ML19324C293

Safety Evaluation Supporting Licensee Responses to Generic Ltr 83-28,Item 2.2.1, Equipment Classification Program for All Safety-Related Components

ML19324C293
Person / Time
Site:	Grand Gulf
Issue date:	11/08/1989
From:	Office of Nuclear Reactor Regulation
To:
Shared Package
ML19324A624	List: ML19324A623 ML19324C292 ML19324C293
References
GL-83-28, NUDOCS 8911160090
Download: ML19324C293 (2)

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S FETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGUI.ATION GRAND CULF NUCLEAR STATION, UNIT 1 DOCKET NO. 50-416 GENERIC LETTER 83-28. ITEM 2.2.1 i

EQUIPMENT CLASSIFICATION PROGRAM FOR ALL SAFETY-RELATED COMPONENTS 1

1.0 INTRODUCTION

Generic Letter 83-28 was issued by the NRC on July 8,1983 to indicate actions I

to be taken by licensees and applicants based on the generic implications of i

the Salem ATWS events.

Item 2.2.1 of that letter states that licensees and applicants shall describe in considerable detail their program for classifying all safety-related components other than RTS components as safety-related on plant documents and in information handling systems that are used to control ~

plant activities that may affect these components.

Specifically, the i

licensee / applicant's submittal was required to contain information describing *

(1) the criteria used to identify these components as saf ety-related; (2) the information handling system which identifies the components as safety-related, (3) the manner in which station personnel use this information handling system to control activities affecting these components; (4) management controls that are used to verify that the information handling system is prepared, maintained, validated, and used in accordance with approved procedures; and (S) design verification and qualification testing requirements that are part of the specifications for procurement of safety-related components.

i The licensee for Grand Gulf Nuclear Station, Unit 1, submitted responses to Generic Letter 83-28 Item 2.2.1 in submittals dated June 26, 1985 and i

June 17, 1988. We have evaluated these responses and find them to be acceptable.

2.0 DISCUSSION AND EVALUATION i

t The licensee for Grand Gulf Nuclear Station, Unit 1, provided submittals that cescribe programs to assure that all components necessary for accomplishing the required safety-related functions are properly designated on alant documents, in plant procedures, and in the information hanaling system tlat are all used l

to control plant activities that may affect these components. A description of the criteria used for classifying components and equipment as saf ety-related and a description of the preparation, maintenance, control and use of the e

information handling system which contains the classification information were also provided.

In addition, management controls used by the licensee assure

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that the information handling system will be consistent, adeouately prepared and maintained, and will be used as intended.

Furthermore, the licensee assures that appropriate design verification and qualification is specified for the procurement of safety-related components and parts.

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Detailed evaluation of this item is documented in the contractor's technical report EGGtNTA-7293 (Enclosure 2 to letter dated November 8,1969).

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3.0 CONCLUSION

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The staff and our contractor have reviewed the licensee's responses to Generic Letter 83-28, Item 2.2.1, regarding the equipment classification program for safety-related components and conclude that they are acceptable.

Principal Contributor:

L. Tran r

Dated: November 8, 1989 I

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