ML20150C147
| ML20150C147 | |
| Person / Time | |
|---|---|
| Issue date: | 10/20/1987 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20150C150 | List: |
| References | |
| REF-QA-99900403 NUDOCS 8803180041 | |
| Download: ML20150C147 (1) | |
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APPENDIX A General Electric Company
. Nuclear Energy Business Operations Docket No. 99900403/87-03 NOTICE OF NONCONFORMANCE During an inspection conducted July 27 - Au General Electric's (GE) Quality Assurance (gust 6, 1987, the implementation of QA)programattheSanJose, California facility was reviewed.
In addition, documentation supporting GE's response to items of nonconformance and unresolved items in relation to NRC Inspection Report No. 99900403/87-01 was also reviewed. This review was in response to allegations submitted to the NRC by the Government Accountability Project, based upon a review of work records supplied them by a former GE employee, Mr. Sam A. Milam, III. These concerns allege potential deficiencies in design control activities within GE's QA program during the period March 1978 to April 1982. The QA program requirements are discussed in GE Topical Report NED0-11209-04A, Revision 6, dated June 30, 1986, which describes the QA program GE applies to those design, procurement, and fabrication activities involving safety-related structures, systems, and components of nuclear power plants within the GE scope of work. Section 5 of NED0-11209-04A, Revision 6, requires, in part, that activities affecting quality be accompitshed in accordance with documented instructions, procedures, or drawings.
Based on the results of this inspection, it appears that certain activities at the San Jose facility were not conducted in accordance with consnitments made to the NRC.
GE Topical Report Section 3.12. "Design Change Application," states, in part, that following management decision to apply corrective action to specific projects, the responsible engineer makes the necessary design document changes I
to implement the change as outlined in GE Engineering Operating Procedure 42-6.00, "Independent Design Verification."
Contrary to the above, documentation reviewed could not support GE's performance of a seismic analysis, as required by the GE Problem Review Board in a letter dated November 17, 1980, extending the original seismic qualification data performed in 1978, to a 1980 revised design configuration of the reactor mode switch and its interface with the isolation casing.
(87-03-01)
YDf 41 871020 999004o399 ENVGENE DCD
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