IR 05000160/1989003
| ML20247Q774 | |
| Person / Time | |
|---|---|
| Site: | Neely Research Reactor |
| Issue date: | 09/18/1989 |
| From: | Bassett C, Mcalpine E NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20247Q771 | List: |
| References | |
| 50-160-89-03, IEIN-87-003, IEIN-87-022, IEIN-87-031, IEIN-88-008, IEIN-88-032, IEIN-88-100, IEIN-89-002, IEIN-89-009, IEIN-89-013, IEIN-89-027, IEIN-89-035, IEIN-89-037, NUDOCS 8909290094 | |
| Download: ML20247Q774 (8) | |
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UNITED STATES
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NUCLEAR REGULATORY COMMISSION
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REGION 81
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101 MARIETTA STREET.N.W.
ATLANTA, GEORGI A 30323
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SEP 191989 Report No.: 50-160/89-03 Licensee: Georgia Institute of Technology 225 North Avenue
. Atlanta, GA 30332-Docket Nos.: 50-160 License No.: R-97
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Facility Name: Georgia Institute of Technology Research Reactor
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Inspection Conducted: August 22-24, 1989 Inspector:
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_ C. H. Bassett, Radiation Specialist pate/ Signed Approved by:
8MF G.1_s o.,&
?.'i s e 9 E. J. McAlpine Chief
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Date Signed Radiation Safety Projects Section Nuclear Material Safety and Safeguards Branch Division of Radiation Safety and Safeguards SUMMARY Scope:
This -routine, unannounced inspection involved onsite review of radiation protection program activities including radiation control activities,
' transportation, and followup )and review of licensee actions concerning Inspector Followup Items (IFIs and NRC Information Notices (ins).
Results:
The staffing and current organizational structure were adequate to meet Technical. Specification (TS) requirements and to implement the licensee's radiation protection program.
The licensee has continued to make progress in improving the radiation protection program at the facility and demonstrated timely response to NRC initiatives and IFIs including improvements to procedures and methodologies for radiation control activities.
No weaknesses or violations were identified during the inspection.
One IFI was established concerning the development of a procedure governing the shipment of radioactive material.
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REPORT DETAILS 1.
Persons Contacted Licensee Employees R. Barrow, Research Scientist I W. Downs, Senior Reactor Operator
- R. Karam, Director, Neely Nuclear Research Center
- B. Revsin, Manager, Office of Radiation Safety J. Taylor, Senior Engineering Safety Assistant Other licensee employees contacted during this inspection included operators, technicians, and administrative personnel.
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- Attended exit interview 2.
Radiation Control (83743)
a.
Organization and Control TS Section 6.1 details the organizational structure, selected position responsibilities and the reporting chain for safety, safety p(olicy, and radiation control at the Georgia Tech Research Reactor GTRR) facility.
Through discussions with licensee personnel, the inspector verified that the facility management responsibilities and organizational structure met TS requirements.
The Manager of Radiation Safety (MORS) is responsible-for directing the' daily HP activities at the facility.
The MORS reports directly to the Director, Neely Nuclear Research Center (NNRC), who is responsible for overall operation of the facility.
If the need were to arise, the MORS may report any
'(R50)y or radiation control problem to the Radiation Safety Officerwho is safet and independent of the reactor facility staff..In addition, the MORS also has the option to report directly to the President of the University if problems or issues cannot be resolved at a lower level.
Permanent staff who are assigned routine Health Physics (HP) duties and assist the MORS in performing daily HP activities include a Senior Engineering Safety Assistant and a Research Scientist I.
In addition, part-time student employee technicians report to the MORS
'and perform designated HP duties. At the time of the inspection, two graduate and one undergraduate student technicians were employed at the facility.
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Posting-10 CFR 10.203 specifies the requirements for posting radiation areas, high radiation areas, and radioactive material areas.
During tours of the facility, the inspector noted the posting of radiation areas, high radiation areas, and radioactive material storage areas.
