ML20056G350

Operating Rept for Univ of Ma Lowell Reactor for Jul 1992 - June 1993. W/930827 Ltr

ML20056G350
Person / Time
Site:	University of Lowell
Issue date:	06/30/1993
From:	Kegel G MASSACHUSETTS, UNIV. OF, LOWELL, MA (FORMERLY LOWELL
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9309030031
Download: ML20056G350 (12)

Text

'

University of Massachusetts Lowell Radiation Laboratory i University Avenue Lowell, Massachusetts, 01854 508 934-3821 August 27, 1993  ;

i Director Nuclear Reactor Regulations U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Gentlemen:

Enclosed please find a copy of the Annual Report covering the operations of the University of Massachusetts Lowell Research Reactor for the period from July 1,1992 to June 30, 1993.

Sincerely yours, 0t usAM) 1cz p(

i s Gunter Kegel, j Director Radiation Laboratory {

l l

93d90$0d31 930630 E PDR ADOCK 05000223 j:] I R PDR gj l

5 i

l -

I s

OPERATING REPORT i

l FOR TIIE UNIVERSITY OF MASS. LOWELL REACTOR FOR TIIE PERIOD JULY 1,1992 TO JUNE 30,1993 1 i

i l

.t Docket No. 50-223  !

1 l License No. R-125 L

l r

i l  :

l l

t 1 OP93-1 i

CONTIINIS A. Introduction 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 H. 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 I

i 3. Solid Wastes i

OP93-2

?

I

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 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.

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 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 radiological sciences and nuclear j engineering. The remaining two floors of the Pinanski Building are presently occupied by various other University departments. i 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. No amendment applications have been submitted since that titne.

l l

i s

i OP93-3 l l

l 1

I J

B. FUNCTION r i l The Radiation Laboratory is a major research focal point of the l University. More than 200 graduate students have used or are using the l 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 Engmeenng, )

Radiological Science and Nuclear Engineering. Much research is correlated j with safety and efficiency in the nuclear and radiation industries, including  ;

public utilities, pharmaceuticals, medical applications, health effects, etc.;

l 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 j various departments of the University. It also provides these services to l other universities in the New England area, government agencies and, to a limited extent, industrial organizations in Massachusetts and the New l

England area l l

C. OPERATING EXPERIENCE '

i

1. Experiments and Facility Use l l The major uses of the reactor during this fiscal year were activation l analysis, dosimetry studies, calibrations, isotope production, neutron damage 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 utilize.d N-16 production for high energy gamma fields.

Isotopes were produced for calibration standards and lab practicums.

Reactor time used for teaching purposes included a reactor operations course emphasizing control rod calibrations, critical approaches, period measurement, prompt drops and calorimetric measurement of po we r.

l

\

OP93-4

l l l Radiological science students utilized the facility by performing l i

l 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.  ;

t Several activation and decay experiments were performed for both j l university and non-university students alike. For the sixth consecutive  !

i year, activation and decay experiments were provided for local high school ,

i physics classes which observed the experiment in their classrooms via l interactive cable T.V.  ;

l The major outside use for the reactor facility is neutron and gamma damage studies of electronic components. l t i

2. Chances in Facility Desien i l None.  :

i  :

i

3. Performance Characteristics  :

! Overall, the performance of the reactor and associate systems has j been normal over the past year.

l

4. Chances in Operatine Procedures Related to' Reactor Safety There have been no changes in Operating Procedures related to l Reactor Safety.

l l

i On May 7,1993 the Safety Analysis Report for the Low Enriched Uranium (LEU) and the new Tech Specs were approved, by the Reactor Safety Sub-Committee, and submitted to the NRC.  !

The Security Plan has been revised to show changes in security measures. The plan has been approved by the Reactor Safety Sub-Committee. It was submitted to the NRC on May 27, 1993 for their approval.

j OP93-5 l

l

l l

5. Results of Surveillance Test and Inspections j All Technical Specification Surveillances required during the fiscal j year were performed in a timely manner. The results of each requirement have been reviewed by the Reactor Supervisor and Chief Reactor Operator. l All surveillance test results were found to be within specified limits and j surveillance inspections revealed no abnormalities which would jeopardize l the safe operation of the reactor. Each required calibration was_ also I performed.

6. Staff During the month of October the Reactor Supervisor was placed on a medical leave. On October 27, 1992 Dennis Martineau was appointed i Acting Reactor Supervisor. The facility is presently in search of a i replacement for the Reactor Supervisor. As of June 30,1993 the  !

operations staff consists of five Trainees, one part time Reactor Operator, ,

and two Senior Operators including the Reactor Supervisor. j l

l

7. Operations Summary l During the course of the fiscal year 1992-1993 the reactor was l critical a total ofi 70.86 hours9.953704e-4 days <br />0.0239 hours <br />1.421958e-4 weeks <br />3.2723e-5 months <br />. The utilization is broken down as follows:

Operating flours Critical hours 170.86 Hours at full power 100.07 Megawatt hours 119.60 Exnerimental Utilization  !

l Sample hours 101.92 l Number of irradiations 232

Number of training hours 184.60 i

OP93-6 l

1

1 1

1 i

i

! D. ENERGY GENERATED 1 ,

4

)

! Total energy generated (MWD) 4.98 l Number of hours reactor was critical 170.86  ;

} Total cuniulative energy output (MWD) 159.995 l E. INADVERTENT AND EMERGENCY S11UTDOWNS i

i There was one (1) inadvertent scram due to a detent switch

! malfunction on Valve P-12.

• l l

} F. MAJOR MAINTENANCE I  ;

i No major maintenance was performed during this fiscal year.

l l

l G. CIIANGES TO TIIE FACILITY UNDER 10 CFR 50.59 j  !

