IR 05000094/1982001
| ML20041C937 | |
| Person / Time | |
|---|---|
| Site: | Vanowen |
| Issue date: | 02/12/1982 |
| From: | Book H, Garcia E, Wenslawski F NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | |
| Shared Package | |
| ML20041C926 | List: |
| References | |
| 50-094-82-01, 50-94-82-1, NUDOCS 8203020677 | |
| Download: ML20041C937 (4) | |
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U. S. UUCLEAR RECUL\\ TORY ComiISSION
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PIGION V
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Report No. 50-94/82-01 Docket No. 50-94 License No. R-40 Safeguards Group Licensee:
Rockwell International Corocration 8900 De Soto Avenue Canoaa Park, California 91304 Facility Name: L-77 Research Reactor Inspection at: Canoaa Park. California Inspection condu ed : January 22. 1982, Telephone calls on January 25 and 28,1982.
Inspector :
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E. M. Garcia, Radiation Specialist Da'te signed Date Signed
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Date Signed
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Approved by:
um F. Wensl wski, Chief Ddte S'igned Reac agat Pro ction Section
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Approved by:
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H. E. Book', Citfef
~ Date Signed Radiological Safety Branch
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Inspection on January 22, 1982 and telephone calls on January 25 and 28, 1982.
Areas Inspected:
Special closeout, announced inspection by a regional based inspector of the L-77 facility to verify proper disposition of contaminated components, to verify that the facility had been decontaminated to levels prescribed in the dismantling order, to assure the facility will present no substantial radiological hazard to future occupants, and to provide a basis for certifying the above to NRR for the purpose of terminating the license. The inspection included review of records, interviews with personnel, and independent surveys of the facility.
The inspection involved 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> onsite by one NRC inspector.
Results: The inspection confirmed the licensee's findings of January 6, 1982, Report of Radiation Survey of the L-77 Reactor Facility in Suppor_t of Request to Terminate Facility License R-40 and to Release the Facility N.-.
for Unrestricted Use Docket 50-94.
RV Form 219 (2)
8203020677'820216
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PDR ADOCK 05000094 Q
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DETAILS 1.
Persons Contacted
- R. G. Jones, Vice President, Finance and Administration
- R. J. Tuttle, Manager, Radiation and Nuclear Safety Q. Koon, Radiation Instrumentation Engineer, Quality Assurance Department R. R. Garcia, Health Phy:icir'
C. Philpott, Portable Instruments Records Supervisor
- Indicates those individuals attending the exit interview.
Also Mr. D. L. Speed, Health Physicist, with the State of California Department of Health Services, Radiologic Health Section accompanied and assisted during the inspection and was present at the exit interview.
2.
The Facility The L-77 reactor facility, consisted of the reactor room, the reactor console room, and the laboratory room. The wall separating the console room and laboratory has been removed as well as all the furnishings and part of the wall to the reactor room.
The floor tile in the reactor room and console room have also been removed. The facility thus is an unfurnished room of about 70 by 46 feet with partial partitions.
Water, gas, sewer lines and electrical conduits are located inside
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the room on the outside walls and are accessible for surveys.
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3.
Licensee's Records-
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The inspector reviewed records of the surveys conducted by the licensee and the calibration records of the instruments used. The records indicate that the licensee divided the walls and floors of the reactor roomandconsoleroomingectionsapproximatelyonemeterbyonemeter and as many as six 100 cm smears were taken in each section.
Smears'were.also taken of the ceiling, exposed pipes, light fixtures, manholes, drains, and ventilation components. All smears were counted on an NMC Automatic Counting System proportional counter. The results oftheseanalysisindicatethatcontaminationleyelswerelessthan 20 dpm/100 cm alpha and less than 50 dpm/100 cm beta-gamma.
The records also indicate that surveys for fixed and induced contamination were performed.
These surveys were conducted using:
(1) a Ludlum Model 125 micro-r-meter, a Technical Associates PUG-1 with a P-11 GM
" pancake" probe, and a Technical Associates FM-5 with a PAS-9 alpha scintillation probe.
No residual activity above background was detected.
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Certain mino'r inconsistencies between the licensee's January 6, 1982 survey. report to the NRC and the records were noted.
The report states that the laboratory room (416-55) "has been cleaned and surveyed" and that a Technical Associates CP-7' ion chamber as well as the instruments mentioned above had been used to measure residual activity in all rooms.
No surveys of the laboratory room or records of the use of the CP-7 instrument were available. The. licensee's representative stated that the laboratory room had been converted into a classroom about 1972.
At that time a survey had been conducted. The licensee's survey records only go back to 1974.
Regarding the surveys with the CP-7, the licensee's representative stated that the CP-7 was used some time after the surveys with the micro-r-meter, GM and alpha scintillation instruments had been conducted.
Therefore, the results of CP-7 surveys were not noted on the records for the surveys with the other instruments. These two inconsistencies are insignificant, since extensive surveys by the licensee in adjacent rooms, and the inspectors surveys (see paragraph 4) failed to identify any contamination.
The inspector verified that the instruments identified by the licensee's representative as being used for the surveys were within the specified calibration dates and that the calibrations performed were traceable to NBS standards.
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Inspector Surveys The inspector performed surveys of all three rooms for removable contamination andfixedorinducedcogtamination. All48smearteststagenindicate less than 20 dpm/100 cm alpha and less than 50 dpm/100 cm beta-gamma.
The instrument used for this analysis was an NMC PC-55 serial #77-2712-05
calibrated on January 27, 1982, the date the smears were counted.
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Measurements of direct radiation identified no residual activity above background.
The following NRC instruments were used:
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Eberline PRM-5-32 serial number 2983 calibrated on January 21, 1982 using a HP 210 GM pancake probe (background was approximately 75 cpm), and an AC03 alpha scintillation probe (back much less than half the lowest scale mark of 50 cpm) ground was
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Eberline PRM-7 micro-r-meter / serial number 247 due for calibration March 30, 1982 (background about 10 ur/hr).
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Telephone Calls During the January 1982 site visit the inspector identified that four floor conduits left the reactor room but only two ended in the console room.
During a telephone conversation on January 25, 1982 the inspector requested that the licensee identify where the two other conduits terminated and that the area be surveyed.
On January 28, 1982 during a telephone conversation the licensee informed the inspector that the conduits
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-3-i terminated in the laboratory room, and that they appeared never to been used. The licensee'further stated that surveys of the conduits
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for removable contamination and fixed contamination failed to identify any radioactivity above background.
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6.
Exit Interview s
. The inspector met with the individuals noted in paragraph 1 at the close of the inspection. The inspector reviewed the scope and findings of the inspection and indicated that based upon the surveys performed, records reviewed and interviews conducted, Region V would recommend that the license be terminated.
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