The postings were in accordance with the regulations.
No-violations or deviations were noted.
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Transportation 10 CFR 71.5 requires that each licensee who. transports licensed material outside theLconfines of its plant or other place of use comply with the applicable. requirements of the Department of Transportation (DOT) in 49 CFR Parts 170 through'189.
The inspector discussed the transportation of radioactive material with licensee representatives.
The licensee indicated that radioactive waste materials are transferred to the State License for shipping.
One radioactive waste shipment had been made since the last review by NRC of shipping records.
The inspector verified that. the waste had been transferred to the State License and that employees of the State had completed the shipment.
No problems. were noted with the shipping records but the inspector did note that no procedure existed to provide guidance for the shipment of radioactive material.
The licensee indicated that, in the past, personal expertise had been relied upon to ensure that the shipments were correct and made in accordance with the regulations.
The licensee acknowledged the value of having a procedure governing the shipment or radioactive material and agreed to evaluate the need for such a procedure. This will be tracked by the NRC as an inspector followup item (IFI) 50-160/89-03-01.
No violations or deviations were noted.
4.
Action on Previous Inspection Findings (92701, 92702)
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(Closed)
IFI 50-160/88-02-04:
Review Proposed Changes to Procedure 9038, Bioassay Program The inspector reviewed the changes that had been made to this procedure and concluded that sufficient technical guidance to conduct the appropriate analytical radiological measurements and evaluate the resultant data had been provided.
In addition, a new procedure, 9037 Tritium Determination in Urine, Rev 0, dated April 28, 1989, had been written to provide specific guidance concerning the presence of tritium in the urine.
The inspector also reviewed the minutes of the NSC for April 28, 1989, which outlined the review and approval of these two procedures.
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(Closed)' IFI 50-160/88-02-05:
Review Calibration Procedures and
. Records of the Kanne Chamber and GM Gas Monitor The inspector reviewed the calibrations that had been performed for the.Kanne Chamber and the Geiger-Mueller'(GM) Gas Monitor. The Kanne Chamber had been calibrated on January 24, 1989, and the GM Gas Monitor on January 19, 1989.
The calibrations were performed according to the procedures and appeared to adequate.
The inspector also reviewed the two procedures and the changes that had been.made.
Procedure 9010, Kanne. Chamber Calibration, Rev. 3, dated February 10, 1989, had been revised to include updated figures, appropriate references to the. figures, and updated operating instructions.
Procedure 9012, Operation and Calibration of the Gas Monitor, Rev. 3, dated April 28, 1989, had been revised to include the new sampling setup figures and associated operating instructions.
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'(Closed) IFI 50-160/88-02-06:
Review ' the Licensee's Commitment to Provide Additional Gamna Spectroscopy System Training to HP Personnel The inspector reviewed the training that had been provided to HP personnel-and the associated training records. Training on Procedure 9154, Operation and Calibration of the Gamma Analysis System for Effluent Monitoring, Rev.
1, dated October 14, 1983, had been performed of November 2, 1988.
Additional related training had been conducted on November 4 and 29, 1988.
The training was given to the Senior Engineering Safety (SES) Assistant to provide instruction for verifying equipment calibration, count reproducibility, and operation of the lithium-drifted germanium spectroscopy system and the sodium iodide spectroscopy system. The training appeared to be adequate.
The inspector also observed a demonstration of the operation of the germanium spectroscopy system by the SES Assistant.
No problems were noted, d.
(Closed) IFI 50-160/88-02-07:
Revise Procedures 9010 and 9015 so that Appropriate References Are Made to the Manufacturer's Technical Manual The inspector reviewed-the procedures, 9010, Kanne Chamber Calibration, Rev. 3, dated February 10,1989, and 9015, Cooling Water Gamma Monitor, Rev. 2, dated October 21, 1988.
Procedure 9010 had been revised previously and the appropriate references made to the manufacturer's technical manual added.
