ML20246F381

Safety Evaluation Supporting Amend 31 to License DPR-21

ML20246F381
Person / Time
Site:	Millstone
Issue date:	05/02/1989
From:	Office of Nuclear Reactor Regulation
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Shared Package
ML20246F373	List: ML20246F369 ML20246F375 ML20246F381
References
NUDOCS 8905120216
Download: ML20246F381 (3)

Text

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• UNITED STATES NUCLEAR REGULATORY COMMISSION c E WASHINGTON, D. C. 20555 5, s %. /!

3.x....f SAFETY EVALUATION EY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 31 TO FACILITY OPERATING LICENSE NO. DPR-21 NORTHEAST NUCLEAR ENERGY COMPANY MILLSTONE NUCLEAR p0WER STATION, UNIT N0. 1 DOCKET NO. 50-245 INTRODUCTION Ey letter dated January P4,1989, Northeast Nuclear Energy Company (NNECO or licensee) submitted a request for changes to the Technical Specifications (TS) for Millstone Nuclear Power Station, Unit No. 1.

The amendment will revise the TS to provide a clarification for Emergency Core Cooling System (ECSS) eveilability and power supply requirements when the reactor is in the refueling mode, in addition, references to Sections 3.5.F.8, 3.7.C.1.c and 3.7.C.I.d will be deleted from the TS since those sections were deleted in Amendment No.1, dated January 29, 1987 EVALUATION During the Spring 1989 refueling outage, the litersee plans to conduct maintenance and inspections on 4160 volt busses 14C and 14D. This work will necessitate removing these busses from service, not concurrently, for extended periods of time. A review of the TS by the licensee identified TS 3.5.F.7(e) as being affected by the proposed maintenance of busses 14C and 14D. Specifically, this TS requires that the ECCS subsystems be operable or available for operation with the breakers racked out and that the subsystems comprising the allowable selection combination be supplied by independent electrical power.

L TS 3.5.F.7, as currently written, does not allow fuel movement if the ECCS requirements of TS 3.5.F.7(e) are not met. The licensee's proposed TS change would clarify the ECCS availability and power requirements for ECCS. The changes proposed by the licensee retains the requirement for availability of two ECCS subsystems, thus maintaining redundancy in water supply system equipment. This change does clarify the power supply requirements for these ECCS systems.

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l In addition, the licensee proposes changing the term " racked out" to

" racked down" in TS 3.5.F.7(e) because the latter term is used widely by the Millstone Unit No.1 operating staff.

l The remaining proposed changes are editorial in nature. References to TS 3.5.F.8 are being deleted f rom specifications 3.5. A.1, 3.5. A.3, 3.5.B.1, and 3.5.F.1, since TS 3.5.F.8 was combined with TS 3.5.F.7 in Amendment No. 1. Reference to TS 3.7.C.1c and d is being deleted from TS 3.7.B.5, since Specifications 3.7.C.1c and d were deleted in Amendment No. 1.

The staff has reviewed the licensee's January 24, 1989 proposal regarding changes in the TS for ECCS availability and power supply reovirements.

ECCS is provided in a light water nuclear power plant to provide cooling and makeup water in the event of a pestulated loss-of-coolant accident (LOCA) as required by General Design Criterion 35 (GDC 35) and 10 CFR 50.46.

The licensee's proposed change to TS 3.5.F.7 is applicable when the reactor is in the refueling mode only. In this mode, the reactor is shutdown, the system is depressurized, the reactor vessel head is off, and water level is maintained within required limits. As detailed in the Standard Technical Specifications, ECCS is not required to be operable in these conditions.

The licensee's proposal would still require that two ECCS subsystems be available, with the breakers racked out. The TS change would clarify the allowable sources of ECCS subsysten power. The staff finds this proposal to be acceptable since it is more conservative than required, will provide an adequate level of safety when operating in the refueling mode and does not change the intent of the ECCS requirements. Also, the staff finds the change in terminology from " racked out" to " racked down" to be acceptable since these are equivalent expressions and it will eliminate a possible source of confusion between the TS that presently uses " racked out" and the operating stcff that uses " racked down."

The staff finds the remainino proposed changes (deletion of references to TS 3.4.F.8, 3.7.C.1(c) and (d) acceptable since these are minor editorial changes mode to reflect a previous change made in Amendment No. 1, dated January 29, 1987.

ENVIRONMENTAL CONSIDERATION This amendment changes a requirement with respect to the installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20 and makes changes which are minor and corrective in nature. We have 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 staff has previously published a proposed finding that the amendment involves no significant 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 951.22(c)(9). Pursuant to 10 CFR 651.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendment.

9 CONCLUSION We have 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 (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.

Dated: May 2, 1989 Principal Contributor: Mike Boyle

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