ML20214L571
| ML20214L571 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 03/20/1978 |
| From: | Switzer D NORTHEAST NUCLEAR ENERGY CO., NORTHEAST UTILITIES |
| To: | Reid R, Ziemann D Office of Nuclear Reactor Regulation |
| References | |
| TAC-7421, NUDOCS 8705300152 | |
| Download: ML20214L571 (6) | |
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March 20, 1978 Docket Nos. 50-245 50-336 f/
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Director of Nuclear Reactor Regulation A42 cc Attn:
Mr. D. L. Ziemann, Chief Operating Reactors Branch #2 Mr. R. Reid, Chief Operating Reactors Branch #4 U. S. Nuclear Regulatory Commission Washington, D. C.
20555 Gentlemen:
Millstone Nuclear Power Station, Unit Nos.1 and 2 Proposed Revisions to Environmental Technical Specifications Pursuant to Section 5.6.3 of the Millstone Unit No.1 (License No. DPR-21) and Unit No. 2 (License No. DPR-65) Environmental Technical Specifications (ETS),
Northeast Nuclear Energy Company (NNECO) hereby proposes to incorporate the following proposed revisions into the ETS:
(1) In Table 2.4-1, delete Item B, Primary con 1nnt Sampling and Analysis for I-131 and I-133, as shown on at t ached Page 2.4-15.
(2) Delete Note 4, which is no longer relevant with the deletion of Item B as shown on attached revised Page 2,4-16.
O (Efe thse hanges are proposed to eliminate unnecessary redundancy between the 4
Technical Specifications and the ETS.. Primary coolant sampling and analy-is, r Iodines is covered by the Millstone Unit No.1 Technical Specifications in4ectitons-36.Cgnfj4.6.CandintheMillstoneUnitNo.2TechnicalSpecifica-
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s in Sections 3.5.8 and 4.4.8.
Primary coolant sampling frequencies are more
$strictiveinSafetyTechnicalSpecificationsthaninETS;therefore,noproce-Q ural changes or adverse environmental effects will result from issuance of the above proposed changes.
In this instance, the benefit / cost analysis is not applicable; the change merely '
eliminates redundant specifications which have no effect on plant procedures or environmental effects.
i 8705300152 780320 PDR ADOCK 05000245 p
l e 6' The Millstone Environmental Review Board has reviewed and approved the above requested changes.
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Very truly yours, NORTHEAST NUCLEAR ENERGY COMPANY i
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W D. C. Switzer fj President Attachment i
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STATE OF CONNECTICUT ss.
Berlin COUNTY OF HARTFORD Then personally appeared before me D. C. Switzer, who being duly sworn.
-did state that he is President of Northeast Nuclear Energy Company, a Licensee herein, that he is authorized to execute and file the foregoing information in the name and on behalf of the Licensees herein and that the statements contained in said information are true and correct to the best of his knowledae and belief.
Notary Public i
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August' 19, 1976 Table 2.4-1 (Continued)
(1)
A composite sample is one in which the quantity of liquid sampled is proportional to the quantity of liquid vaste discharged.
(2)
For certain mixtures of gagna emitters, it may not be possible to measure radionuclides in concentrations near their sensitivity limits when other nuclides are present in the sample in much greater concentrations. Under these circumstances, it will be more appropriate to calculate the concentrations of such radionuclides using measured ratios with those radionuclides which are routinely identified and measured.
(3)
The detectability limits for activity analysis are based on the technical feasibility and on the potential significance in the environment of the quantities released. For some nuclides, lower detection limits may be readily achievable and when nuclides are measured below the stated limits, they shall also be reported.
(5)
To be representative of the average quantities and concentrations of radio-active materials in liquid effluents, samples should be collected in pro-portion to the rate of flow of the effluent stream. Prior to analyses, all sampler taken for the composite should be throughly mixed in order for the composite sample to be representative of the average effluent release.
(6)
These analyses are required when the steam generator gross activity (sampled and analyzed 3 times per week as per the Safety Technical 3
Specifications Table 4.7-2) exceeds 1 X 10 7 p Ci/ml.
2.4-16 Amendment No. 30 to DPR-21 Amendment No. 14 to DPR-65
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