ML19327C160
| ML19327C160 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 11/08/1989 |
| From: | NRC |
| To: | |
| Shared Package | |
| ML19327B717 | List: |
| References | |
| GL-83-28, NUDOCS 8911210037 | |
| Download: ML19327C160 (3) | |
Text
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g, ENCLOSURE j
i SAFETY EVALUATION GENERIC LETTER 83-28. ITEM 2.2.1
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EQUIPMENT CLASSIFICATION PROGRAM FOR ALL SAFETY-RELATED COMPONENTS JAMES A. FITZPATRICK NUCLEAR POWER PLANT DOCKET NO. 50-333
1.0 INTRODUCTION
s Generic Letter 83-28 was:1ssued by the NRC on July 8, 1983 to indicate actions to be taken by licensees and applicants based on the generic implications of the Salem ATWS events.
Item 2.2.1 of that letter states that ifcensees 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 r
licensee / applicant's submittal was required to contain information describing
. (1)-the criteria used to identify these components as safety-related; (2) the information handling system which identifies the components as safety-related; s
(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, 8911210037 891108 PDR ADOCK 05000333 P
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1 validated, and used in accordance with approved procedures; and (5) design verification and qualification testing requirements that are part of the specifications for procurement of safety-related components.
The licensee for the James A. FitzPatrick Nuclear Power Plant responded to the requirements of this item in submittals dated November 9, 1983, June 29, 1984, July 2, 1985, December 31, 1985, March 20, 1987, and October 16, 1989. We have evaluated these responses and found them to be acceptable.
2.0 DISCUSSION AND-EVALUATION The New York Power Authority, the licensee for The James A. FitzPatrick-Nuclear Power Plant provided submittals describing programs to assure that all components necessary for accomplishing the required safety-related functions are properly designated on plant documents, procedures, and in the information handling systems that are used to control plant activities that may affect these components.
l These ;abmittals contained a description of the criteria used to classify components and equipment as safety-related and a description of the information handling system including the procedures for maintaining it and preventing unauthorized changes to it.
Included also was a description of how the i
station personnel use this information handling system to determine the
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classification of components and equipment when preparing work requests which control all activities which may affect these components and equipment at the plant.
In addition, management controls were described which the licensee uses'to assure that the information handling system was properly prepared and validated,.is adequately maintained and is used as was intended.
- Further, licensee requirements to include evidence of design verification and
. qualification testing in procurement specifications for replacement components were described.
More detailed evaluation of the licensee submittals relative to this item is presentedintheenclosedcontractor'stechnicalevaluationreport(NTA-7215).
3.0 CONCLUSION
On the basis of this evaluation, the staff and our contractor have found the licensee's responses relating to their equipment classification program for l
l safety-related components to be acceptable.
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