ML20079A077

Safety Evaluation Supporting Amend 183 to License DPR-65

ML20079A077
Person / Time
Site:	Millstone
Issue date:	12/20/1994
From:	Office of Nuclear Reactor Regulation
To:
Shared Package
ML20079A072	List: ML20079A069 ML20079A077
References
NUDOCS 9412300133
Download: ML20079A077 (2)

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UNITED STATES

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j NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20066 4001

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SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION i

j RELATED TO AMENDMENT NO.183 J

i TO FACILITY OPERATING LICENSE NO. DPR-65 1

NORTHEAST NUCLEAR ENERGY COMPANY j

THE CONNECTICUT LIGHT AND POWER COMPANY i

THE WESTERN MASSACHUSETTS ELECTRIC COMPANY i

MILLSTONE NUCLEAR POWER STATION. UNIT NO. 2 DOCKET NO. 50-336 I

1.0 INTRODUCTION

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By letter dated April 22, 1994, the Northeast Nuclear Energy Company (the 2

licensee) submitted a request for changes to the Millstone Nuclear Power Station, Unit No. 2 Technical Specifications (TS). The requested changes would change Table 3.3-9 of the TS by modifying the indicated measurement

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range for the neutron flux monitor on the remote shutdown panel. The proposed changes would also include some corrections of typographical errors.

l 2.0 EVALUATION l

Panel C-21 is the remote hot shutdown panel that is located outside of the control room.

In the event of a forced evacuation the operators are able to j

maintain the plant in hot shutdown condition with panel C-21, and bring it to cold shutdown with the local operation of certain equipment.

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l Currently, one of the variables that can be monitored at the C-21 panel is wide range logarithmic neutron flux. The two wide range logarithmic neutron flux monitors are dual scale meters which, when wired to do so, are capable of 1

displaying the neutron source power hvel in 10" to 10 counts per second j

(CPS) and the operating power level in 10 a% to 100% power.

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The licensee discovered, during a channel check, that panel C-21 did not meet i

the channel check criterion when placed in the CPS position. An investigation i

by the licensee, including a review of the original design, indicated that the panel C-21 was never designed or installed with the capability of receiving the CPS input. Therefore, it is the licensee's contention that the CPS scale 4

on the panel C-21 is unnecessary because the range of the percent power can provide the information necessary for safe shutdown; and the entry in TS Table 3.3-9 for the " Wide Range Logarithmic Neutron Flux Monitor" for the CPS scale can be removed. The staff agrees that, with the range of the operating neutron flux monitor, the additional CPS monitor is unnecessary.

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j 9412300133 941220 PDR ADOCK 05000336 p

PDR

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The licensee is requesting permission to remove the CPS measurement range j

requirements for panel C-21.

Based on the indication by the licensee that (1) the range of the percent power scale can provide the information necessary for i

safe plant shutdown and (2) the staff does not have a requirement for CPS j

input for panel C-21, the staff approves of the proposed change.

i With regards to the proposed corrections of typographical errors, the licensee has proposed corrections to the index which the staff has determined to be acceptable.

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3.0 STATE CONSULTATION

In accordance with the Commission's regulations, the Connecticut State l

official was notified of the proposed issuance of the amendment. The State official had no cosmients.

4.0 ENVIRONMENTAL CONSIDERATION

i The amendment changes a requirement with respect to installation or use of a 1

facility component located within the restricted area as defined in 10 CFR 3

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 l

exposure. The Commission has previously issued a proposed finding that the 4

amendment involves no significant hazards consideration, and there has been no j

public comment on such finding (59 FR 27059). 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

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environmental assessment need be prepared in connection with the issuance of j

the amendment, i

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5.0 CONCLUSION

i The Commission has concluded, based on the considerations discussed above, i

that:

(1) there is reasonable assurance that the health and safety of the I

public will not be endangered by operation in the proposed manner, (2) such j

activities will be conducted in compliance with the Commission's regulations, i

and (3) the issuance of the amendment will not be inimical to the common j

defense and security or to the health and safety of the public.

Principal Contributor: S. Brewer i

l Date:

December 20, 1994 i

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