ML19274C742
| ML19274C742 | |
| Person / Time | |
|---|---|
| Site: | 07000754 |
| Issue date: | 09/14/1978 |
| From: | Kratzke R NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | Starostecki R NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| References | |
| NUDOCS 7811170083 | |
| Download: ML19274C742 (3) | |
Text
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UNITED STATES NUCLEAR REGULATORY COMMisslON 3%
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SEP 141978 DOCKET N0:
70-754 LICENSE N0:
SNM-960 MEMORAN0UM FOR:
Richard W. Starostecki, Chief Fuel Reprocessing and Rscycle Branch Division of Fuel Cycle and Material Safety FROM:
Robert T. Kratzke Fuel Reprocessing and Re. cycle Branch Division of Fuel Cycle and Material Safety APPLICANT:
General Electric Company FACILITY:
Vallecitos Nuclear Center
SUBJECT:
NRC - GE VALLECITOS NUCLEAR CENTER MEETING
SUMMARY
, SEPTEMBER 5 - 7, 1978 Enclosed is the meeting summary for the September 5 - 7, 1978 meeting between NRC and GE Vallecitos Nuclear Center.
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m F'obert T. Kratzke Fuel Reprocessing and Recycle Branch Division of Fuel Cycle and Material Safety
Enclosure:
As Stated 781117 CD93
SUMMARY
OF GENERAL ELECTRIC VALLECITOS tiUCLEAR CENTER SITE VISIT - SEPTEMBER 5-7, 1978 During the peried Septenber 5-7, 1978, R. T. Kratzke and L. L. Gordon of the NRC visited the General Electric Vallecitos Nuclear Center (VNC) site.
The purpose of the visit was to review man 3gement control functions and quality assurance (QA) programs plan for the VNC operations.
Also to assess implementation of the QA plan.
A variety of other subjects were discussed as appropriate to the completion of the SNM-960 license renewal review or pertinent to such licensing action. This included criticality, radiation protection, effluent monitoring, tritium releases and decommissioning.
The meeting attendees were:
GE VNC G. E. Cunningham, Senior Licensing Engineer R. A. Moschner, Manager, fluclear Safety and Quality Assurance e
V. L. Whitman, Quality Assurance, Irradiation Processing Operation G. C. Be rg, ARSD, Product Assurance E. F. Kurtz, Manager, Advanced Fuel Laboratory flRC R. T. Kratzke, Licensing Project Manager L. L. Gordon, Quality Assurance During the meetings with VNC personnel, the following observation, statements, and commitments were made:
The license conditions concerning QA as presented in Section 10, Appendix A of the SNM-960 license renewal application required certain revisions to clarify aspects of the conditions and to commit VNC to appropriate points as presented in 10CFR50 Appendix B.
These revisions dealt with the scope of the QA program, procedures and instructions, audits, and storage of records systems.
Assessment of the QA manuals (administrative, QA procedures and QA instructions) revealed that the implementing procedures essentially met the requirements of ANSI ti46.2 "QA Requirements for Past Reactor Nuclear Facilities". The program however was lacking a procedure covering records management. VNC has committed to the preparation of this procedure prior to iscuance of the license.
VNC also comitted to make certain changes in tha audit procedure.
NRC will review and determine the items and systems that are safety related and subject to the QA plan as based on 10CFR50 Appendix B.
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- Change Authorizations (CA) i VNC's primary management control tool used to assure proper maintenance of protection levels for VNC operations under-going modification or the initiation of new operations.
Aspects of the CA procedures, management responsibilities and lines of authority were reviewed in detail.
The role of the Vallecitos Technological Safety Council (VTSC) in the management scheme was also discussed.
In general, Appendix A clearly outlines an effective management scheme highlighting the topics discussed.
However some revisions will be required to include CA records management provisions.
This should be completed by September 29, 1978.
VNC is reviewing NRC's comments and proposed license conditions concerning cri ticali ty.
VNC intends to discuss with the NRC those proposed changes within the next couple days. After resolution of the issues, GE will incorporate the conditions into Appendix A " License Conditions" of the renewal application.
Target date for this revision is September 29, 1978.
i A site-wide decommissioning study is being undertaken at the Division level.
en The study is currently evaluating the various decommissioning options. The study is in its initial phases.
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