ML20245D435

Safety Evaluation Supporting Amend 112 to License DPR-36

ML20245D435
Person / Time
Site:	Maine Yankee
Issue date:	04/24/1989
From:	Office of Nuclear Reactor Regulation
To:
Shared Package
ML20245D433	List: ML20245D428 ML20245D434 ML20245D435
References
NUDOCS 8904280302
Download: ML20245D435 (2)

Text

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fM m 'O UNITED STATES NUCLEAR REGULATORY COMMISSION '

i "k. .i,r , b' i #1.

,((ffef WASHINGTON, D. C. 20555 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR PEACTOR REGULATION RELATED TO AMENDMENT NO.112 TO FACILITY OPERATING LICENSE N0. DPR-36 MAINE YANKEE ATOMIC POWER COMPANY MAINE YANKEE ATOMIC POWER PLANT DOCKET N0. 50-309

1.0 INTRODUCTION

On Maren 28, 1988 Faine Yankee Atomic Power Company (MYAPCo) submitted its

. final report on the design and accuracy evaluation of the Inadequate Core CoolingInstrumentationlICCI)fortheMaineYankeeAtomicPowerStation (MYAPS).

The staff reviewed the information presented by MYAPCo and the staff concluded that MYAPCo's ICCI system for MYAPS consisting of (1) a vessel l inventory system based en a differential pressure (dp) system, (2) a '

saturation margin rionitor, and (3) a core er.it thermocouple system is acceptable since it meets the requirements of Item II.F.2 of NUREG-0737. The staff acceptance, however, is contingent on the resolution of the following open items.

1. Emergency procedures and operator training in the use of the ICCI system have not been reviewed by the staff.

2. Technical Specifications for the ICCI system have not yet been submitted and reviewed by the staff.

3. An implementation letter report as required by Item II.F.2 of NUREG-0737 1 l must be submitted by MYAPC0 (see attachment to this safety evaluation report).

l The conclusions end the open items were transmitted by letter to MYAPCo dated July 7, 1988. .

By letter dated February 15, 1989 MYAPCo submitted Technical Specifications for the ICCI system.

D P

4r 2.0 EVALN TIOM In December, 1988 the licensee installed the ICCI to satisfy a NUREG-0737 requirement. TFe syster supplements existino instrumentation in order to insure an unambiguous, easy-to-interpret indication of inadequate reactor core coolirp. The proposed Technical Specifications are in accordance with

! NRC guidelines in that they meet the required number of operable instrument l channels, the frequency #or checks, calibration and testing of the system.

I ICCI does not actuate any control function of the reactor system. Its l

purpose is to provide the plant operator additional information on reactor vessel water level, particularly during transient events. Such data is utilized ir. the MYAPS emergency operating procedures. The proposed Technical Specifications on ICCI do not create any new or different kind of accident because they do not interact with any safety aspects of plant operations.

I-The additional information, provided to the operator, may increase margins of safety for plant operators during unusual events. Early indication on whether or not the water level is responding to corrective measures taken during an event is important information for safe operations.

l l 3.0 ENVIROWENTAL CONSIDEpfTION This amer h ent involves a change in the installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20.

The steff has determined that the amendment involves no signficant increase in the amounts, and no significant change in the types, of any effluents that may be released of4ite, and that there is no signficant increase in individual or cumulative occu mtional radiation exposure. The Commission has previously issued a proposed finding that this amendment involves no signficant hazards consideration and there has been no public comment on such

findir.c. Accordingly, this. amendment meets the eligibility criteria for I categorical exclusion set forth in 10 CFR 51.22(c)(9). Pursuant to 10 CFR l 51.22(b), no environmental impact statement or environmental assessment need

! be prepared in connection with the issuance of this amendment.

4.0 CONCLUSION

i 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 nanner, and (2) such l activities will be conducted in compliance with the Commission's regulations, and the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the p"blic.

Principal Contributor: Patrick Sears Dated: April 24, 1989 l

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