Procedure 9015 was changed during the period of the inspection and the inspector verified that the appropriate references were added, e.
(0 pen) IFI 50-160/88-02-08:
Evaluate the Present Stack Sample Collection Method and Consider the Use of Another Sample Collection Method L _ _ ___ _ _ _ ___
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The inspector reviewed the licensee's Procedure 9017, Stack Grab i
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Sample Analysis, Rev. 2, dated October 14, 1988..
The ' licensee indicated that the present stack sample collection method had been evaluated and that a new method was being considered..The new method would be very similar to a portion of the method used to calibrate
.the Kanne Chamber. lhis would involve the use of a 550 milliliter (ml)
bottle which would be attached to the sampling port in the exhaust duct.
The bottle would be flushed for a period of time and the-tubing used to connect the bottle with the duct would be pinched off to isolate the effluent in the bottle.
The stack gas sample would than be analyzed immediately.
The revision and implementation of Procedure 9017 will be reviewed during a subsequent inspection.
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(Closed) IFI 50-160/88-02-09:
Determine the Lower Limit of Detection (LLD) and Provide the Necessary Counting Time Guidance for the 500 ml Polyethylene Bottle Gas Geometry TS 3.5.a(1) specifies that the concentration of gross radioactivity, above -background, in liquid effluents discharged from the Reactor Building to the sanitary sewer shall not exceed 3 E-6 microcuries per m1, excluding tritium.
This establishes a minimum level of activity that must be detected by any analysis to meet the requirements of the TS.
Consequently, count times must be sufficient to meet this limit of detection.
The inspector reviewed Procedure 9155, Determination of Count Times Based on A Priori Lower Limit of Detection (LLDI, Rev. O, dated December 30, 1988'.
The licensee had written this procedure in response to this IFI and to establish a nominal detection limit under a standard set on conditions that would be applicable to gamma spectroscopy systems, bench top alpha / beta counting systems, and liquid scintillation counting systems.
The procedure provides a specific LLD value for the 550 m1 liquid geometry system and provides guidance on determining the LLD value for various other geometries as well. The procedure appeared to be adequate.
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(Closed) IFI 50-160/88-02-10:
Provide Guidance on the Minimum Counting Time for Analyzing Charcoal Cartridges to Etsure that LLDs Would Be Met As stated Paragraph 4.f above, Procedure 9155, Determination of Count Times Based on A Priori Lower Limit of Detection (LLD), Rcy. O, dated December 30, 1988, was developed by the licensee to provide such data as minimum counting times to ensure that the appropriate LLDs are met.
A minimum count time of 30 minutes was established for the charcoal cartridge geometry.
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(Closed) IFI 50-160/88-02-11:
Provide Guidance on the Minimum
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As stated in Paragraph 4.f above, Procedure 9155 was developed by the licensee for this purpose.
The minimum counting time needed to achieve the LLD for the 550 ml liquid effluent geometry was established at 30 minutes.
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(0 pen) IFI 50-160/88-02-12:
Specify a Dead Time Limit for the Multichannel Analyzer in Procedure 9154 The licensee indicated.that this procedure, 9154, Operation and Calibration of the Gamma Analysis System for Effluent Monitoring, Rev. 1, dated October 14, 1988, had not been reviewed or revised to date. The licensee agreed that the issue of specifying a " dead time" limit for the multichannel analyzer would be considered and added to
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the procedure if necessary.
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(Closed) Unresolved Item (URI) 50-160/89-01-01:
Reevaluate the Appropriate Gaseous Effluent Release Data to Substantiate the Annual Radiation Dose Estimates Since 1985 The licensee ; had reevaluated the appropriate gaseous effluent releases and direct radiation exposure data since 1985.
All years'
exposure data were evaluated by taking the average dose received at 29 of the 30 environmental film badge locations around the perimeter of the facility.
