ML19260C740

Forwards Amend to License DPR-65,incorporating Revised Pages 3-44 & 3-45 to Tech Specs Re Fire Detection Instruments

ML19260C740
Person / Time
Site:	Millstone
Issue date:	01/03/1980
From:	Counsil W NORTHEAST UTILITIES
To:
Shared Package
ML19260C741	List: ML19260C740 ML19260C743
References
TAC-7544, NUDOCS 8001080555
Download: ML19260C740 (2)

Text

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'2 *:.'":::"~~ anwsen L L - :;:::M;; "".:.lll:::l January 3, 1980 Docket No. 50-336 Director of Nuclear Reactor Regulation Attn: Mr. R. Reid , Chief Operating Reactors Branch #4 U. S. Nuclear Regulatory Commission Washington, D. C. 20555 Ref erenc e: (1) R. Reid letter to W. G. Counsil dated September 19, 1978, transmitting Amendment No. 43 and Supporting Safety Evaluation to Facility Operating License No. DPR-65 for Millstone Nuclear Power Station, Unit No. 2.

Gentlemen:

Millstone Nuclear Power Station, Unit No. 2 Proposed Revisions to Technical Soecifications Pursuant to 10CFR50.90, Northeast Nuclear Energy Company (NNECO) hereby proposes to amend its operating license, DPR-65, by incorporating the changes identified in Attachment 1 into the Millstone Unit No. 2 Technical Specifications.

The change proposes to revise the location, type, and number of fire detection instruments as requested in the Reference (1) Safety Evaluation. The proposed revision, which involves a change from heat detectors to smoke detectors, and requires fire surveillance in additional areas, will improve fire detection capability, thereby enhancing the fire protection program at Millstone Unit No. 2. The revised Table 3.3-10 is included as Attachment 1. Proposed changes in the existing Technical Specifications have been delineated by change bars in the right-hand margin.

The above proposed changes have been reviewed pursuant to 10CFR50.59 and have not been found to constitute an unreviewed safety question.

The Millstone Unit No. 2 Nuclear Review Board has reviewed and approved the above-proposed changes and concurred in the above determination.

NNECO has reviewed the proposed license amendment pursuant to the requirements of 10CFR170 and has determined that no fee is applicable in this instance.

The basis f ar this determination is that the proposed change is a direct result of tne NRC Staff review associated with Amendment No. 54 to Facility Operating License No. DPR-65 relating to fire protection modifications.

As stated in Reference (1), appropriate fees were submitted at that time and additional fees are not appropriate to execute requirements documented in the Saf ety Evaluation.

1704 322 so o m eo STS p

We trust you find the above information responsive to the Reference (1) require-ments.

Very truly yours, NORTHEAST NUCLEAR ENERGY COMPANY

/1. CTA/W W. G. Counsil Vice President Attachment 1704 323