ML20153B080
| ML20153B080 | |
| Person / Time | |
|---|---|
| Issue date: | 09/27/1978 |
| From: | Pagliaro J, Schultz W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML20153B074 | List: |
| References | |
| NUDOCS 7811290404 | |
| Download: ML20153B080 (6) | |
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U.S. NUCLEAR REGULATORY COMMISSION
, OFFICE OF INSPECTION AND ENFORCEMENT REGION III~
Report No. 78-01 License No. 34-07225-09 Priority I Category B Licensee: Picker Corporation 595_ Miner Road Cleveland, OH 44143 Inspection Conducted: August 23,.1978-Wid.Ge 9 - 7_? '76 Inspector: W.11. Schultz
'h M Approved By: '#J. A. Pagliaro, Chief '7-2I-77 Materials Radiological Protection Section 2 Inspection Summary Inspection on August _23, 1978 (R_eport No. 78-01)
. Areas Inspected: Organization and administrative control; health physics practices and proceduree; respiratory protection program; facility air sampling; personnel monitoring; air.and liquid effl.fents; waste shipments; area' surveys and license conditi6ns. The inspection involved 6 inspector-hours onsite by one NRC inspector.
Results: No items of noncompliance or deviations were identified.
.7811290S$
7 DETAILS I
- 1. Persons Contacted This was an unannounced reinspection'which was conducted on August 23, 1978. Information in this report was furnished by the following licen-see personnel:
Mr. Darwin Murray, Supervisor of Isotope Operations Mr. Clarence Pengov, RSO The Ohio State Health Department was notified of this inspection; however, no representative of that agency was present during the inspection.
2.. Management Control Systems There have been no changes in personnel since the last inspection; however, there have been several minor changes in the titles of responsible individuals. The President of Picker Corporation is still Mr. K. J. Carlson.. Mr. J.' B. Stickney is now Vice President and General Manager. Mr. R..W. Arndt is Manager of Isotope Oper-ations, and' Mr. Darwin Murray is still supervisor of Isotope Operations.
- 3. Use of Material, Facilities and Equipment The licensee uses byproduct material, primarily cobalt 60, procured under this license for the fabrication and distribution of tele-therapy sources to authorized recipients.
Records of the licensee's inventory were reviewed during this inspection and the inventory was found to be within the authorized possession limit specified in the license.
No items of noncompliance were identified.
- 4. Personnel Radiation Protection - External External radiation exposure is monitored by film badges supplied by the Radiation Detection Company. Whole body badges are processed on a weekly basis and wrist badges are processed once a month. In t addition, all personnel involved in the source fabrication wear dosimeters.
Past exposure histories (Form NRC-4) have been prepared for all personnel involved in the source fabrication program. Therefore,
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a all personnel are: permitted to receive whole body exposures of up to three rem per quarter. The film badge records.were reviewed for the period October 1, 1977 through July 1, 1978. During this period the maximum quarterly whole body exposure was 2,010 mrem and the maximum quarterly extremity exposure was 1,955 mrem. All personnel ex,asures for this period' were within the limits specified in 10 CFR 20.101(b) .
Dosimeter readings also agreed closely with exposures shown on the film badge processor's report.
The licensee has submitted in a timely manner the annual exposure report required by 10 CFR 20.407. The licensee has also submitted a termination report as required by 10 CFR 20.408 for Mr. Mark Rosumny.
Mr. Rosumny,formerly held the position of Radiation Safety Officer.
No items of noncompliance were identified.
- 5. Personnel Radiation Protection - Internal Internal radiation exposure is monitored by whole body counting.
Personnel engaged in the source fabrication program are given whole ocdy counts twice each year by Professor K. G. McNeill of Toronto, Canada. The most recent evaluation was made on April 18 and 19, 1978 and showed a maximum body burden of 21 nanocuries. The previous evaluation was made on October 17 and 18, 1977 and chowed a maximum body burden of 65 nanocuries. The 65 nanocurie maximum is less than 7% of the MPBB-for cobalt 60.
No items of noncompliance were identified.
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- 6. Surveys l
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- a. Restricted Areas.
2drect reading radiation surveys and smear type contamination surveys are performed in the restricted areas eve *y 31 days or less. The records were reviewed for the period sep; ember 15, i i
1977 (date of last inspection) through August 22, 1978. During this period the highest level of removable 5 ntamigation found during normal working periods was 8.5 x 10 dpm/ft . This contamination was found in the decontamination room which is a pre-entry area of the hot cel16 Also,2the licensee found a l contamination level of 2.26 x 10 dpm/ft in the same area during cleanup and waste removal from room.
5 2 The licensee has an action level of 5 x 10 dpm/ft and when- ,
ever the action level is exceeded the area is cleaned. A review I of the survey records showed that appropriate clean-up was made when the action level was exceeded. *1
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Direct reading radiation levels in restricted areas were up to 1 R/hr. However, these levels occurred in the area near the liquid waste storage tank in the basement and were not in an area which is routinely occupied by authorized personnel.
