ML20212N516

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Safety Evaluation Supporting Order Authorizing Dismantling of Facility & Disposition of Component Parts
ML20212N516
Person / Time
Site: 05000433
Issue date: 08/26/1986
From:
Office of Nuclear Reactor Regulation
To:
Shared Package
ML20212N501 List:
References
NUDOCS 8608280260
Download: ML20212N516 (6)
v • d • e


Text

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s UNITED STATES 3

NUCLEAR REGULATORY COMMISSIOtJ h.

,j WASHINGTON, D. C. 20655 e

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SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION SUPPORTING ORDER AUTHORIZING DISMANTLING OF FACILITY AND t

i DISPOSITION OF COMPONENT PARTS TO FACILITY OPERATING LICENSE NO. R-124' UNIVERSITY OF CALIFORNIA AT SANTA BARBARA UNIVERSITY OF CALIFORNIA AT SANTA BARBARA L-77 RESEARCH REACTOR 4

DOCKET-NO. 50-433

1.0 INTRODUCTION

By application dated September 9, 1985, as supplemented, the UniversityofCaliforniaatSantaBarLara(UCSB) requested authorization to decontaminate and dismantle the 10W (thermal) L-77 research reactor, to dispose of its component parts in accordance with the proposed plan, and to terminate Facility Operating License 1

No. R-124. All fuel has been removed from the core tank and shipped to an authorized Department of Energy facility.

4 The reactor was originally licensed to operate at the University of i;

Nevada, Reno, at a maximum power level of 10W.

It was donated and j

transferred to UCSB in 1974. The integrated burnup while at UCSB has ij been approximately 360 W hours.

I i

2.5 FACILITY DESCRIDTION l

The UCSB L-77 research reactor is located on the first floor of the Physics Building located on the eastern side of the main campus.

Figures 1 and 2 indicate the campus location of the Physics Building and the location of the research facility within the building, 3

respectively.

The UCSB L-77 research reactor is a small, solution-type nuclear reactor designed for laboratory use.

It was manufactured by The Atomics International Division of North American Aviation, a predecessor of the Rocketdyne Division of Rockwell International.

The reactor consists of a core tank containing the fuel solution of 90% U-235 enriched uranyl sulfate) w thin an inner shield tank, which is mounted inside a water filled outer shield tank (See Figure 3).

3.0 EVALUATION UCSB proposes to dismantle the facility in accordance with their dismantling plan and will decontaminate the facility to meet the requirements of contamination levels in Regulatory Guide 1.86 and dose levels of SpR/hr above background.at one meter for unrestricted use.

8600280260 860826 PDR ADOCK 05000433 W

PDR

l Tha staff has reviewed the UCSB plan to dismantle and decontaminate the reactor facility, and to dispose of its component parts and j

radioactive material. The review considered the management i

responsibilities and connitments (the health physics program including procedures, equipment, instrumentation, survey techniques, training, and personnel dosimetry), the waste disposal, and the final j

survey. The functions and activities that were ongoing during i

operation of the facility will be maintained in appropriate scope i

during the disnantlirg and decontamination program.

3.1 Management I

The Reactor Director of the UCSB L-77 reactor facility will :naintain l

all responsibility for activities at the facility. He will report to 1

the Chairman of the Department of Chemical and Nuclear Engineering, who ultimately reports through the College of Engineering to the Vice j

Chancellor for Administration, UCSB. A Project Engineer, supplied by the contractor, will be responsible for daily activities and direction of the deconnissioning mechanics. However, he will report to the Reactor Director.

i 3.2 Health and Safety 3.2.1.

Management l

i The health physics activities are located in the Office of j

Environmental Health and Safety, which reports to the Vice Chancellor j

for Administration, UCSB. The UCSB Radiation Protection Officer, i

assigned from the Office of Environmental Health and Safety, will review and concur on all health,~ safety, and environmental protection concerns. The contractor's health physicist will report to the Project Engineer who, in turn, will report health and safety i

concerns to the UCSB Radiation Protection Officer. The health j

physicist's responsibilities include maintenance of radioactive i

exposure records for the contractor's personnel, ensuring compliance I

with work procedures, itplementation (,f the in-plant radiation i

protection program, the survey instrumentation program, bicassay of personnel, radioactivity monitoring, documentation of radioactive j

waste packaging, and ALARA planning.

t 3.2.2

" Unrestricted Use" Release Criteria The staff position for release for unrestricted use or unrestricted access is Regulatory Guide 1.86, Tatle I, and an exposure rate of no more than SpR/hr above natural background at 1 meter from any i

measured surface. Alternatively, the licensee may show that the maximum radiation dose to an individual would be less than the staff's recommended annual dose limit of 10 mrem /y'r considering,

l l

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f potential occupancy in the vicinity of the radiation. Then exposure rate levels of greater than SpR/hr above background at one meter would be acceptable. UCSB has indicated that they plan to meet the 4

SpR/hr criterion.

3.2.3 Health Physics Instruments Continuing evaluation of the radiological status of the facility will be carried out by the health physicist during the dismantling and decontamination procedures. Levels of radiation will, therefore, be known at all times in areas where personnel are working. Portable survey insturments used for health physics will include alpha, beta and gamma survey meters. Staff review indicates that instruments to be used by the licensee during dismantling and decontamination are state-of-the-art. All instruments will be labeled describing their calibration status.

The staff finds that the licensee's instruments, calibrations and procedures are adequate to characterize the status of the dismantling and decontamination prcgram for the facility. The criteria and activities with respect to unrestricted use of equipment and facilities are acceptable for use in a final termination survey.

3.2.4 Dose Potential UCSB has estimated that the collective dose expected for the entire dismantling and decontamination operation will be less than 0.05 person-rem. The collective dose to the public will be negligible. This estimate is based on the expected levels of radioactivity from all sources and the manner in which experienced and well-trained worker: will be perfonning their tasks in the expected radiation fields. These items, among others described by UCSB, will atsure that collective dose will be ALARA, and are found to be acceptable by the staff.

4.0 CONCLUSION

Based on the foregoing consfor: rations, the staff concludes that the dismantling and decontamination oporations can be conducted without undue risk to the health and safety of the public or operators, and without any significant impict on the environment.

Principal Contributor: John Dosa Dated:

August 26, 1986 i

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