ML20235N641

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Insp Rept 70-0734/87-11 on 870818.No Violations Noted.Major Areas Inspected:Decontamination Confirmatory Survey of Portions of Experimental Bldg in Which NRC Licensed Activities (Triga Fuel Fabrication) Conducted
ML20235N641
Person / Time
Site: 07000734
Issue date: 10/01/1987
From: Jonathan Montgomery, Pang J, Thomas R
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V)
To:
Shared Package
ML20235N617 List:
References
70-0734-87-11, 70-734-87-11, NUDOCS 8710070017
Download: ML20235N641 (9)
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U. S. NUCLEAR REGULATORY COMMISSION t, REGION V. Repoht No.070-734/87-11 ~ Docket No. 70-734 License No. SNM-636 Safeguards Group'1 Licencee: G.A. Technologies, Inc. P. O.. Box 85608 San Diogo, California 92138-Facility Wa.me: Same Inspection at: Same Inspection Conducted: August 18, 1987 Inspectors: M'* Qer-) lo't - 27 R..D. Thomas, Chief Date Signed Nuclear Materials Safety Section T.f:.9 3-gog J. F. Pang,VRadiation Specialist Date Signed Approved by: 871h /o///77 j/ J. L. Montgomery, Chief Date Signed Nuclear Materials Safety and Safeguards Branch Summary: Inspection on August 18, 1987 (Report No. 70-734/87-11) A decontamination confirmatory survey was conducted by NRC inspectors.of the portions of the Experimental Building (E Building) in which NRC licensed activities (TRIGA fuel fabrication) had been conducted. The survey results-indicate that the NRC licensed portions have been satisfactorily decontaminated by the licensee. The area is acceptable for release to unrestricted use. 8710070017 871001 PDR ADOCK 07000734 C PDR

't (p ~. DETAILS 1. Persons Contacted Ben Kapel,. Material License Reviewer, State of California L. R. Quintana, Supervisor, Health Physics K. Wong, Senior Health Physicist,. State of California l 2. Introduction A. final report by GA-Technologies, Inc. dated July 28, 1987 on the decontamination of the Experimental Building indicated that the building had been decontaminated to levels below the release limits'and was acceptable for release-to unrestricted'use. Activities conducted.within the building were authorized by State and NRC licenses. This report l covers only the areas under the NRC license for TRIGA fuel fabrication. A decontamination confirmatory survey of the portions of the Experimental 1' Building where NRC licensed materials had been used was conducted on August 18, 1987. On the same day, State of California inspectors were conducting decontamination confirmatory surveys of portions of the [ building where state licensed materials had been used. The area in the northwest corner of the building, which was a section of the old fuel fabrication, was not included in this confirmatory survey. This area now contains office spaces and the telecommunications group. This area will be surveyed at some fnture date. Based upon the results of the combined confirmatory surveys, the State of California will release the entire area if the'results indicate that the areas can be released for unrestricted use. 3. Procedure Radiation surveys were conducted in those portions of the Experimental Building where the TRIGA fuel fabrication had been done. The areas surveyed included the floor areas of the second and third floor mezzanines and appropriate floor area sections of the main floor (Figure 1). It was noted that the licensee had scabbled much of the floor areas on the main floor and had dug trenches to effect the removal of drain pipes. The ditches were also surveyed if they were located within the areas where work with NRC licensed materials had been conducted. A 100% gamma survey was conducted on the floor areas with Eberline PRM-7's Serial Numbers 247 and 510 calibrated on 7-21-87 and 7-27-87 respectively. The instruments were held approximately one to two inches from the floor surfaces. Selected areas of the walls, pipings and conduits located in the areas where work with NRC licensed materials had been conducted were also included in the survey. Contamination surveys were conducted of selected areas within the same above mentioned locations using Eberline E-520's, Serial Numbers 1747 and 2776 calibrated on 6-11-87 and 7-10-87 respectively. The E-520s were equipped with Model HP-260 pancake GM

2 L detectors. 'Also, 14 wipe samples were collected and analyzed (Table 1). The instrument used.to analyze the wipes is the NRC Region V:Tennelec-Model,LB5100 low background system. Three soil samples were collected from selected areas of the ditches which had been dug in the floor areas. A drain pipe located above the floor along the north wall in the area was cut open and the' scrapings from the pi~pe interior were collected. These samples were analyzed at-the Radiological and Environmental Sciences Laboratory of the U.Se Department'of Energy Idaho Operations Office (see Tables 2 to 5). 4. Discussion and Findings Radiation surveys conducted indicated the_ presence of background levels ranging from 15-30 pR/hr. The range is attributed to natural background contributions from the varying amounts of concrete present. Contamination surveys conducted indicated the presence of two contaminated spots of approximately 15 cm2 each. One spot located next to a wall support on the west wall in the solvent extraction area had a beta gamma contamination level of approximately 6000 dpm. Another spot-located adjacent to a drain pipe on the ncrth west wall of the building had e beta gamma contamination level of approximately 3000 dpm. The contamination in each location was removed by the licensee. A resurvey by the NRC inspector indicated that the contamination had been removed. Wipes collected from 14 locations did not indicate the presence of any significant removable contamination. See Table 1 for the results. Soil samples collected from three trench locations indicated the presence of less than 1 pCi U-235/g soil in two of the samples and nothing detectable in the third sample (Table 2, 3, 4). These results are well within the NRC guidelines criteria of 30 pCi U-235/g soil for the most insoluble form of U-235. Analyses of the scrapings from the drain pipe also _ indicated less than 1 pCi U-235/g (Table 5). 5. Conclusions The portion of the Experimental Building which was examined during the confirmatory survey had been satisfactorily decontaminated by the licensee and is acceptable for release to unrestricted use in accordance with NRC guidelines.

3 A TABLE 1 U. S. Nuclear Regulatory Commission Region V Independent Survey Data Licensee: G.A. Technologies Date: 8-18-87 By: J. Frank Pang and R. D. Thomas Contamination Wipes Sample (Alpha) (Beta / Gamma) Number Location dpm dpm 1 On top of switch box 6.6 7.7 2 Behind pipe near floor 7.1 17 3 Drain pipe 94 261 4 Behind wall bracket 2.0 4.3 5 Inside channel bracket 10 9.8 5 Inside channel bracket-heao level 13 23 l 7 Inside breaker box '5 21 8 On top of light fixture 14 14 9 Top of switch box

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