ML20154R730

Safety Evaluation Supporting Util 840206 Response to Generic Ltr 83-28,Item 4.5.1, Reactor Trip Sys Reliability (Sys Functional Testing)

ML20154R730
Person / Time
Site:	Waterford
Issue date:	09/28/1988
From:	NRC
To:
Shared Package
ML20154R721	List: ML20154R717 ML20154R730
References
GL-83-28, NUDOCS 8810040341
Download: ML20154R730 (2)

Text

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SAFETY EVALUATION FOR GENERIC LETTER 83-28 ITEM 4.5.1 - REACTOR TRIP

$YSTEM RELIABILITY ($YSTEM FUNCTIONAL TEST!hG) t WATERFORD 3 i DOCKET le0: 50 382 [

1. INTRODUCTION On February 25, 1983. both the scram circuit breakers at Unit 1 of the i Salee kuclear Power Plant failed to open upon an automatic reactor trip  :

signal from the reactor protection system. This incident occurred during ,

the plant startup and the reacter was tripped renually by the operator about 30 seconds af ter the initiation of the automatic trip signal. The failure of the circuit breakers has been determined to be related to the sticking of the under voltage trip attachment. Prior to this incident. (

on February 22. 1983, at Unit 1 of the Salem Muclear Plant, an automatic ,

trip sigral was generated based on steam generator low low level during L plant startup. Ln this event scrar circuit breakers also failed to open upon an autoratic reactor trip signal. In this case. the reactor was '

tripped r.anually by the operator almost coincidentally with the autcedtic trip.

l Following these incidents, on February 28,19t3 the NRC Executive. Director [

for Crerations (EDO). directed the staff to investigate and report on the ,

generic trplications of these occurrences at Unit 1 of Salem Nuclear Power i Plant. The results of the staff's inquiry into the generic implications l of the Saler unit incidents are reported in FUREG-1000. "Generic Implications ,

at ATW5 Events at the Saler Nuclear Power Plant." As a result of this ,

investigation, the Cossiission requested (by Generic Letter 83 28 dated  :

July 8.1983) all licensees of operating reactors, applicants for en operating license, and holders of construction perrits to respond to certain generic concerns. These concerns were categorized into four ,

areas: (1)PostTripReview.(?)EquipeentClassificationandVendor ,

Interface. (3) Post Paintenance Testing, and (4) Reactor Trip System (RTS) l Reliability improvements.  ;

The fourth action itee. RT5 Reliability Irprovements, censists of Action Itees 4.1 through 4.5. This safety eve 194 tion re Mrt (5ER) addresses ,

Action item 4.5.1. 'RTS Reliability Irprovements 15ystee Functional i Testing).'only. }

!!. REVIEW GU10ftlhES I This evaluation of the utility response was conducted using NRR review  :

guidelines dated February 11, 1985 from Mr. Fran6 J. Piraglia. Actirg j 8910040343 anowg fDR ADOCK 0500030p rw  !

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Director. Division of Licensing NRR to Pr. Richard P. Denise Of rector of Reactor Safety and Projects. Region IV and other Region Division Directors. The review guidelines state that this item concerning testing diverse trip features should be considered complete when the licensee has sutritted a staterent comitting to independent, on-line functional testing of the diverse trip features.

!!!. EVALUATION AND CONCLUSION By letter dated February 6. 1984. the licensee provided information regarding RTS on line testing of diverse trip features.

The licensee stated that on line functional testing of the reactor grotection system will be perfornd using operating procedure OP 903 CCC, Manual Reactor Trip Test.' We have reviewed this procedure as part of the plant records and the tests of the undervoltage and shunt features for all eight reactor trip breakers are included. The tests are perforced in accordance with the procedures and as required by the Technical Specifications every 18 months.

Based on our review, we conclude that the on-line reliability verification testing of the reactor protection system by Vaterford 3 reets the review guidelines and is acceptable.

Frincipal NPC Contributor. T. Staker Dated: September 28, 1988