One film badge, location No. 9, had been excluded from the average due to the high background in the area as a result of the radioactive material stored in the storage " barn" or shed located southeast of the Reactor Building and in the southeast corner of the restricted area of the facility.
From a review of these data, the licensee concluded that an exposure of less than 10 millirem per year had resulted from direct radiation and gaseous effluent. -One revision to an annual report was issued for 1986 as a result of this reevaluation.
The licensee indicated that the crivironmental monitoring procedures will be revised following a reevaluation of all doses recorded for the past 10 years. After the reevaluation of those data, a conclusion concerning the adequacy of the monitoring program would be made and changes instituted as necessary.
The inspector reviewed the gaseous eftluent and direct radiation data since 1985.
The licensee's conclusions appeared to be adequate and substantiated by the data.
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(Closed) IFI 50-160/89-01-02:
Followup on a Commitment Made to the NRC to Remove Byproduct Material from a Shed Located Near the Southeast (SE) Corner of the Restricted Area Perimeter Fence.
The licensee indicated that this material had been shipped to a burial ground after being transferred to the State License (see Paragraph 3).
The inspector reviewed the shipping papers of the radioactive material shipment made after the waste material had been
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transferred' ' to the State by the licensee.
The licensee also indicated that sources, which had been stored in the shed, were taken to the Reactor Building and placed in a shielded storage location in the basement level of the building.
This had reduced the radiation levels _along the fence in the southeast corner of the restricted area.
of' the facility 'from approximately 40 microrem per hour to 10 microrem per hour above background.
5.
Followup on Information Notices (92717)
The inspector determined that the following NRC Information Notices (ins)
had been' received by-the licensee, reviewed for applicability, and distributed to the appropriate personnel.
IN 87-03 Segregation of. Hazardous and Low-Level Radioactive Wastes, dated January.15, 1987.
IN 87-?2 Operator Licensing Requalification Examinations at Nonpower
' Reactors, dated May 22, 1987.
IN 87-31 Blocking, Bracing, and Securing of Radioactive Materials Packages in Transportation, dated July 10, 1987.
IN 88-08 Chemical Reactions with Radioactive Waste : solidification Agents, dated March.14, 1988.
L IN 88-32 Prompt Reporting to NRC of Significant Incidents Involving (
Radioactive Material, dated May 25, 1988.
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IN 88-100 Memorandum of Understanding Between NRC and OSHA Relating to NRC-licensed Facilities (53 FR 43950, October 31,1988), dated December 23, 1988.
IN 89-02 Criminal Prosecution of Licensee's Former President for Intentional Safety Violations, dated January 9,1989.
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l IN 89-09 Credit for Control Rods Without Scram Capability in the Calculation of the Shutdown Margin, dated January 26, 1989.
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IN 89-13 Alternative Waste Management Procedures in Case of Denial of Access to Low-Level Waste Disposal Sites, dated February 8,1989.
IN 89-27 Limitations on the Use of Waste Forms and High Integrity Containers for the Disposal of Low-Level Radioactive Waste, dated March 8, 1989.
IN 89-35 Loss and Theft of Unsecured Licensed Material, dated March 30, 1989.
IN 89-37 Proposed Amendments to 40 CFR Part 61, Air Emission Standards for Radionuclides, dated April 4,1989.
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Exit Interview (30703)
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The inspection scope and results were summarized on August 24, 1989, with those persons indicated in Paragraph I above.
The adequacy of the licensee's organization and staffing was discussed as was the licensee's transportation of radioactive material program.
Actions taken by the licensee in response to the various IFIs and the URI were also discussed.
No apparent violations or deviations were noted. One IFI was established concerning the development of a procedure governing the shipment of radioactive materials.
Item Number Description and Reference 50-16089-03-01 IFI - Followup the development of a procedure for the shipment of radioactive materials (Paragraph 3).
Licensee management was informed that the URI and eight of the ten IFIs discussed in Paragraph 4 were closed during this inspection.
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