IR 05000094/1979001
| ML19253C524 | |
| Person / Time | |
|---|---|
| Site: | Vanowen |
| Issue date: | 10/16/1979 |
| From: | Book H, Curtis J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | |
| Shared Package | |
| ML19253C522 | List: |
| References | |
| 50-094-79-01, 50-94-79-1, NUDOCS 7912050693 | |
| Download: ML19253C524 (2) | |
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U. S. NUCLEAR RF ATORY COMMISSION OFFICE OF INSPF ION AND ENFORCEMENT
REGION V
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Report No.
50-94/79-01 50-94 R-@
License No.
Priority
,:ategory Licensee:
Rockwell International Corporation 8900 DeSoto Avenue Canoga Park, California 91304 Facility Name:
l-77 Inspection at:
Canoga Park, CA Inspection condu ted:
September 4-6, 1979 Ins pec tors -
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Sumary:
Fuel Facility and Materials Safety Branch Inspectfan on September 4-6, 1979 (Report No. 50-94/79-01)
Areas Irispected: A routine inspection of the L-77 research reactor facilicy was conducted to establish the present physical status of. the facility and detemine the licensee's timetable related to their dismantling plan for the reactor. The inspection involved 3 inspection hours by one radiation specialist.
Results:
No items of noncompliance were identified.
1504 014 IE:V Form ?l9(1)
[O 7912050
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DETAILS 1.
Persons Contacted
- M. Remley, Manager, Health Safety and Radiation Services
- R. Tuttle, Manager, Radiation and Nuclear Safety
- H. Wieseneck, Director, Research and Engineering R. Garcia, Health Physicist
- indicates presence at exit interview 2.
Facility Status - Tour The inspector toured the L-77 facility with a licensee representative.
The main conponents of the L-77 reactor are intact and located in a laboratory room in the R&D building on the Rockwell International Canoga Park Site.
The room containing the reactor components is posted and locked. The fuel that had been removed from the reactor two years ago and stored at the facility has been removed and transferred to an SNM Storage Facility.
Intrusion alarms were removed and routine, manned surveillance of the facility was discontinued when the fuel was transferre 3.
Radiological Surveillance Routine smear and Nta-gamma radiation level surveys are performed in the facilityonaguarterlyschedule.
Smear counting results have been less than 50 dpm per 100 cm and radiation levels reported are in the background range.
Four film badges were located on the inside surface of the four walls and changed quarterly until they were discontinued in mid-1978. The results of the previous two quarters were zeros and the stored fuel had been removed in December of 1977.
Access is controlled by limited issue of keys to the locked facility.
There is no routine maintenance or janitorial service carried out at the facility.
The assigned Health Physicist performs a survey quarterly.
4.
Exit Interview The scope and results of the inspection were discussed with licensee manage-ment and staff representatives. The status of the L-77 was discussed. There is presently no time table for licensee action to dismantle, transfer or othenvise dispose of, the L-77 reactor. Any active program for dismantling would be performed according to plans presented to NRC in applict. tion for the NRC Dismantling Order. The licensee is aware of the necessity to have formal surveys and agreements approved by NRC prior to any release of the facility for non-licensed or unrestricted use.
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