ML19290E827
| ML19290E827 | |
| Person / Time | |
|---|---|
| Site: | 05000433 |
| Issue date: | 02/01/1980 |
| From: | Book H, Curtis J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | |
| Shared Package | |
| ML19290E826 | List: |
| References | |
| 50-433-79-03, 50-433-79-3, NUDOCS 8003170095 | |
| Download: ML19290E827 (4) | |
Text
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U. S. NUCLEAR REGUL\\ TORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT REGION V Report No.79-03 Docket No.50-433 License No. R-124 Safeguards Group Licensee: University of California, Santa Barbara Santa Barbara, California 93106 Facility Name: L-77 Research Reactor Inspection at: UC Santa Barbara c
.s Inspection conducted:
December 17-19, 1979 61 td 2
h Inspectors:
/Dat6 Signed J. [Curtis, Radiation Specialist Date Signed Date Signed g
6
/
O e
Approved By:
s H. E. Book, Chief, Fuel Facilities and Date Signed flaterials Safety Branch g
Inspection on December 17-19,1979 (Report tio. 50;4T3779-03)-
Areas Inspected: Routine, unannounced inspection of Radiation and En-vironmental Protection programs of the L-77,10 watt research reactor (Type H).
The inspection included tours of the facility, a radiation survey of levels inside and adjacent to the facility and exanination of records, reports and logs pertaining to radiation safety. TF-inspection involved seventeen hours on-site by one inspector.
Results:
No items of noncompliance or aeviations were identified.
RV For:a 219 (2) 80031700gg.
DETAILS 1.
Persons Contacted
- Prof. A. E. Profio, Reactor Director
- Mr. F. E. Gallagher, Radiation Safety Officer Mr. D. Ringwald, Electronics Technician / Reactor Operator Trainee
- Present at the exit interview.
2.
General Operations - Tour and Surveys The reactor was shut down at the time of the inspection and was not in routine use, except for weekly cperational checks, during this scholastic quarter. Most utilization of the reactor occurs during the spring quar-ter, flarch to June, when laboratory courses which use the reactor and adjacent facilities are scheduled.
The inspector toured the facility and conducted independent measurement surveys of radiation and contanination levels in and adjacent to the facil i ty.
Radiation measurements were taken with fiRC Region V Eberline flicro R-meter PRf t-7 Serial #247 due for next calibration 12/22/79.
General dose rates measured three feet above the floor and within the reactor facility enclosure were generally 0.01 to 0.025 mR/hr.
The maximum reading was 0.5 mR/hr.
Sealed sources, possessed under a California State license were stored in the roon adjacent to this area. A contam-ination survey was performed.
Swipe samples of floor and work surfaces in and around the facility were counted in the flRC Region V fluclecr
!!easurements Corporation Counter PC-55.
Counting results indicated that no removable contamination was detected on the swipe samples.
flo items of noncompliance or deviations were identified.
3.
Radiation Protection Program Records, procedures and portions of log books related to radiological safety were exanined and discussed with licensee representatives.
Doc-uments examined included the Reactor Operations Manual and Emergency Plan; records of reactor startup and use, radiation surveys and personnel exposure reports.
There was no evidence of unusual or unexpected ra-diation levels related to reactor operation.
Personnel exposures, based on thermoluminescent dosimeters (TLD) results, are reported for persons who enter the reactor facility on a routire basis. Most persons monitored for exposure are users of an accelerator and or work with state licensed radioactive materials. The licensee representative indicated that the exposures reported were probably re-lated to use of the accelerator, but precise determination of the source of exposure was limited.
Personnel dosimetry for staff and class par-ticipants is issued on a quarterly basis.
Exposures reported were in the 0 to 150 mRen per quarter range.
2 Area dosimeters are placed on the four inside walls of the building in which the reactor facility is located and are changed monthly.
Levels reported for these dosimeters are in the 0 to 180 mrem per month range with the highest levels reported for a dosineter placed on the wall within 10 feet of the the radioactive source storage area.
Other areas are in the 0 to 45 mrem per month range.
Dosimeter results for students in the fluclear Engineering Laboratory Courses were in the 30 to 110 mrem / quarter range.
Discussion of these results with the licensee representatives led to the conclusion that a portion of this reported exposure might be attributed to the storage location of students dosimeters when they were not being worn. Better control methods for dosimeters during "non-use" periods will be inves-tigated by the licensee.
Visitors to the reactor facility are required to sign in on a visitors log located on a table at the entrance.
At this point dosimeters are issued to individuals or representatives of groups.
There were no sig-nificant exposures reported for visitors.
Entries in the visitors log during tour signups were, on some occasions, frivolous and in sorre in-stances obviously fictitious.
Since this log constitutes a record for personnel dosimetry and access control, the inspector noted the obser-vation and called it to the attention of the licensee representatives during the exit interview.
f4r. Frank Gallagher, the Campus Radiation Safety Officer (RS0), is a member of the Reactor Operations Committee. This committee or a sub-committee performs quarterly surveillance of reactor operations via an audit of logs and records.
The Environmental Health and Safety Office (EH&S) performs semi-annual radiation and contamination surveys of the reactor facility, counts and evaluates Constant Air Monitor (CAM) samples from the reactor room, and performs an annual in-depth evaluation of state licensed " user" programs associated with use of reactor activated samples.
Samples of reports of these surveillance activities were ex-amined and discussed with the licensee representatives.
f!o unusual or unexpected results associated with reactor operations were identified.
flo items of noncompliance or deviations were identified.
4.
Review of Licensee Response to Bulletin 79-19 The licensee received IE Bulletin 79-19 and it was referred to the EH&S office and the RSO for response.
Licensee representatives indicated that wastes generated by flRC licensed reactor operations are very small and no liquid wastes are generated. The estimated annual total of one
,.. to five micro curies of short halflife radioactivity generated by the reactor is co-mingled with other wastes generated under state license and disposed of by transfer to a state licensed waste collection contractor.
In response to receipt of Bulletin 79-19 the RSO posted and re-circulated an internal Radiation Safety Bulletin containing procedures for waste collection, storage and handling by UC Santa Barbara radioactive mater-ial users.
No items of noncompliance or deviations were identified.
5.
Licensee Statistical Summary Reoort of Personnel Monitoring Results The licensee submitted a statistical summary of 1978 personnel monitor-ing results pursuant to the requirements of 10CFR 20.407, September 1978.
A copy of the sumnary report and cover letter were examined.
fio items of noncompliance or deviations were identified.
6.
Exit Interview At the close of the inspection an exit interview was held with Professor Profio and f1r. F. Gallagher. The scope and findings of the inspection were reviewed and discussed.
No items of noncompliance or deviations were identified.