ML19319A705
| ML19319A705 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 04/17/1975 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19319A704 | List: |
| References | |
| NUDOCS 7911270699 | |
| Download: ML19319A705 (2) | |
Text
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TOPICAL REPORT EVALUATION 7
Report Number:
DUKE-1, Nonproprietary
_ Report
Title:
Quality Assurance Program, DUKE-1 (Amendment No. 2)
Report Date:
February 1975 Originating Orgar.ization:
Duke Power Company
. Reviewed By:
Quality Assurance Branch SUIMARY OF TOPICAL REPORT Topical Report DUKE-1 describes the Quality Assurance.(QA) Program which the Duke Power Company (DPC) applies to those design,
' procurement, construction, and operations phase activities of safety related structures, systems, and components of DPC's-nuclear power
' plants.
DUKE-1 commits DPC to comply with the requirements of Appendix B to 10 CFR Part 50 and to follow the QA guidance provided by the NRC in:
1.
" Guidance on Quality Assurance Requirements During Design and Procurement Phase of Nuclear Power Plants," WASH 1233, Rev. 1, May 24, 1974, 2.
" Guidance on Quality Assurance Requirements During the Construction Phase of Nuclear Power Plants," WASil 1309, May 10, 1974, and 3.
" Guidance on Quality Assurance Requirements During the Operations
' Phase of Nuclear Power Plant's," WASH 1284, October 26, 1973.
DPC has provided for our evaluation a detailed organizational description of those individuals and groups involved in carrying out activities required by the QA Program and a delineation of duties, s
responsibilities, and authority of those organizational elenents in the QA Program.
DUKE-1 contains a description of the measures used to carry out DPC's QA Program activities and describes how applicable requirements of Appendix B will be satisfied by the administration and implementation of these neasures.
SUFB1ARY OF REGULATORY EVALUATION We have evaluated the QA' Program and the organizations responsible for QA functions as describe' in DUKE-1..We find thatlQA policy and direction originate at an acceptably high management level and are effectively communicated to other parts of the organization.
Those performing QA functions have responsibility and authority commensurate with their duties in imp h menting the QA Program. We also find that neasures have been established, to be implemented by written procedures and instructions, which address each of the criteria of Appendix B and demonstrate conformance with each criterion.
Based on our review and evaluation of DURE-1, we conclude that:
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l..-The organizations'and persons perfdrming QA functions within
'DPC have.the.' required independence and authority to effectively carry out the QA Program without reservation or undue influence' i
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-from those directly responsible-for. costs and schedules, and 2.
The DPC QA Program contains the necessary requirements, procedures,'and controls to demonstrate that quality-related activities will.be conducted in accordance with Appendix B r
to 10 CFR Part 50..
1 REGULATORY-POSITION It is the staff's position that DPC's Topical Report " Quality Assurance Program, DUKE-1," is acceptable for use in the design,
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procurement, construction, and operations. phase of nuclear power plants. The Topical Report Sections 17.0 and 17.1 can be referenced by' report number in Section-17.1 of future-Preliminary Safety l
Analysis Reports, and Sections'17.0 and 17.2 can be referenced by report number in Section 17.2 of-future Final Safety Analysis Reports.
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