ML20212E224

Safety Evaluation Accepting Util 831104 Response to Item 4.5.2 of Generic Ltr 83-28 Re on-line Functional Testing of Reactor Trip Sys,Including Independent Testing of Diverse Trip Features of Reactor Trip Breakers

ML20212E224
Person / Time
Site:	Farley
Issue date:	02/27/1987
From:	Office of Nuclear Reactor Regulation
To:
Shared Package
ML20212E173	List: ML20212E170 ML20212E224
References
GL-83-28, NUDOCS 8703040297
Download: ML20212E224 (1)

Text

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ENCLOSURE 1

SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION GENERIC LETTER 83-28. ITEM 4.5.2

REACTOR TRIP SYSTEM RELIABILITY, ON-LINE TESTING

JOSEPH M. FARLEY NUCLEAR PLANT, UNITS 1 AND 2 DOCKET N05. 50-348 AND 50-364 INTRODUCTION Generic Letter 83-28, issued by NRC on July 8,1983, defines certain actions to j be taken by reactor plant licensees based on the generic implications of the

Salem Anticipatory Trip Without Scram events. Item 4.5 is a staff position i which requires on-line functional testing of the reactor trip system, including independent testing of the diverse trip features of the reactor trip breakers

, for all plants. Item 4.5.2 recuires applicants and licensees with plants not currently designed to pemit this periodic on-line testing to .fustify not '

4 making modifications to permit such testing. However, design modifications for the automatic shunt trip are installed at the Farley site as approved by our

, letter dated September 20, 1983. By letter dated November 4,1983, Alabama Power Company, the licensee for Farley Nuclear Plant Units 1 and ?, responded to the staff position regarding Item 4.5.7 of Generic Letter 83-28. Our review of this response follows.

EVALUATION

. Licensee letter dated November 4,1983, defines the on-line testing of the undervoltage and shunt trip attachments of the reactor trip breakers and refers to our previous reviews. Our previous evaluation, noted above, confirmed that the design of the reactor trip breakers permits on-line and independent testing of the undervoltace and shunt trip attachments. Further, the existing Farley plant Technical Specifications require on-line testing of the entire reactor trip system on a periodic basis.

CONCLUSION The NRC staff finds that the Joseph M. Farley Nuclear Plant, Units 1 and 2 are designed to pemit on-line functional testing of the reactor trip system, including independent testing of the diverse trip features of the reactor trip breakers. Thus, the desion meets the staff position of Item 4.5.2 of Generic letter 83-28, and is acceptable.

Date: February 27, 1987 Principal Contributors:

A. Toalston E. Reeves 8703040297 87022738 ADOCK 050 l

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