ML20214Q309

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Closeout Insp Rept 70-0168/87-01 on 870311.No Violations Noted.Major Areas Inspected:Interviews W/Personnel & Independent Measurements
ML20214Q309
Person / Time
Site: 07000168
Issue date: 05/14/1987
From: Taylor M, Jason White
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:
Shared Package
ML20214Q286 List:
References
70-0168-87-01, 70-168-87-1, NUDOCS 8706040339
Download: ML20214Q309 (4)


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U.S. NUCLEAR REGULATORY COMMISSION REGION I Report No. 070-00168/87-01 Docket No. 070-00168 License No. SNM-188 Priori ty 3 Category E Licensee: Nuclide Corporation Nuclide Analysis Associates 642 East College Avenue State College, Pennsylvania 16801 Facility Name: Nuclide Corporation Inspection At: 642 East College Avenue, State College, Pennsylvania 1155 Zion Road, BelleFonte, Pennsylvania Inspection Conducted: March 11, 1987 Inspector- s ce ar # bue% 'J!N!f7 garMarlene J. Taylor date Health fhysicist Approved by , Rescur/ Ya

,,brJohn R. White,' Chief n t? ,,

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date Nuclear Materials Safety Section C Inspection Summary: Inspection on March 11, 1987, (Report No. (070-00168/

87-01)

Areas Inspected: Special, announced closeout inspection including interviews with personnel and independent measurements.

Results: No violations were identified. The facility meets NRC guidelines for release for unrestricted use.

8706040339 870520

{DR ADOCK 07000168 PDR

D DETAILS

1. Persons Contacted Michael Michlik, Production Manager Karl Farringer, Automation Engineer
  • Dr. Leonard Herzog, President
  • Charles lleyman, President, M.A.A.S., Inc.
  • Present at exit interview

2. Background

Nuclide Corporation was authorized by NRC License No. SNM-188 to possess uranium (enriched) in any form for the testing and calibration of mass spectrometers. License No. SNM-188 expired on September 30, 1984. The licensee is in the process of applying for a new license and is moving their operation from 642 East College Avenue, State College, Pennsylvania, to 1155 Zion Road, Bellefonte, Pennsylvania. The licensee is also chang-ing its name to M.A.A.S. Inc.

3. Observations and Measurements i

The inspector toured the licensee's facility and surveyed for loose sur-face contamination and direct radiation. Contamination wipes were counted usinj a Tennelec Model LB 5100 gas flow proportional counter at Region I.

The results and locations of the wipes are shown in Table 1. Radiation surveys were performed using an Ludlum Model 14C survey meter with a thin end window probe (s/n 44066) sensitive to beta and gamma radiation, and was calibrated November 24, 1986. No radiation levels above instrument background were detected at the State College facility. The results of all the measurements for the State College Facility indicate that the facility meets NRC guidelines for release of a facility for unrestricted use.

The inspector found the licensed material located at the Bellefonte facility to be properly posted and secured. Radiation surveys were conducted at the Bel.lefonte facility, the results of which appear in .

Table 2. I

4. Exit Interview The results of the survey were reviewed with licensee representatives identified in Paragraph 1. Licensee representatives indicated that a license application covering the material licensed under License No. SNM-188 would be submitted by March 31, 1986.

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Report No. 070-00168/87-01 Table 1 Wipe tests at 642 East College Avenue, State College, Pennsylvania I

6 feet _ _

1 2 3 4 5 6 10 feet l 7 8 9 i '

gross alpha gross beta

1. < LLD < LLD I 2. < LLD < LLD l 3. < LLD < LLD 4.

< LLD < LLD

5. < LLD < LLD
6. < LLD < LLD
7. < LLD < LLD
8. < LLD < LLD
9. < LLD < LLD l

The results in this table are in units of disintegrations per minute (dpm) l measured on the wipes which covered 100 square centimeters each. At the time l of the measurement, the background count was 0.18 cpm for the gross alpha and 1.19 cpm for the gross beta and the efficiency of the detector was 0.229 for gross alpha and 0.260 for gross beta. The LLD (Lower Limit of Detection) is 9 dpm for gross alpha and the LLD is 20 dpm for gross beta. The LLD was cal-culated using the following formula.

LLD = 4.66 47t e

l B= Background count rate t= Counting time e= Efficiency

Conclusion:

No removable radioactive contamination, in excess of NRC guidelines for release of a facility for unrestricted use, was detected in this facility.

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-D Report No. 070-00168/87-01 Table 2 15 Feet l

l 14 mR (contact) 0.2 mR/hr.

0.2 mR/hr. 0.3 mR/hr. 12 feet 0.05 mR/hr. i 0.05 mR/hr.

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  • box containing sealed sources 1

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