvania 19406

Subject:

Docket No. 50-244

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', Semiannual Radioactive Effluent Release Report'January June, 1984

Dear Dr. Murley:

The enclosed information is being forwarded to you in accordance with the requirements of Technical Specification Sections 6.9.1.4 and

4. 12.

Several typographical errors in the sign of the exponent were included in the gaseous effluent portion of the july December, 1983 Semiannual Radioactive Effluent Release Report. Corrected pages are included'ith this report.

A listing is included of those batch releases for which the LLD of 5E-07 was not obtained with a brief explanation as required by Table 4.12-1 subnote (a) of the Technical Specification. The LLD value is determined by counting one liter of sample for one hour. The normal LLD values for samples having little or no activity are <3E-07.

y truly yours, ger W. Kober Enc.

84092b0133 840905 PDR ADOCK 05000244 R PDR

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September 5, 1984 Dr. Thomas E. Murley, Regional Administrator U. S. Nuclear Regulatory Commission Region I 631 Park Avenue King of Prussia, Pennsylvania 19406

Subject:

Docket No. 50-244 Semiannual Radioactive Effluent Release Report January june, 1984

Dear Dr. Murley:

The enclosed information is being forwarded to you in accordance with the requirements of Technical Specification Sections 6.9.1.4 and

4. 12.

Several typographical errors in the sign of the exponent were included in the gaseous effluent portion of the July December, 1983 Semiannual Radioactive Effluent Release Report. Corrected pages are included: with this report.

A listing is included of those batch releases for which the LLD of 5E-07 was not obtained with a brief explanation as required by Table 4.12-1 subnote (a) of the Technical Specification. The LLD value is determined by counting one liter of sample for one hour. The normal LLD values for samples having little or no activity are <3E-07.

y truly yours, ger W. Kober Enc.

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84092b0133 840905 PDR ADOCK OS000244 R PDR