ML20117J841

Operating Rept for Univ of Mass Lowell Reactor for Period 950701-960630

ML20117J841
Person / Time
Site:	University of Lowell
Issue date:	06/30/1996
From:	MASSACHUSETTS, UNIV. OF, LOWELL, MA (FORMERLY LOWELL
To:
Shared Package
ML20117J829	List: ML20117J828 ML20117J841
References
NUDOCS 9609110017
Download: ML20117J841 (10)

Text

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l OPERATING REPORT FOR THE UNIVERSITY OF MASS. LOWELL REACTOR FOR THE PERIOD JULY 1,1995 TO JUNE 30,1996 Docket No. 50-223 License No. R-125 1

l OP96-1 9609110017 960827 DR ADOCK 050002 3

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l CONTENTS

A. Introduction l

B. Function l

l C Operating Experience  ;

l 1. Experiments and Facility Use

2. Changes in Facility Design l

3. Performance Characteristics l 4. Changes in Operating Procedures Related to Reactor Safety ,

5. Results of Surveillance Tests and Inspections

6. Staff Changes

7. Operations Summary D. Energy Generated E Inadvertent and Emergency Shutdowns F. Major Maintenance G Facility Changes Related to 10 CFR 50.59 l H. Environmental Surveys I. Radiation Exposures and Facility Surveys i

1. Personnel Exposures

2. Radiation Surveys

3. Contamination Surveys J. Nature and Amount of Radioactive Effluents

1. Liquid Wastes

2. Gaseous Wastes

3. Solid Wastes 1

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A. INTRODUCTION 1 l In the late 1950's the decision was made to build a Nuclear Center at l what was then Lowell Technological Institute. Its stated aim was to train l and educate nuclear scientists, engineers and technicians, to serve as a

! multi-disciplinary research center for LTI and all New England academic institutes, to serve the Massachusetts business community, and to lead the way in the economic revitalization of the Merrimack Valley. The decision I was taken to supply a nuclear reactor and a Van-de-Graaff accelerator as the initial basic equipment.

i Construction of the Center was started in the summer of 1966.

Classrooms, offices, and the Van-de-Graaff accelerator were in use by l 1970. Reactor license R-125 was issued by the Atomic Energy Commission l on December 24, 1974, and initial criticality was achieved on January 1975.

The name of the Nuclear Center was officially changed to the "Pinanski Building" in the spring of 1980. The purpose was to reflect the l l l change in emphasis of work at the center from strictly nuclear studies. At that time, the University of Lowell Reactor became part of a newly established Radiation Laboratory. The Laboratory occupies the first floor of the Pinanski Building and performs or coordinates research and educational studies in the fields of physics, radiological sciences, and nuclear engineering. The remaining two floors of the Pinanski Building are l presently occupied by varicus other University departments.

On February 14, 1985, the University of Lowell submitted an application to the Nuclear Regulatory Commission for renewal of the facility operating license R-125 for a period of 30 years. On November 21, 1985, the license renewal was granted as Amendment No.9 of License R-125 in accordance with the Atomic Energy Act of 1954.

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i B. FUNCTION The Radiation Laboratory is a major research focal point of the j University. More than 200 graduate students have used or are using the Laboratory's services; the comparable number for the faculty is in excess l of 25. The University departments utilizing the facility include Biology, j Chemistry, Geology, Physics, Mechanical Engineering, Plastics Engineering, '

l Radiological Science and Nuclear Engineering. The University's Amherst l campus and Medical Center have active research programs at the Radiation Laboratory. Much research concerns safety and efficiency in the nuclear and radiation industries, including public utilities, pharmaceuticals, medical applications, health effects, etc.; however, much research is also done by workers in other fields who use the unique facilities as analytical tools.

l In addition, the Laboratory's facilities are used in the course work of l vanous departments of the University. It also provides these services to other universities in the New England area, government agencies and, to a limited extent, industrial organizations in Massachusetts and the New England area, as well as school science programs in the Merrimack Valley.

