ML20198N196
| ML20198N196 | |
| Person / Time | |
|---|---|
| Site: | University of Missouri-Columbia |
| Issue date: | 01/09/1998 |
| From: | NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20198N162 | List: |
| References | |
| 50-186-97-201, NUDOCS 9801200290 | |
| Download: ML20198N196 (1) | |
See also: IR 05000186/1997201
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DETAILS
1.0 Radiation Control
a.
Insoection Scone (83743)
.
The inspector reviewed the radiation protectior program to determine compliance
with the requirernents m 10 CFR Part 20 and T.S. 3.4, 3.6, 3.7, 5.1, 5.4, and
6.1.
b.
Qbgervations and Findinas
The inspector accompan!ed a health physics technician during weekly radiation
instrumentation checks. All procedures and actions appeared appropriate.
The inspector noted that calibration sources used by the technician were ceing
stored in a room near the front lobby which was not posted. Upon comparing the
source strengths with the activity levels in Appendix C of Part 20 the inspector
determined that a Plutonium 239 source was 157 times the amount specified.
10 CFR 20.1902(e) requires that licensed materialin excess of ten times the
amount of such material specified in Appendix C must be stored in areas that are
conspicuously posted with signs that include the radiation symbol and the words
"OAUTION, RADIOACTIVE MATERIAL (S)" or DANGER, RADIOACTIVE
MATERIAL (S)." Failure to post the radioactiva materials storage area is a violation
(50-186/97201-01).
The licensee immediately pos9d the area appropriately. No other similar
circumstances were identifle The licensee had previously conducted an
inventory of all sources and had stored the larger ones together in a posted room.
The licensee could not identify a cause for overlooking the Pu 239 source.
Access to the reactor bridge was being controlled due to a minor P-32
contamination event that was discovered on October 7 of this year. A single
sample encapsulated in welded alur. .aum had breached at the weld after several
weeks of irradiation. Similar failures of encapsulation were rare. The inspector
observed reactor staff taking precautions to minimize any possible contamination
spread. Contamination the lircensee had identliied was only slightly elevated
above administrative limits
Area radiation monitors and portable lastruments were calibrated as required.
'
Tht majority of postings, labeling, and surveys met regulatory requirements as
observed on the tour of the reactor laboratory.
A representative samp'e of areas were surveyed . * the inspector for radiation
levels including the beam port floor, hot cell, wastt, areas, laundry, anu labs. No
unexpected levels were identified. Some areas were temporarily elevated as the
licensee had recently moved waste barrels out from areas that are inaccessible
during operation in preparation for shipping. These areas were acceptably posted.
9801200290 91,vt09
ADOCK 05000186
G
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