ML20033E981
| ML20033E981 | |
| Person / Time | |
|---|---|
| Site: | Yankee Rowe |
| Issue date: | 03/06/1990 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20033E976 | List: |
| References | |
| NUDOCS 9003150207 | |
| Download: ML20033E981 (2) | |
Text
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UNITED STATES
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SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION
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SUPPORTING AMENDMENT NO.130 TO FACILITY OPERATING LICENSE NO. DPR-3 YANKEE ATOMIC ELECTRIC COMPANY YANKEE NUCLEAR POWER STATION DOCKET NO.50-029 l
INTRODUCTION By letter dated January 5,1990, the Yankee Atomic Electric Company (YAEC or 1
the licensee) requested an amendment to facility Operating License No. DPR-3 for the Yankee Nuclear Power Station (YNPS or the plant). The proposed amendment incorporates into the Technical Specifications modifications to allow Yankee to utilize a new Neutron Flux Instrumentation System, including its ability for enhanced testing at power, and modifications to clarify Specifications.
DISCUS $10N The present Neutron Fluy Instrumentation System at YNPS was installed during the initial plant construction. The instrumentation's past and present i
performance has been good. However, due to advances in the capabilities of more nodern systems and the difficulty to procure replacement parts, the licensee has requested to upgrade YNPS's system.
The upgraded system will be installed in the Control Room directly across from 3
the existing system in a new panel. - This panel accommodates new instrumentation 1
drawers as well as relays, status lights, switches, and other devices needed to interface with the Reactor Protection System. Changes to the front of the Main Control Board (MCB) are minimal. The source range, intermediate range, and start-up rate meters are reused. The six power level meters and associated gain adjustment potentiometers are replaced with new digital bargraph meters and gain adjustment push buttons. New alarms are provided on the MCB in i
addition to those presently used to complement the new neutron flux equipment.
Utilization of the upgraded system will require an allowance for bypassing, one train at a time, the new system trip logic during quarterly testing currently required for the Main Steam Isolation Trip Logic. This is due to the interface of the trip logic circuits in the upgraded system with the existing Reactor Protection System trip logic circuits via a common reactor trip circuits.
The upgraded system will allow Yankee to perform testing of its low trip setpoint during the channel functional and calibration tests. Additionally, Yankee will also be able to perform a quarterly testing of relays in the new J
system trip logic circuits. This enhanced testing capability will give further assurance that this vital equipment will perform its safety function, 9003150207 900306 PDR ADOCK 05000029 P
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ElWIPONMEt1Ttt (0t'S!UERATI,0N This entretent involves a changt in a requirement with respect to the instal 16tice or use of e fec.ility component located within the restricted area as defined in 10 CFR Part 20, and changes to the surveillance requirements. The staff has determined that the avendment involves no significant increase in the amounts, and no significant change in the types, of any effluents that may be released offsite, erd that there is ro significant increase in individual or cumulative occupationel radiation exposure. The Comission has previously published a proposec' finding that the amendment involves no significant hazards consideretion and there has been no public coment on such finding. Accordingly, this 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 essessment need be prepered in connection with the issuance of thit emendment.
CONCLUSION The Comittico made a proposed determination that the amendment involves re significant hazards consideratien which was published in the Federal Reaister (55 FR 2450) er January 2/,,1990. No public coments were received roc the State of l'assachutetts did not have any corrents.
The sta'f has concluded, based on the consideretions discussed above, that:
(1) there is reesenable assurance that the health and safety of the public wiii not be endangered by operation ir, the proposed manner, and (2) such activities will be conducted in compliance with the Comission's regulctions, and (3) the issuance of this enendment will not be inimitti tes the cerron defense end security or to the health and safety of the public.
l Principal Contributor:
Patrick Searr I
l l
Dated:
March 6. 1990 i