C. OPERATING EXPERIENCE

1. Experiments and Facility Use  !

The major uses of the reactor during this fiscal year were activation analysis, dosimetry studies, calibrations, limited isotope production, neutron damage studies, combined neutron and gamma radiation effects on electrical cables, service life for neutron detectors, fission decay product

, studies, teaching and personnel training.

l Activation techniques were used for such diverse studies as geologic composition of rock samples and intracellular calcium in heart tissue. The

( evaluation of the neutron to the gamma ratio and detailed neutron spectral l mapping for in-core experiments is continuing.

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' Dosimetry studies and calibrations utilized N-16 production for high energy gamma fields. -

Isotopes were produced for calibration standards, medical research use, and lab practicums.

Reactor operating time used for teaching purposes included a reactor l operations course emphasizing control rod calibrations, critical approaches,  !

period measurement, prompt drops and calorimetric measurement of power and preparation of students for NRC licensing examinations.

Radiological science - students utilized the facility to perform radiation and contamination surveys. Senior students participated in a laboratory that required locating and identifying an unknown isotope of low activity in a mockup power plant environment. The isotope was provided for the students in an isolated area in the reactor pump room during non-operating hours. During the practicum, the students were supervised by faculty and staff. The reactor served as a source of neutron and gamma radiation for various radiological science and biology laboratories.

A number of activation and decay experiments were performed for both university and non-university students alike. For the eighth consecutive year, activation and decay experiments were provided for local school science classes involving over 2,200 students who observed the experiment at the reactor or in their classrooms via interactive cable T.V.

The major outside use for the reactor facility is neutron and gamma damage studies of electronic components and electrical cable and service life determination for neutron detectors.

2. Changes in Facility Design None.

3. Performance Characteristics The performance of the reactor and associated systems has been normal over the past year.

4. Changes in Operating Procedures Related to Reactor Safety We still await the Department of Energy to provide a firm schedule for fuel eternent fabrication and the NRC to approve the Safety Analysis OP96-5

Report for the Low Enriched Uranium (LEU) and the new Technical Specifications related to use of the LEU fuel. Changes to operating procedures will then be needed to implement the new fuel use, as well as detailed testing with new core elements.

New nuclear and radiation detection instruments have been acquired. The detailed planning, safety reviews, and procedure changes needed to install and operate the new instrumentation is in progress.

5. Results of Surveillance Test and Inspections All Technical Specification Surveillances required during the fiscal year were performed in a timely manner. The results of each requirement have been reviewed by the Reactor Supervisor and Chief Reactor Operator.

Almost all surveillance test results were found to be within specified limits and surveillance inspections revealed no abnormalities which would j jeopardize the safe operation of the reactor. One surveillance test found that one rod drop time was slightly greater than specification; investigation ,

found an oil film on the magnet which delayed breakaway by about 100 milliseconds. The magnets and rod heads were cleaned and drop times were reduced below specified values. Magnet cleaning will be 4 incorporated in the annual rod maintenance. Each required calibration was also performed.

6. Staff Changes As of June 30, 1996 the operations staff consists of three Trainees, one part time student Reactor Operator, two part time student Senior Reactor Operators with the most senior serving as Chief Reactor Operator, and two staff Senior Operators, including the Reactor Supervisor.

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7. Dperations Summary l During the course of the fiscal year 1994-1995 the reactor was 4

} critical a total of 646 hours0.00748 days <br />0.179 hours <br />0.00107 weeks <br />2.45803e-4 months <br />. The utilization is broken down as follows: j

! Operating Hours i

l Critical hours 646 l Hours at full power 459

Megawatt hours 568 l 1

Experimental Utilization

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! Sample hours 2190 l (includes multiple samples) i Number of irradiations 730 Number of training hours 222

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! D. ENERGY GENERATED i.

