ML17202G713
| ML17202G713 | |
| Person / Time | |
|---|---|
| Site: | Dresden, Quad Cities, 05000000 |
| Issue date: | 11/28/1989 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17202G712 | List: |
| References | |
| GL-83-28, NUDOCS 8912060032 | |
| Download: ML17202G713 (2) | |
Text
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Ef!JCLOSURE.1 SAFETY EVALUATION.BY.THE OFFlCE.OF NUCLEAR.REACIQ.g.REGULATION CQMMONWEALT~.EDISON COMPANY.
1.0 INTRODUCTION
DRESDEN.UNITS 2 AND.3 DOCKET.NOS. 50-237 AND 50.249 gUAD.CITIES UNITS.I ANQ~£ DOCKET NOS. 50.254.ANO 50-265 GENERIC LETTEe.83:gB,--ITEM 2.2.1 E9U1~MENT.CLAS~IFICATION FOR ALL.
SAFETY.RELATED.COMPONENTS 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 ATWS events.
Item 2.2.1 of that lttter 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 lic~nsee/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 th~ 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 (5) design verification and qualification testing requirements that are part of the specifications for procurement of safety-related components.
Commonwealth Edison Company (CECo), the licensee, for.both Dresden and Quad Cities, responded to the requirements of this item in dual submittals dated November 5, 1983, February 29, 1984, April 3, 1989, and October 4, 1989 (which was further clarified by an October 27, 1989 submittal).
We have evaluated these responses and find them to be acceptable.
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- ' 2.0 DISCUSSION.ANO.EVALUATION The submittals provided by CECo aescribed the programs in place 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 ar-e used to-control plant activities that may affect these components.
These submittals 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 station personnel use this information handling system to determine the classification of components and equipment when preparing work requests which control all
_activities which mdy 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 require-ments to include evidence of design verification and qualification testing in procurement specifications for replacement components were described.
More detailed evaluations of the licensee submittals relative to this item are presented in the enclosed contractor's technical evaluation reports EGG-NTA-7202, (October 1989) for Dresden and EGG-NTA-7299 (October 1989) for Quad Cities.
- 3. 0 CONCLUSION On the basis of this evaluation, the staff finds the licensee's responses relating to their equipment classification program for safety-related components to be acceptable for both Dresden and Quad Cities.
Principal Contributor:
Donald Lasher Dated: