ML20005D923
| ML20005D923 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 12/20/1989 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20005D922 | List: |
| References | |
| GL-83-28, NUDOCS 9001020271 | |
| Download: ML20005D923 (2) | |
Text
.
)'
r^
8 o
UNITED STATES
[
E" NUCLEAR REGULATORY COMMISSION
~
r n-
.E
- I-WASHING TON. D, C. 20655 i
k....
p t
ENCLOSURE 1
'E SAFETY EVALUATION BY THE OFFICE OF flUCLEAR REACTOR REGULATION GENERIC LETTER 83-28. ITEM 2.2.1 EQUIPMENT CLASSIFICATION PROGRAM FOR ALL SAFETY-RELATED COMPONENTS EDWIN I. HATCH NUCLEAR PLANT. UNITS 1 AND 2 GEORGIA POWER COMPAliY DOCKET NOS._50-3?1 AND 50-366
- 1. - li4TRODUCTI.O.N I
Generic Letter 83-28 was issued 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 ATHS 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 ccmponents 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 licensee's/ 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; (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, maintaineo, 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, Georgia Power Company, responded to Generic Letter 83-28, Item 2.2.1 in submittals dated November 7,1983, Februncy 29, 1984, June 3, 1985, and September 8,1988. We have evaluated these responses and conclude that they are acceptable.
2.0 DISCUSSION AND EVALUATION E
The-licensee for Edwin 1. Hatch Nuclear Plant, Georgia Power Company, provided submittals describing a program for classifying all safety-related components as l
L safety-related on plant documents, procedures, and information handling system that are useo in the plant to centrol safety-related activities.
In addition, 1
l 1
L 9001020271 891220 l
PDR ADOCK 05000321 1
.p PNV
g..
- the licensee also upgraded the present program which will enhance the procurement, neintenance, and operation of the plant by designating a component as active or passive and safety-related or non-safety-related.
A description of the criteria for classifying the structure, system, or component as safety-related and a description of the information handling system used to identify safety-related components and the methods used for its development and validation was also provided.
Furthermore, the licensee described the process by which the station personnel use this information handling system to determine that an cetivity is safety-related and the procedures that apply to the subject activity.
Periodic audits will be used as management controls to assure information handling systems will be consistent, adequately prepared and maintained, and used as intended. Also, the licensee requires that appropriate design i
verification and qualification testing is specified for the procurement of all safety-related components and parts.
Detailed evaluation of this item is docunented in the enclosed contractor's report.
3.0 CONCLUSION
We have reviewed the licensee's responses to Generic Letter 83-28 Item 2.2.1, i
regarding the equipment classification program for safety-related components and conclude tnat they are acceptable.
4
- - _ -