! There have been no facility changes to date which pose an j unreviewed safety question. All other changes made throughout the year j are listed under changes in Operating Procedures (C.4).

}

i 11. ENVIRONMENTAL SURVEYS a

1

Surveys of the environs external to the reactor building have l continued to show no increase in levels or concentrations of radioactivity j as a result of reactor operations. Air particulate samples collected at a j continuously monitored site on the roof of an adjacent building have 1 i shown no reactor produced radioactivity. Film badges collected monthly at 1

i the same location have failed to show any elevated radiation levels above background.

j Analysis of water samples collected from the Merrimack River j upstream and downstream of the reactor location have continued to yield j no radioactivity associated with reactor operations.

i j

f

\

i OP93-7  !

1

l

1. RADIATION EXPOSURES AND FACILITY SURVEYS

! 1. Personnel E xposures l

Personnel exposures are maintained at the lowest reasonable level.

Doses received by individuals concerned either directly or indirectly with l

l operation of the reactor were within allowed limits. Measurable whole l body penetrating and ring finger shallow doses are given below. ,

! l l Personal Exposures l Dose Summary i 1992 1992 1993 1993 Total  :

l 3rd 4th 1st 2nd l Martineau Whole Body 0 0 0 0 0 Ring 5 0 30 0 35 i Montesalvo Whole Body 50 0 0 0 50 ,

Ring 50 410 140 0 600 I l

McKee Whole Body 0 30 30 0 60 l

Rine 100 220 190 20 530 1 l Regan Whole Body 0 0 10 0 10 l Ring 100 0 0 0 100 Pace Whole Body 0 0 0 0 0 Ring 0 0 0 0 0 Strafalace Whole Body -

0 0 0 0 l

Rine -

20 70 0 90 j Church Whole Body 0 10 0 0 10 Ring 0 0 0 0 0 McCarthy Whole Body 0 20 0 0 20 Ring 660 10 0 0 670 Coakley Whole Body 0 - - -

0 Ring 0 - - -

0 i Maher Whole Body 0 20 0 0 20 Ring 40 20 20 0 80 Delanocentis Whole Body 10 20 - -

30 Ring - - - -

0

, OP93-8 l

l 8

1 I

~ Wallace Whole Body 0 - - -

0 i Ring 0 - - -

0 Gebrgeorgis Whole Body 0 0 - -

0 Ring 0 0 - -

0 l Chabot Whole Body 0 110 20 220- 350 l Ring 0 110 0 130 240  !

! Pamelia Whole Body 0 - - -

0 i Ring - - - - -

l Leipprandt Whole Body 0 0 0 0 0 Ring 0 0 0 0 0 Total Whole Body 100 mrem  !

or 0.10 manrem i

! *Not Reactor Related l

l # Shallow Dose I

2. Radiation Surveys i l Radiation levels measured in the reactor building have been typically  !

l less than 0.1 mrem /hr in general areas. Experiments have been conducted i in which transient levels at specific locations have been in excess of 100 l

l mrem /hr. Doses in these instances have been controlled by use of j shielding and/or personnel access control. The pump room remains j designated as a high radiation area during reactor operation. Dose i equivalent levels in the order of 10 mrem /hr are present adjacent to the beam ports during maximum power operation. l

3. Contamination Survevs i l

General area contaminatien ha., not been a problem in the reactor i building. Contamination can occur at specific locations where samples are handled and particular exper'.ments have been in progress. Monthly Surveys have failed to detect significant contamination levels at these locations.

I i

OP93-9  :

)

., . . _ . . - - _ . . .,, -.. ,,i

~

~

l I

J. NATURE AND AMOUNT OF RADIOACTIVE WASTES l

l. Liquid Wastes l l Following is a summary of radioactivity releases to the sanitary l sewer during the reporting interval:  !

i i

Date Undiluted Gross Beta Total pCi 1992 pCi/ml i

07/07/92 1.276 x 10- 7 3.62 07/27/92 2.047 x 10-7 5.81 l

08/l3/92 9.207 x 10-7 26.14 .

08/20/92 3.191 x10 7 2.89 09/29/92 1.812 x 10-7 5.14 i 10/09/92 1.440x10 6 - 40.88 11/04/92 3.002 x 1()-7 8.52 l' 11/30/92 5.685 x 10-7 16.14 1993 l  :

l I 03/02/93 2.001 x 10-7 5.28 03/22/93 6.04 8 x 10-7 17.17

( 04/29/93 4.044x10-7 11.48 06/17/93 5.964 x 10-7 16.93 06/28/93 2.272 x 1 ()-7 6.45 07/08/93 9.9 84 x 10-7 28.34 l

l OP93-10 l

2. _ Gaseous Wastes Argon-41 continues to be the only reactor produced radioactivity identifiable in the gaseous effluent. Following are the monthly stack release data for Ar4 1 for the reporting period:

Date Amount Released Duration of Release (Ci) (hrs) .

July 1992 0.101 4.25 August 1992 0.066 2.7 September 1992 0.428 19.0 t October 1992 0 0 ,

November 1992 0 0 l December 1992 0.475 18.25 January 1993 0.270 10.0 February 1993 0.123 7.0 March 1993 0.130 6.75 April 1993 0.361 18.75 May 1993 0.286 8.5 June 1993 0.154 6.5 Total 2.394 101.7

3. Solid Wastes Solid wastes, primarily paper, disposable clothing along with other miscellaneous items have been packaged in appropriate containers. Most j of the activity from these wastes consisted of short lived induced l

radioactivity. These wastes were held for decay and then released if no activity remained.

l l

l OP93-11 i

i