ML20072G218

Operating Rept for University of Mass Lowell Reactor,For Period 930701-940630

ML20072G218
Person / Time
Site:	University of Lowell
Issue date:	06/30/1994
From:	Bettenhausen L MASSACHUSETTS, UNIV. OF, LOWELL, MA (FORMERLY LOWELL
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9408240238
Download: ML20072G218 (1)

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i UNIVERSITY'OF MASSACHUSETTS LOWELL 1 UNIVERSITY AVENUE LOWELL, MA 01854 (508) 934-3365 August 18, 1994 Docket No. 50-223 License No. R-125 U. S. Nuclear Regulatory Commission Document Control Desk Washington, D. C. 20555 ,

Gentlemen:

SUBJECT:

ANNUAL OPERATING REPORT Enclosed is the annual report of operation of the University of Massachusetts Lowell Reactor (UMLR). This report is provided pursuant to the requirements of Technical Specification 6.6.4 for the reactor.

Sincerely yours, ee II. Bettenhausen Reactor Supervisor cc: Region I Administrator T. S. Michaels, Senior Project Manager S. II. Weiss, Chief, ONDB Directorate coioos o

9408240239 940818 PDR ADOCK 05000223

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OPERATING REPORT FOR TIIE UNIVERSITY OF MASS. LOWELL REACTOR FOR THE PERIOD JULY 1,1993 TO JUNE 30,1994 Docket No. 50-223 License No. R-l'25 l

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A. INTRODUCTION In the late 1950's the decision was made to build a Nuclear Center at what was then Lowell Technological Institute. Its stated aim was to train 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 was taken to supply a nuclear reactor and a Van-de-Graaff accelerator as K

the initial basic equipment.

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

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

I The name of the Nuclear Center was officially changed to the "Pinanski Building" in the spring of 1980. The purpose was to refle-et the 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

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educational studies in the fields of physics, radiological sciences, and nuclear engineering. The remaining two floors of the Pinanski Building are i presently occupied by various 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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CONTENTS 1

A. Introduction j B. Function C Operating Experience

1. Experiments and Facility Use

2. Changes in Facility Design

3. Performance Characteristics

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 II. Environmental Surveys I. Radiation Exposures and Facility Surveys

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 OP94-2

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

In addition, the Laboratory's facilities are used in the course work of various 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 C. OPERATING EXPERIENCE

1. Exneriments 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, fission decay product studies, teaching and personnel training.

Activation techniques were used to study geologic composition of rock samples. The evaluation of the neutron to the gamma ratio for in-core experiments is continuing.

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

Isotopes were produced for calibration standards and lab practicums.

Reactor operating time used for teaching purposes included a reactor OP94-4

operat' ions course emphasizing control rod calibrations, critical approaches, period measurement, prompt drops and calorimetric measurement of power and preparation of students and staff members for NRC licensing examinations.

Radiological science students utilized the facility by performing standard surveys. Senior students participated in a laboratory that required locating and identifying an unknown isotope of low activity. The isotope was provided for the students in an isolated area in containment 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 radiological science laboratories.

Several activation and decay experiments were performed for both ,

university and non-university students alike. For the seventh consecutive year, activation and decay experiments were provided for local high school l 1

physics classes involving over 2,000 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.

2. Changes in Facility Design None.

3. Performance Characteristjsui Overall, the performance of the reactor and associated systems has been normal over the past year.

4. Changes in Operating Procedures Related to Reactor Safety A new Operating Procedure related to Reactor Safety was added in May 1994. This Procedure is to be utilized in the simulation of a critical e.xperiment which entails loading the core to a known configuration for training purposes.

We are presently waiting for the NRC to approve the Safety Analysis 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.

The Security Plan has been revised to show changes in security OP94-5 '

measu'res. The plan was accepted by the NRC on June 9,1993.

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.

All surveillance test results were found to be within specified limits and surveillance inspections revealed no abnormalities which would jeopardize the safe operation of the reactor. Each required calibration was also performed.

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6. Staff Changes On January 3,1994, Dr. Lee 11. Bettenhausen was appointed Reactor Supervisor. As of June 30, 1994 the operations staff consists of five Trainees, two part time student Reactor Operators, one part time student Senior Reactor Operator, and three staff Senior Operators, including the Reactor Supervisor.

