ML20052A081
| ML20052A081 | |
| Person / Time | |
|---|---|
| Issue date: | 04/09/1982 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20052A078 | List: |
| References | |
| NUDOCS 8204270049 | |
| Download: ML20052A081 (2) | |
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TOPICAL REPORT EVALUATION Report Number: BAW-10096A, Rev. 4 Report
Title:
B&W NPGD Quality Assurance Program for Nuclear Equipment Report Date: March 1975, Revised March 1982 Originating Organization: Babcock.& Wilcox Company Reviewed by: Quality Assurance Branch
SUMMARY
OF TOPICAL Topical Report BAW-10096A, Rev. 4 describes the quality assurance (QA) program which Babcock & Wilcox (B&W) applies to those design, procurement, and manufac-turing activities involving safety-related structures, systems, and components of nuclear power plants within the B&W scope of work.
BAW-10096A, Rev. 4 com-mits B&W to comply with the requirements of Appendix B to 10 CFR Part 50 and to comply with the Regulatory Position of Regulatory Guides 1.28 (2/79), 1.30 (8/72), 1.37 (3/73), 1.38 (5/77), 1.58 (9/80), 1.64 (6/76), 1.74 (2/74), 1.88 (10/76), 1.123 (7/77), 1.144 (9/80), and 1.146 (8/80).
B&W 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, responsibilities, and authority of those organizational elements involved in the QA program.
B&W-10096A, Rev. 4 contains a description of the measures used to carry out the B&W QA program acti-vities and describes how applicable requirements of Appendix B will be satisfied by the administration and implementation of these measures.
SUMMARY
OF REGULATORY EVALUATION We have evaluated the QA program and the organizations responsible for QA func-tions as described in BAW-10096A, Rev. 4.
We find that QA 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 respon-sibility and authority commensurate with their duties in implementing the QA pro-gram. We also find that measures have been established, to be implemented by written procedures and instructions, which address each of the criteria of Appen-dix B in an acceptable manner.
Based on our review and evaluation of BAW-10096A, Rev. 4, we conclude that:
1.
The organizations and persons performing QA functions within B&W have the required independence and authority to effectively carry out the QA program without undue influence from thos'e directly responsible for costs and schedules, and 2.
The B&W QA program contains requirements, procedures, and controls which, when properly implemented, comply with the requirements of Appendix B to 10 CFR Part 50 and the applicable regulatory guides contained in Section l
17.1 of the NRC Standard Review Plan.
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REGULATORY POSITION It is the staff's position tthat the B&W topical report BAW-10096A, Rev. 4, "B&W NPGD Quality. Assurance Program for Nuclear Equipment,".is' acceptable for use in
' the design, procurement, and manufacturing of nuclear power plants.
The topical l
report can be referenced by report-number in Section 17 of the Safety Analysis Report.
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