No items of noncompliance were identified.
. b. Unrestricted Areas Direct reading and smear type surveys are performed in unre-stricted areas every 14 days. The records were reviewed for the period September 15, 1977 through August 22, 1978.- During this period the removable contamination ranged from 0 dpm to 488 dpm. The licensee has an action point of 200 cpm at which
. point the area is decontaminated until the level is below the 200 cpm. This is equivalent to 2,439 dpm. Also, the direct reading surveys showed all radiation levels in unrestricted areas were less than 0.6 mR/hr.
4 No items of noncompliance were identified.
- 7. Air Sampling i l
- a. In-Plant Continuous fourteen day air samples are collected in the hot laboratory at two locations. The two sampling heads have not ,
been moved since the last inspection. Both heads are perma- l nently mounted. Filter papers are exchanged every fourteen days and evaluated. Although the air samplers are run con-tinuously the licensee is using a dilution time of only 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> to determine the concentration of activity released to restricted areas. The records were reviewed for the period .
January 4, 1978 through August 16, 1978. Duriggthisperiod themaximumconcentrationnotedwas2.g4x10 uCi/ml.
This -is well below the FTC a of 9 x 10 uCi/ml for insoluble cobalt 60.
There have been no changes in the air sampling program for pre-entry or entry into the hot cell since the last inspection.
Pre-entry samples are taken to determine " stay time" in the hot cell. In addition, samples are taken during actual entry into the hot cell. Records of samples taken since the last inspection showed the maximum 7 concentration found for pre-entry or entry was 8.51 x 10 uCi/ml. Calculations showed the maximum " stay time" was 24 minutes, however, the actual
" stay time" was only 2.5 minutes.
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f Mine Safety Appliance half face masks with Type H cannister filters are worn each time an individual enters the hot cell. l Although respirators are worn during all cell entries, no l allowance is made for the use of respirators.
- b. , Stack The stack effluent is monitored continuously and the filter paper which is used to sample the stack effluent is monitored ,
continuously by a GM tube connected to a ratemeter and a strip chart recorder. In addition, at 31 day intervals the filter
. paper is removed and counted in a well counter- The air flow through the stack sampler averages 5 cfm.- Surveys records were ,
reviewedsincethedateofthelagginspectionandthemaximum l uCi/gf. This is well below concentration noted was 3.3 x 10 the permissible concentration of 3 x 10~ uCi/ml for an unre-stricted area.
Uo items of noncompliance were identified.
- 8. Waste Disposal ,
- a. Liquid Liquid radioactive waste is disposed to the sewer in 50 gallon batches. Waste is dumped from the top of the holding tank into a 55 gallon drum. If the concentration in the drum is within permissible limits the 50 gallons of liquid is discharged into the sanitary sewer. During the period August 26, 1977 through December 31, 1977 a total of 128 mil 11 curies of cobalt 60 were disposed to the sanitary sewer. Also, during the period January:1, 1978 through August 23, 1978 a total of 37 milli-curies of cobalt 60 were disposed to the sanitary sewer. Records showed all releases were well below Part 20 limits.
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- b. Sobid The licensee disposes of solid radioactive waste by transferring it to a licensed waste disposal agency. There have been no shipments of radioactive waste since the last inspection.
No items of noncompliance were identified.
- 9. Posting and Labeling Posting and labeling was in accordance with applicable sections of 10 CFR 20,203. .'orm NRC-3 and a Notica of Workers were posted as required by 10 CFR 19.11.
f No items of noncompliance were identified.
- 10. Procedures for Receiving Packages of Radioactive !!aterials The licensee makes a~ complete survey of all packages containing radioactive material immediately upon receipt. A record is main-tained that shows all surveys have been made as required.
No items of noncompliance were identified.
- 11. License Conditions All license conditions were reviewed during the inspection and no problems were noted.
No items of noncompliance were identified.
- 12. Independent Measurements During the inspection direct reading radiation measurements were made at various locations throughout the licensee's facilities with one of the licensee's portable survey meters. It was noted all radiation levels were within regulatory limits.
No it.eas of noncompliance were identified.
- 13. Instrumentation and Equipment There have been no changes in the hot cell, remote handling devices, shielding capabilities, ventilation system, liquid retention system and instrumentation since the last inspection. All systems and components appeared to be adequate for a program of this scope.
- 14. Quality Assurance All scaled sources are leak tested by the licensee prior to transfer to a customer to assure that removable contamination does not exceed O.005 uCi.
No items of noncompliance were identified.
- 15. Management Interview l
At na conclusion of the inspection the inspection findings were r e' awed with Mr. Darwin Murray, Supervisor of Isotope Operations ano with Mr. Clarence Pengov, Radiation Safety Officer. They were informed that no items of noncompliance were noted during this l inspection.
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