ML17055B774

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Safety Evaluation Supporting Amend 84 to License DPR-63
ML17055B774
Person / Time
Site: Nine Mile Point Constellation icon.png
Issue date: 06/03/1986
From:
Office of Nuclear Reactor Regulation
To:
Shared Package
ML17055B773 List:
References
NUDOCS 8606120690
Download: ML17055B774 (4)


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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION SUPPORTING AMENDMENT NO.

TO FACILITY OPERATING LICENSE NO.

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

1 DOCKET NO. 50-220

1. 0 INTRODUCTION By letter dated December 31, 1985, Niagara Mohawk Power Corporation (the licensee) requested an amendment to Appendix A of Facility Operating License No.

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

1.

The proposed amendment would modify Technical Specification (TS) Section

3. 1. 1(f), by eliminating the reference to the "AEC'.", and by eliminating the reference to Section 6.9.2 reportability requirements pertaining to reactivity anomalies.

The proposed change does not present a new procedure or situation, but merely clarifies an existing one.

2. 0 EVALUATION If the difference between an observed and predicted control rod inventory exceeds the equivalent of 1 percent in reactivity, current TS require notification of the "AEC" within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> in accordance with Specification 6.9.2.

Reference to Section 6.9.2 is an inappropriate requirement and unnecessary due to:

(1) the AEC's reorganization, (2) the reportability requirements of Sections 50.72 and 50. 73 to 10 CFR Part 50, and (3) the intent of Section 6.9.2 being for fire protection related matters only.

Sections 50.72 and 50.73 to 10 CFR Part 50 require the licensee to notify the NRC as soon as practical and in all cases within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> if a TS requiring plant shutdown occur s.

This reportabi lity requirement is also found in TS Section 6.6. 1.

Therefore, it a plant shutdown were to occur due to the conditions covered under Section

3. l.1(f), it would be a plant shutdown required by the TS and thereby reportable in accordance with Section 6.6. 1.

Additionally, the referenced Section 6.9.2 outlines actions that must be taken with respect to Fire Protection Program Reports.

The referenced section is therefore not applicable to Section

3. 1. 1(f).

The proposed change does not present a

new procedure or situation, but merely clarifies an existing one, and therefore is acceptable.

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3. 0 ENVIRONMENTAL CONSIDERATION This amendment relates to changes in recordkeeping, reporting, or administrative procedures or requirements.

Accordingly, this amendment meets the eligibilitycriteria for categorical exclusion set forth in 10 CFR 51.22(c)(10).

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

4. 0 CONCLUSION The staff 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, and (2) such activities will be conducted in compliance with the Commission's regulations and the issuance of this amendment will not be inimical to the common defense and security nor to the health and safety of the public.

Principal Contributor:

J.

Kel ly Dated:

June 3, 1986

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