ML14245A053

Univ. of Massachusetts-Lowell - Annual Operating Report for 2013-2014

ML14245A053
Person / Time
Site:	University of Lowell
Issue date:	08/27/2014
From:	Bobek L Univ of Massachusetts - Lowell
To:	Document Control Desk, Office of Nuclear Reactor Regulation
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Download: ML14245A053 (10)

Text

~,4University of Massachusetts UMASS Lowell Pinanski Building One University Avenue Lowell, Massachusetts 01854 tel:

978.934.3365 fax.

978.934.4067 e-mail:. LeoBobek@uml.edu Leo M. Bobek Reactor Supervisor RADIATION LABORATORY August 27, 2014 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555 Re: License No. R-125, Docket No. 50-223 Pursuant to Technical Specification 6.6.4 of NRC License No. R-125 we are submitting the routine Annual Report for the University of Massachusetts Lowell Research Reactor.

Sincerely, Leo M. Bobek, Reactor Supervisor 4¢-co

Al University of Massachusetts Lowell Research Reactor (UMLRR) 2013-2014 OPERATING REPORT NRC Docket No. 50-223 NRC License No. R-125 Universiy of AJ UnMassachusetts UMASS Lowell One University Avenue Lowell, Massachusetts 01854

CONTENTS Facility History and Overview A.

Narrative Summary

1. Operation Experience and Experiments

2. Facility Design Changes

3. Performance Characteristics Changes

4. Changes in Operating Procedures Related to Reactor Safety

5. Results of Surveillance Tests and Inspections B.

Tabulations C.

Inadvertent and Emergency Shutdowns D.

Major Maintenance E.

Facility Changes Related to 10 CFR 50.59 F.

Environmental Surveys G.

Radiation Exposures and Facility Surveys

1. Personnel Exposures

2. Radiation Surveys

3. Contamination Surveys H.

Nature and Amount of Radioactive Effluents

1. Liquid Wastes and Gaseous Wastes

2. Solid Wastes This report is submitted as required by the Technical Specification 6.6.4 of reactor license R-125 and provides the information as outlined in the specification.

1

Facility History and Overview 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 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 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.

In 1991, the University of Lowell name was changed to University of Massachusetts Lowell. On August 4, 2000, the reactor was converted from high enrichment uranium fuel to low enrichment uranium fuel.

The University of Massachusetts Lowell Radiation Laboratory (UMLRL) is one of 22 research centers at the University. The University departments utilizing the laboratory include Biology, Chemistry, Earth Sciences, Physics, Mechanical Engineering, Plastics Engineering, Radiological Sciences, and Chemical/Nuclear Engineering. Several of the UMass campuses, 2

including the university medical center, have or continue to have research programs at the Radiation Laboratory.

Much of the research is concerned with safety and efficiency in the nuclear and radiation industries, including pharmaceuticals, medical applications, health affects, public utilities, etc. However, much of the research conducted in other scientific fields that make use the unique facilities as analytical tools.

Beyond the research activities, the Laboratory's reactor and Cobalt-60 facilities are used in the educational courses of various departments within the University. It also provides these services to other campuses of the Massachusetts system, 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 numerous school science programs in the Merrimack Valley.

UMLRR Cutaway View 3

A.

NARRATIVE

SUMMARY

1.

Operating Experience and Experiments The UML research reactor is designed to produce thermal (low energy) neutrons for radioactivation and neutron radiography purposes, and fast (high energy) neutrons for radiation effects studies. Uses include neutron activation analysis research, materials atomic displacement damage studies, neutron absorption studies, short-lived radioisotope production, neutron detector studies, and neutron imaging (radiography). Education uses include a variety of lab courses in the nuclear engineering and radiological sciences programs.

Tours and demonstrations are provided to several other UMass Lowell courses, as well as other universities, high schools, and various organizations.

Short lived isotopes (e.g., Al-28, Na-24) were produced for routine practicum and demonstration purposes. The reactor was used for several nuclear engineering and non-nuclear engineering laboratory exercises and demonstrations.

In addition, the reactor was used for training of student operator license candidates. Student candidates are provided an opportunity to work at the reactor and gain practical experience while studying for a future licensing examination.

Approximately 50 organized tours were provided to UMass students, local college students, grade school students, and other groups, and individual tours. As part of emergency responder training, tours and presentations also were provided to the UML Police Department,.

2.

Facility Design Changes There were no facility design changes during the reporting period..

3.

Performance Characteristics Changes As noted in previous annual reports, the linear power monitoring channels have exhibited electronic problems resulting in several spurious scrams (Section C).

Replacement power monitoring channels were ordered and received. They are currently being benched-tested to evaluate functionality.

Performance of all other the reactor and related equipment has been normal during the reporting period. There were no discernable changes that would indicate any degradation of other systems or components.

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4.

Changes in Operating Procedures Related to Reactor Safety Several procedures were updated or modified.

Two emergency operating procedures were updated to reflect changes in the emergency call numbers for University responders. Two administrative procedures were updated to reflect a location change for the University Police dispatch center.

Another administrative procedure was updated to accommodate changes to NRC regulations and definitions. The area radiation monitoring system calibration procedure was modified for the use of a new detector calibration station.

The rod reactivity worth measurement procedure was modified for a change in measurement methodology.

All the procedure changes were appropriately documented and reviewed by the UMLRR reactor safety committee.

5.