7. Operations Summary During the course of the fiscal year 1993-1994 the reactor was critical a total of 352.65 hours7.523148e-4 days <br />0.0181 hours <br />1.074735e-4 weeks <br />2.47325e-5 months <br />. The utilization is broken down as follows:

Operating liours Critical hours 352.65 Ilours at full power 157.32 Megawatt hours 184.08 Experimental Utilization Sample hours 120.11 Number of irradiations 182 Number of training hours 198.88 D. ENERGY GENERATED l

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Total energy generated (MWD) 7.67 Number of hours reactor was critical 352.65 Total cumulative energy output (MWD) 167.665 E. INADVERTENT AND EMERGENCY SHUTDOWNS There were nine (9) inadvertent scrams due to equipment malfunction. There were two (2) manual scrams due to equipment malfunction. Almost all of these scrams were due to aging instrumentation for which replacement is planned in the near future.

F. MAJOR MAINTENANCE No major maintenance was performed during this fiscal year.

G. FACILITY CHANGES RELATED TO 10 CFR 50.59 There have been no facility changes to date which pose an unreviewed safety question. All other changes -made throughout the year i are listed under changes in Operating Procedures (C.4).

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 continuously monitored site on the roof of an adjacent building have shown no reactor produced radioactivity. This air sampler was moved to the roof of the Pinanski Building in May 1994. Film badges collected monthly at the same location have failed to show any elevated radiation i levels above background. Beginning in January 1994, quarterly thermoluminescent dosimeters replaced the monthly film badges for  :

environmental monitoring. This change was made in order to achieve the l sensitivity necessary to measure compliance with dose units in unrestricted areas as specified in the new 10CFR20. Data for the first two OP94-7 i

quarte'rs of 1994 show that doses in unrestricted areas are indistingishable from background radiation levels.

Analysis of water samples collected from the Merrimack River

. upstream and downstream of the reactor location have continued to yield l no radioactivity associated with reactor operations.

I. RADIATION EXPOSURES AND FACILITY SURVEYS I. Personnel Exposures Personnel exposures were maintained at the lowest reasonable levels. Doses received by individuals concerned either directly or indirectly with operation of the reactor were within allowed limits. Of the l 24 individuals who were monitored by film badge during the year, the maximum external dose equivalent for one individual was 300 mrem for the year. Two other individuals received 20 and 10 mrem respectively.

2. Radiation Surveys Radiation levels measured in the reactor building have been typically less than 0.1 mrem /hr in general areas. Experiments have been conducted l 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 I 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 l are handled and particular experiments have been in progress.

Contamination in these areas is controlled by the use of easily replaced I plastic-backed absorbent paper on work surfaces, contamination protection for workers, and restricted access OP94-8

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J. NATURE AND AMOUNT OF RADIOACTIVE WASTES ,

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1. Liquid Wastes ]

Following is a summary of radioactivity releases to the sanitary sewer during the reporting interval:

I Date Volume Released, Activity, gallons pCi 07/08/93 7500 28 ,

08/25/93 7500 16 09/08/93 7500 5 09/13/93 7500 5 09/28/93 7500 5 ,

10/19/93 7500 4 11/08/93 7500 2 l 12/21/93 6000 1 l

02/10/94 7300 1 02/28/94 7500 5 03/31/94 7500 1 06/02/94 7500 3 06/09/94 7500 3 06/14/94 7500 1 06/20/94 7500 16 06/22/94 5500 4 ,

.06/29/94 7500 19 Annual Total 119 The 1993 total activity data was based on gross beta sample analysis. The

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1994 release data was based on gamma spectral analysis of the waste water samples.

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2. Gaseous Wastes Argon-41 continues to be the only significant reactor produced radioactivity identifiable in the gaseous effluent. Following are the monthly stack release data for Ar4I for the reporting period:

Date Amount Released (Ci)

July 1993 0.63 August 1993 0.25 September 1993 0.20 October 1993 0.80 November 1993 0.28 December 1993 0.29 January 1994 0.34 February 1994 0.48 March 1994 0.22 April 1994 0.80 May 1994 1.24 June 1994 0.37 Total 5.90

3. Solid Wastes Solid wastes, primarily paper, disposable clothing, and gloves, along with other miscellaneous items have been packaged in appropriate containers. Most of the. activity from these wastes consisted of short lived induced radioactivity. These wastes were held for decay and then released if no activity remained. A small quantity of long lived waste (< 5 cubic feet) was included as part of a shipment to the Barnwell Low Level Waste Facility during June 1994.

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