ML20154N240

Safety Evaluation Supporting Amend 18 to License NPF-49

ML20154N240
Person / Time
Site:	Millstone
Issue date:	05/19/1988
From:	Office of Nuclear Reactor Regulation
To:
Shared Package
ML20154N197	List: ML20154N193 ML20154N227 ML20154N240
References
NUDOCS 8806020238
Download: ML20154N240 (2)

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SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AWENCPENT NO g ,

TO FACILITY OPERATING LICENSE NO. NPF-49 NORTHEAST NUCLEAR ENERGY COMPAN,Yn _TE AL.

MILLSTONENUCLEARPOWERSTATIONfJNITNO._3 _

DOCKET NO. 50-423 INTRODUCTION i

By letter dated February 18, 1988, the Northeast Nuclear Energy Company (NNECO) 4 submitted a change to the Millstone 3 Technical Specifications. In Technical Specification Section 3.4.9.3 the minimum Reactor Coolant System (RCS) vent area required for cold overpressure protection would be changed from 7.0 to 5.4 square inches. In addition. Technical Specification Sections 3.8.1.2, 3.8.2.2 and 3.8.3.1 would be changed to r.ake them consistent with the revised Section 3.4.9.3.

EVALUA110N The design cold overpressure transients are mitigated by the operation of one Pcwer Operated Relief Valve (PORV) (see FSAR Section 5.2.2.11.2). The size of the vent area in Technical Specification Section 3.4.9.3 was selected to ensure that one PORY would be removed to provide the vent area; however, there was an error made in selecting the current value of 7.0 square inches. The removal of one PORY provides a vent area equal to the cross-sectional area of the piping for each PORY which is 5.4 square inches (pipe outside diameter is 3.5 inches, the wall thickness is 0.438 inches).

The required vent area to mitigate the design basis cold overpressure transients is approximately two square inches. Therefore, the staff finds the vent area of 5.4 square inches acceptable.

The reactor coolant system vent area also appears in the action statements for Technical Specification Sections 3.8.1.2, 3.8.2.2, 3.8.3.2. These sections are changed to be consistent with the revised Section 3.4.9.3. These are administrative changes, therefore, the staff find these changes acceptable.

ENVIRONMENTAL CONSIDERATION This amendment changes a requirement with respect to installation or use of a facility corponent located within the restricted area as defined in 10 CFR '

Part 20. The staff has detemined that the arendment 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 Comission has 880602023eOhh23 ADOCK O ppg PDR P

2 previously published a pr(posed finding that the amendeent involves no signifi. ,

cant hazards consideration and there has been no public comment on such finding.

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.

CONCLUSION We have concluded, based on the considerations discussed above, that (1) there is reascnable 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 cotpliance with the Commission's regulations, and the issuance of ',he amendment will not be inimical to the common defense and security cr to the health and safety of the public.  !

Dated: May 19,1988 Principal Contributor:

R. Ferguson  ;

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