ML20207S092
| ML20207S092 | |
| Person / Time | |
|---|---|
| Site: | 05000192 |
| Issue date: | 03/09/1987 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20207S079 | List: |
| References | |
| NUDOCS 8703180519 | |
| Download: ML20207S092 (8) | |
Text
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[QS Kt Cs#'c, UNITED STATES
[ " -,y [,g NUCLEAR REGULATORY COMMISSION W ASHINGTON, D. C. 20555 g
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y SAFETY EVALUATION BY THE OFFICE OF hl' CLEAR REACTOR REGULATION SUPPORTING ORDER AUTHORIZING DISPANTLING OF FACILITY AND DISPOSITION OF COMPONENT PARTS FOR FACILITY OPERATING LICENSE NO. P-92 THE UNIVERSITY OF TEXAS AT AUSTIN THE UNIVERSITY OF TEXAS TRIGA REACTOR DOCKET NO. 50-192
1.0 INTRODUCTION
By application dated May 3,1985, as supplemented, the University of Texas at Austin (UT) requested authorization to decer.taminate and dismantle the 250 kW TRIGA reactor facility located on the UT campus in Austin, Texas. The reactor is still operating and will remain in intermittent operation until approximately May 1988, when it will be permanently shut down.
Following a suitable decay period, the fuel will be transferred to a new UT TRIGA research reactor facility to be constructed at the UT energy research facility approximately 7 miles from the UT-Austin campus. After the fuel is transferred, the dismantling and decommissioning program will be initiated.
The reactor was originally licensed in 1963 for operation at 10 kW(t).
The license was amended in 1968 for operation at 250 kW(t), which is the current operating power level. Total reactor usage from 1965-1983 was approximately 2000 hours0.0231 days <br />0.556 hours <br />0.00331 weeks <br />7.61e-4 months <br />, with an integrated burnup of about 20 MW-days.
Estimated total burnup until pennanent reactor shutdown is approximately 22-24 MW-days.
2.0 FACILITY DESCRIPTION The UT TRIGA reactor is located on the first floor of Taylor Hall, a two-story building, located almost in the center of the campus.
Figures 1 and 2 indicate the campus location of Taylor Hall and the location of the reactor facility within Taylor Hall, respectively.
Part of the Taylor Hall building has already been demolished. The remaining structure housing the reactor room will be demolished following the decommissioning cf the reector facility.
The UT reactor is a standard Mark I TRIGA heterogeneous pool-type reactor incorporating uranium-zirconium hydride fuel-moderator elements with an enrichment of less than 20% U-235. The reactor core is submerged in an open tank of light water that serves as both a moderator and coolant (See Figure 3).
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3.0 EVALUATION UT proposes to distantle the facility in accordance with their dismantling plan and will decontaminate the facility to satisfy the contamination levels in Regulatory Guide 1.86 and dose levels of SpR/hr above background at one meter from any accessible surface se that the facility can be released for unrestricted use.
The staff has reviewed the UT plan to dismantle and decontaminate the reactor facility, and to dispose of its component parts and radioactive material. The review considered the UT management responsibilities and commitments; the health physics program including procedures, equipment, instrumentation, survey techniques, training, and personnel dosimetry; the waste disposal; and the final survey. These functions and activities were ongoing during operation of the facility and will be maintained in appropriate scope during the dismantling and decontamination program.
3.1 Management The Director of the UT TRIGA facility will maintain resp"insibility for all activities at the facility. The Director has appointed the i,
Assistant Director of the facility to be the Decomissioning Superintendent, responsible for all dismantling, decontamination and s
decomissioning activities. A Decommissioning Supervisor, supplied by the contractor, will be responsible for daily activities and direction of the crews working on site. He will reDort to the Decomissioning Superintendent and will plan all major dis,.antling and decontamination activities with the Superintendent.
3.2 Health and Safety 3.2.1 Management The health physics activities are the responsibility of the Safety i
l Office, which reports to the University Administration (See Figure 4).
l A full-time health physicist from the Safety Office will be assigned I
to the reactor facility for the decomissioning of the UT TRIGA l
reactor. This person will be responsible for recomending and enforcing safety policy, both radiological and industrial. His responsibilities include maintenance of radiation exposure records, implementation of the environmental survey program, ensuring compliance with work procedures, training, and the assignment of additional health physics technicians to specific work tasks, if necessary.
In addition, the health physicist will be responsible for the development and implementation of the in-plant radiation protection program, the survey instrumentation program (including calibration), bioassay of personnel, airborne radioactivity monitoring, supervision and documentation of radioactive waste packaging, and ALARA planning.
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~ s 3.2.2 Cuality Assurance A Quality Assurance Superintendent will be responsible for implerrenting the cuality assurance plan for decommissioning.
In order to insure independence of the quality. assurance program this person will report directly to the University Administration. This person maintains audit and job performance records and verifies that established safety review procedures are followed.
3.2.3 " Unrestricted Use" Release Criteria The staff position for release for unrestricted use or unrestricted access is found in Regulatory Guide 1.86, Table I, or may be satisfied by a radiation level of no more than SpR/hr above natural backgrourd at 1 meter from any measured surface. Alternatively, if it can be shown that the maximum radiation exposure to an individual would be less than the staff's recommended annual exposure limit of 10 mrer/yr above background, considering potential occupancy in the vicinity of the radiation, then exposure levels of greater than SpR/hr above background at one meter would be acceptable. UT has indicated that they plan to meet the SpR/hr criterion.
- j 3.2.4 Health phVsics Instrumentation Continuing evaluation of the radiological status of the facility will be carried out by health physics personnel during the dismantling and decontaminetton procedures. Levels of radiation will, therefore, be known at all times in the areas where personnel are working. Portable survey instruments used for health physics will include alpha, beta and gamma survey meters. All instruments will be labeled with a
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description of their calibration status.
The' staff finds that the licensee's instruments, calibrations, and procedures are adequate to characterize the status of the dismantling
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and decontamination program for the facility. The criteria and
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activities with respect to unrestricted use of equipment and I
facilities are acceptable for use in a final termination survey.
3.2.5" Dose Commitment 5 The licensee has estimated that the collective dose equivalent will be between 6.8 to 13.4 person-rem for the workers and less than 0.005
' person-rem for the general public for the entire 51 month project.
. Based on our evaluation of the total estimated manpower and exposure time of 550 persen-days, the exposure values appear to be reasonable and acceptable, y
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4.0 CONCLUSION
Based on the foregoing considerations, the staff concludes that the dismantling and decontarination operations car be conducted without undue risk to the health and safety of the public or workers, and without any significant impact on the environment.
Principal Ccr.tributors: Harold Bernard i
John Dosa Dated: March 9,.1987 i
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