Results of Surveillance Test and Inspections All surveillance test results were found to be within specified limits and surveillance inspections revealed no abnormalities that could jeopardize the safe operation of the reactor.

Each required calibration was also performed.

B.

TABULATIONS Energy generated this period (MWD) 5.62 Critical hours 295.05 Cumulative energy to date (MWD) 58.61 C.

INADVERTENT AND EMERGENCY SHUTDOWNS There were 7 inadvertent non-emergency automatic shutdowns during the reporting period. All seven were due to electronic noise problems associated with the power monitoring channels. There was no safety significance associated with any of the scrams. Descriptions of all automatic shutdowns are noted in operator logs and are analyzed by an SRO for safety significance and technical specification requirements. New power monitors were ordered and received, and are expected to be installed before the end of the year.

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D.

MAJOR MAINTENANCE One major maintenance activity was performed during the reporting period.

The rubber gasket seal on the pool divider gate was replaced. The gate is stored inside the reactor pool, alongside the reactor pool center partition. Years of immersion in deionized water along with radiation damage from proximity to the Cobalt-60 source both contributed to degradation. The rubber gasket was removed and replaced in July 2013.

E.

FACILITY CHANGES RELATED TO 10CFR50.59 One activity was screened under the UMLRR Procedure AP-6 JOCFR 50.59 Screenings and Evaluations. The intermediate range log-scale reactor power measuring channel installed in 1997 will be replaced with a new wide range logarithmic power monitor. The existing power monitor uses a compensated ion chamber to measure the neutron flux. The new channel will use a fission chamber. Both channels are manufactured by General Atomics. It was determined via the screen this activity would not require a complete evaluation.

The screen has been documented and reviewed by the UMLRR reactor safety committee.

F.

F.

ENVIRONMENTAL SURVEYS Members of the Radiation Safety Office performed an ALARA review for the 2013 calendar year with the results summarized in Sections G and H. The following actions are performed in the indicated time period as part of the UMLRR radiation safety program:

1. Reactor Field Surveys - monthly (byproduct materials license)

2. Reactor Contamination Surveys - monthly (byproduct materials license)

3. Primary water analysis - weekly (SP-10)

4. 20 ml Secondary Water Analysis - each Rx operations day (SP-10)

5.

3 L Secondary Water Analysis - Biennially (SP-10)

6. liquid waste (sewer) - prior to disposal (SP-10)

7. Rad Monitor Check - each detector checked prior to each day's operations by Rx staff.

8.

Personnel dosimetry - monthly; obtained using a NVLAP accredited dosimetry lab.

9. Environmental dosimetry - quarterly using NVLAP lab.

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G.

RADIATION EXPOSURES AND FACILITY SURVEYS

1.

Personnel Exposures An ALARA assessment of the UMass Lowell radiation safety program is performed annually. This review is reported to and reviewed by the Radiation Safety Committee. The 2013 ALARA goal for radiation workers at UMass Lowell was to limit the most exposed radiation worker at UML to less than 10% of the federal radiation exposure limits.

In addition, the radiation safety manual requires a 100 mrem per week TEDE administrative level.

No occupational exposure exceeded an ALARA limit in 2013.

Personnel dosimetry was obtained by review of the 2013 Landauer dosimetry reports. These reports include, where appropriate, whole body OSL dosimetry and finger TLD dosimetry.

Landauer is a NVLAP accredited dosimetry company.

OCCUPATIONAL EXPOSURES GROUP NUMBER Average Average Whole Body Extremity BADGED Dose Dose

(<500mrem)

(<5000 mrem)

Reactor 19 M

1

• NOTE: 'M' indicates no detectable releases or exposure

2.

Radiation and Contamination Surveys A review of all 2013 Research Reactor Radiation Survey and Contamination forms found no measurable removable contamination levels in the facility. The byproduct materials license specifies contamination as Ž_500 dpm/100cm 2 (beta) or Ž50 dpm/1OOcm 2 (alpha). No appreciable stray radiation fields (>2mR/hr) were identified in a free area within the reactor. Radiation levels measured in the reactor building have been typically less than 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, visual 7

and audial notifications, and/or personnel access control. The pump room remains designated as a high radiation area during reactor operation and access is controlled.

H. NATURE AND AMOUNT OF RADIOACTIVE WASTES

1.

Liquid Wastes and Gaseous Wastes As part of UMass Lowell ALARA goals, the radiation safety office has set a campus goal of limiting exposures to members of the public to less than 10% of the federal regulatory limits.

No radioactive material was released through the reactor sewer (no tank discharges in 2013).

Argon-41 continues to be the only significant reactor produced radioactivity identifiable in the gaseous effluent. The reactor stack released roughly 3.95 Ci in 2013 resulting in a (conservative) estimated upper limit to the TEDE of 0.1 mrem/year 100 m from the stack.

ENVIRONMENTAL RELEASES SOURCE ACTIVITY DOSE GOAL Ci mrem mrem Sewer Releases 0

M*

<__10 Stack Releases 3.95 M*

• 10

• NOTE: 'M' indicates no detectable releases or exposure

2.

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 induced radioactivity. These wastes were held for decay and then released if no activity remained. A waste shipment occurred on 6/21/13 *(43 cubic feet of radioactive metal and lab waste) and was sent for proper radioactive waste disposal. The remaining long lived wasted (<20 cubic feet) is stored in a designated long lived waste storage area awaiting ultimate disposal at low-level radioactive waste disposal site.

End of Report 8