ML19323G341

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Application to Amend License DPR-65 by Incorporating Revisions to Tech Specs for Millstone 2 in Response to NRC 800410 Request.Proposed Changes Are Necessary for Safe Operation of Facility.Millstone 2 Is Only Unit W/Tech Specs
ML19323G341
Person / Time
Site: Haddam Neck, Millstone  File:Connecticut Yankee Atomic Power Co icon.png
Issue date: 05/21/1980
From: Counsil W
CONNECTICUT YANKEE ATOMIC POWER CO., NORTHEAST NUCLEAR ENERGY CO.
To:
Shared Package
ML19323G342 List:
References
TAC-42625, NUDOCS 8006020203
Download: ML19323G341 (3)


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: 4 "_.l T C r May 21, 1980 Docket Nos. 50-213 50-245 50-336 A00974 Darrell G. Eis enhut, Acting Director Division of Operating Reactors Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D.

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Reference:

(1)

D. G. Eisenhut letter to All Power Reactor Licensees dated April 10, 1980.

Gentlemen:

daddam Neck Plant Millstone N" clear Power Station, Unit Nos. 1 and 2 Proposed Revisions to Technical Specifications In Reference (1), Connecticut Yankee Atomic Power Company (CYAPCO) and Northeast Huclear Energy Company (NNECO) were requested to submit proposed changes to Technical Specifications to incorporate the requirements of Enclosure 1 into the existing Technical Specifications for each of the three operating units.

It is noted that CYAPCO and NNECO do not concur that the attached proposed changes are necessary to ensure continued safe operation of the facilities.

Nonetheless, pursuant to 10CFR50.90, NNECO hereby proposas to amend its operating license, DPR-65, by incorporating the revisions identified in into the Millstone Unit No. 2 Technical Specifications.

As Hillstone Unit No. 2 is the only one of the three units with Standard Technical Specifications, only that Unit is proposing revisions which closely parallel the Reference (1) request. One substantive change is the time allocated to achieve the hot standby condition in the event of circumstances in excess of those addressed in the Technical Specifications. The proposed interval is eight hours, rather than the NRC-proposed interval of one hour.

This change is more conservative in that sufficient time is allocated to conduct a controlled shutdown and/or cooldown in the event su.5 action is required.

Allocation of only one hour would require a plant trip which yields a greater probability of resulting in off-normal operating conditions. This circumstance would be most undesirable in that less than a full complement of safety systems would be operable for circumstances in which the generic action scatements must be invoked.

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. Regarding the Haddam Neck Plant and Millstone Unit No.1, CYAPCO and NNECO have reviewed the Reference (1) request and have determined that the existing formats of the Technical Specifications do not lend themselves to adoption of the Staff requests. The major complication involves the review of each individual specification and possible incorporation of a statement indicating that the generic action statements of Section 3.0 are not applicable.

This process is necessary to ensure that the Technical Specifications do not require a plant shutdown for conditions where such action is inappropriate, unwarranted, or independent of the failure involved. The Commission's existing Standard Technical Specifications recognize the necessity of this effort. The magnitude of the task is such that it is not appropriate to undertake this review process at this time, as the Reference (1) request does not constitute a matter of safety significance.

It is noted that the Haddam Neck Plant is currently in the process of converting to standard Technical Specifications, and it is envisioned that the intent of Rererence (1) will be incorporated into that effort.

It is acknowledged that the expanded definition of the term OPERABLE - OPERABILITY could be incorporated at this time, but this change would not alter the current intent and does not warrant a request for a license amendment.

NNECO has reviewed the attached changes pursuant to the requirements of 10CFR50.59 and has determined that they do not constitute unreviewed safety questions. The proposed changes serve to clarify the intent of existing Specification requirements.

The Millstone Unit No. 2 Nuclear Review Board has reviewed and approved the attached proposed ch.iges and concurred in the above determination.

NNECO has reviewed ie proposed license amendment pursuant to the require-ments of 10CFR170 and has determined that no fee is applicable in this instance. The basis for this determination is that the proposed amendments result from a written Commission request for the applications, they serve to clarify existing Technical Specifications, they have only minor safety significance, and would be issued for the convenience of the Commission.

We trust you find the attached proposal responsive to the Reference (1) request.

Very truly yours, CONNECTICUT YANKEE ATOMIC POWER COMPANY

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NORTHEAST NUCLEAR ENERGY COMPANY hs W. G. Counsil Vice President Attachment-1 1

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Then personally appeared before me W. G. Counsil, who being duly sworn, did state that he is Vice President of Nertheast 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 knowledge and belief.

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Notary Public

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My Commissioil Expires March 31.193i.

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