Total energy generated (MWD) 23.65

~l Number of hours reactor was critical 646 Total cumulative energy output (MWD) 209.04 E. INADVERTENT AND EMERGENCY SHUTDOWNS There were 8 inadvertent scrams. All but one of these scrams were operator errors induced by aging instrumentation for which replacement is planned in the near future. One scram not related to instruments was operator action tsken in response to a fire alarm in the building adjacent to the reactor building in accordance with Emergency Operating Procedures.

The cause of the fire alarm was a smoking fluorescent light ballast.

F. MAJOR MAINTENANCE OP96-7

No major maintenance was performed in the reporting period.

G. FACILITY CHANGES RELATED TO 10 CFR 50.59 There have been no facility changes to date which pose an unreviewed safety question.

l H. ENVIRONMENTAL SURVEYS Surveys of the environs external to the reactor building have continued to show no increase in levels or concentrations of radioactivity as a result of reactor operations. Air particulate samples collected at a j continuously monitored site on the roof of the Pinanski building have l shown no reactor produced radioactivity. Thermoluminescent dosimeters i are used to monitor unrestricted areas outside of the Reactor. The results l of these measurements show that doses in these areas were indistinguishable from background radiation levels during the period of July 1,1995 to June 30, 1996.

Analysis of water samples collected from the Merrimack River j upstream and downstream of the reactor location have continued to yield

no radioactivity associated with reactor operations. '

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I. RADIATION EXPOSURES AND FACILITY SURVEYS l I. Personnel Exposures i Personnel exposures were maintained at the lowest reasonable 3

levels. Doses received by individuals concerned either directly or l indirectly with operation of the reactor were within allowed limits.

Twenty individuals who were monitored by film badge during the year.  ;

i Only two received external deep dose equivalents of more than twenty )

l millirem (90, 60).

i i 2. Radiation Surveys i

l Radiation levels measured in the reactor building have been typically l

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fess tilan 0.1 mrem /hr in general areas. Experiments have been conducted in which transient levels at specific locations have been in excess of 100 mrem /hr. Doses in these instances have been controlled by use of shielding and/or personnel access control. The pump room remains designated as a high radiation area during reactor operation and access is controlled. Dose equivalent levels in the order of 10 mrem /hr are present adjacent to the closed beam ports during maximum power operation.

3. Contamination Surveys General area contamination has not been a problem in the reactor building. Contamination has occurred at specific locations where samples are handled and particular experiments have been in progress.

Contamination in these areas is controlled by the use of easily replaced plastic-backed absorbent paper on work surfaces, contamination protection for workers, and restricted access.

J. NATURE AND AMOUNT OF RADIOACTIVE WASTES

1. Liauid Wastes Liquid wastes are stored for decay of the short lived isotopes and then released to the sanitary sewer in accordance with 20 CFR 2003. A total of 23.5 Cis were released over the 12 month period. The principle isotopes released were corrosion products ie. Mn-54, Co-60, Zn-65 and Sb-124. This data was based on gamma spectral analysis of the waste water before it is released to the sanitary sewer.

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! Ar on 41 t ues to be the only significant reactor produced l

i l radioactivity identifiable in the gaseous effluent. Following are the i monthly stack release data for Ar4 1 for the reporting period: l

, Month M Hours Ar-41 Released 1

l Curies l

July 1995 0.7 August 1995 2.6  !

September 1995 1.9 October 1995 1.8 November 1995 1.8

! December 1995 0.7 j

January 1996 2.1 February 1996 2.6 l March 1996 2.0 April 1996 1.7 May 1996 1.5 June 1996 1.5 i

Total 20.9 This represents 12 month dose of 0.4 mrem to the nearest member of the

. public using EPAs comply code.

3. Solid Wastes Solid wastes, primarily paper, disposable clothing, and gloves, along with other miscellaneous items have been disposed of in appropriate containers. Most of the activity from these wastes consisted of short lived l induced radioactivity. These wastes were held for decay and then released l if no activity remained. The remaining long lived waste (< 5 cubic feet) is

being accumulated for ultimate disposal at Barnwell.

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