ML17056C160

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Safety Evaluation Supporting Amend 134 to License DPR-63
ML17056C160
Person / Time
Site: Nine Mile Point 
Issue date: 12/03/1992
From:
Office of Nuclear Reactor Regulation
To:
Shared Package
ML17056C159 List:
References
NUDOCS 9212150128
Download: ML17056C160 (6)


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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 2D565 ENCLOSURE 2

SAFETY EVALU TION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. >34 TO FACILITY OPERATING LICENSE NO.

DPR-63 NIAGARA MOHAWK POWER CORPORATION NINE MI E POINT NUCLEAR STATION UNIT NO.

1 DOCKET NO. 50-220

1. 0 INTRODUCTION By letter dated November 20,
1992, as superseded February 7,
1992, Niagara Mohawk Power Corporation (the licensee) submitted a request for changes to the Nine Mile Point Nuclear Station Unit No.

1, Technical Specifications (TS).

The requested changes would revise TS Tables 3.2.7 and 3.2.7. 1; TS 3.3.3, 4.3.3, and 3.3.4; and associated Bases to update these TS to conform them to the requirements of 10 CFR Part 50, Appendix J, and the NRC safety evaluation, dated May 6, 1988.

The requested 'changes would also add a requirement to TS Table 3.3.4 to require closure of the drywell and suppression chamber vent and purge isolation valves on a high radiation signal from the stack radiation monitor.

Closure of these vent and purge isolation valves on a high radiation signal from the stack radiation monitor is a requirement of Iteq. II.E.4.2 of NUREG-0737 and this is the only portion of the February 7,

1992, request being approved by this safety evaluation and license amendment.

The licensee's February 7,

1992, letter superseded a letter from the licensee dated November 28, 1990.

2. 0 EVALUATION The proposed change would add high radiation at the stack radiation monitor as an initiation signal which would cause automatic closure of the drywell and suppression chamber vent and purge isolation valves.

The proposed change would add diversity to the parameters sensed for the initiation of containment isolation and.would therefore be in accordance with the requirements of Section 6.2.4 of. the Standard Review Plan.

The additional of high radiation as initiating,- signal for containment isolation is also in accordance with the requirements:

of.- Item II.E.4.2 of NUREG-0737.

Therefore, the NRC staff finds this proposed'change acceptable.

3.0 STATE CONSULTATION

In accordance with the Commission's regulations, the New York State official was notified of the proposed issuance of the amendment.

The State official had no comments.

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4. 0 ENVIRO 0

S DERATION The amendment changes a requirement with respect to installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20.

The NRC staff has determined that the amendment involves no significant increase in the amounts, and no significant change in the types, of any effluents that may be released offsite, and that there is no significant increase in individual or cumulative occupational radiation exposure.

The Commission has previously issued a proposed finding that the amendment involves no significant hazards consideration, and there has been no public comment on such finding (57 FR 4868 and 57 FR 11111).

Accordingly, the amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9).

Pursuant to 10 CFR 51.22(b) no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendment.

5.5

~NLU The Commission has concluded, based on the considerations discussed

above, that:

(1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed

manner, (2) such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public.

Principal Contributors:

D.

Shum D. Brinkman Date:

December 3, 1992

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December 3,

1992 Docket No. 50-220 Hr. B. Ralph Sylvia Executive Vice President, Nuclear Niagara Mohawk Power Corporation 301 Plainfield Road

Syracuse, New York 13212

Dear Hr. Sylvia:

SUBJECT:

ISSUANCE OF AMENDMENT FOR NINE NILE POINT NUCLEAR STATION UNIT NO.

1 (TAC NO. H79135)

The Commission has issued the enclosed Amendment No. 134 to Facility Operating License No.

DPR-63 for the Nine Mile Point Nuclear Station Unit No.

1 (NMP-l).

The amendment consists of changes to the Technical Specifications in partial response to your application transmitted by letter dated November 20,

1990, as superseded February 7,

1992.

Those portions of your February 7,

1992, application not contained in this amendment will be the subject of future correspondence.

The amendment revises Table 3.3.4 of Technical Specification 3,3.4 to require closure of the drywell and suppression chamber vent and purge isolation valves on a high radiation signal from the stack radiation monitor.

This change is consistent with the requirements of Item II.E.4.2 of NUREG-0737.

A copy of the related Safety Evaluation is enclosed.

A Notice of Issuance will be included in the Commission's next regular biweekly Federal Re<eister notice.

Sincerely, Original signed by:

Donald S.

Brinkman, Senior Project Manager Project Directorate I-1 Division of Reactor Projects I/II Office of Nuclear Reactor Regulation

Enclosures:

l.

Amendment No. 134 to DPR-63 2.

Safety Evaluation cc w/enclosures:

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