ML20141A187
| ML20141A187 | |
| Person / Time | |
|---|---|
| Issue date: | 04/02/1986 |
| From: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE) |
| To: | |
| Shared Package | |
| ML20141A173 | List: |
| References | |
| REF-QA-99901025 NUDOCS 8604040411 | |
| Download: ML20141A187 (3) | |
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TOPICAL REPORT EVALUATION Report Number:
29004-001, Rev. lA Report
Title:
Manufacturing of U.S. Nuclear Regulatory Commission Licensed Dry Storage / Transport Cask Systems for Radioactive Materials (Licensed Products) in the Federal Republic of Germany Report Date:
October 10, 1985 Originating Organization:
General Nuclear Systems, Inc.
(GNSI)
Reviewed By:
Quality Assurance Branch SumARY OF TOPICAL Topical Report 29004-001, Rev. 1A describes the quality assurance (QA) program which applies to the manufacturing activities for NRC-licensed dry storage /
transport casks systems for radioactive materials (licensed products) in the Federal Republic of Germany for use in the United States.
The program applies to those activities which are important to safety as that term is defined in 10 CFR 72.3.
Topical report 29004-001, Rev. lA commits the manufacturing process to comply with the requirements of Subpart G of 10 CFR Part 72.
- GNSI-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.
Topical Report
~29004-001, Rev. 1A contains a description of the measures used to carry out the QA program activities and describes how applicable requirements of Subpart G of 10 CFR Part 72 will be satisfied by the administration and implementation of the measures.
SUMARY OF REGULATORY EVALUATION We have evaluated the QA program and the organizations responsible for QA functions as described in Topical Report 29004-001, Rev. lA. 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 responsibility and authority commensurate with their duties in implementing the QA program.
We also find that measures have been established, to De implemented by written procedures and instructions, which address each of the criteria of Subpart G of 10 CFR Par 72.
Based on our review and evaluation of Topical Report 29004-001, Rev. 1A, we conclude that:
1.
The organizations and persons performing QA functions described therein have the required independence and authority to effectively carry out the QA program without undue influence from those directly responsible for costs and schedules, and l
2.
The QA program describes requirements, procedures, and controls which, when properly implemented, comply with the QA requirements of Subpart G of 10 CFR Part 72.
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REGULATORY POSITION It is the staff's position that the GNSI Topical Report 29004-001, Rev. lA,
" Manufacturing of U.S. Nuclear Regulatory Commission Licensed Dry Storage / Transport Cask Systems for Radioactive Materials (Licensed Products) in the Federal Republic of Germany," is acceptable for use in the manufacture of NRC licensed products in the Federal Republic of Germany for use in the U.S.A.
The Topical Report can be referenced by report number in Section 11 of Safety Analysis Reports for independent spent fuel storage installations.
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