IR 05000186/1997201

Corrected Page 1 of Details to Insp Rept 50-186/97-201 on 971103-07.Violations Noted

ML20198N196
Person / Time
Site:	University of Missouri-Columbia
Issue date:	01/09/1998
From:	NRC (Affiliation Not Assigned)
To:
Shared Package
ML20198N162	List: ML20198N156 ML20198N175 ML20198N196
References
50-186-97-201, NUDOCS 9801200290
Download: ML20198N196 (1)

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DETAILS 1.0 Radiation Control Insoection Scone (83743)

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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 Qbgervations and Findinas The inspector accompan!ed a health physics technician during weekly radiation instrumentation checks. All procedures and actions appeared appropriat 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 specifie 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 roo The licensee could not identify a cause for overlooking the Pu 239 sourc 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 require '

Tht majority of postings, labeling, and surveys met regulatory requirements as observed on the tour of the reactor laborator 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 poste ,vt09 PDR ADOCK 05000186 G pg

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