ML042660200

Annual Report for Mit Research Reactor for the Period July 1, 2003 to June 30, 2004

ML042660200
Person / Time
Site:	MIT Nuclear Research Reactor
Issue date:	09/03/2004
From:	Bernard J, Lau E, Newton T Massachusetts Institute of Technology (MIT)
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML042660200 (31)

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NUCLEAR REACTOR LABORATORY AN INTERDEPARTMENTAL CENTER OF MASSACHUSETTS INSTITUTE OF TECHNOLOGY Edward S. Lau 138 Albany Street, Cambridge, MA 02139-4296 Activation Analysis Reactor Superintendent Telefax No. (617) 253-7300 Coolant Chemistry Tel. No. (617) 253-4211. Nuclear Medicine Reactor Engineering September 3, 2004 U.S. Nuclear Regulatory Commission, Washington, D.C. 20555 ATTN: Document Control Desk

Subject:

Annual Report, Docket No. 50-20, License R-37, Technical Specification 7.13.5 Gentlemen:

Forwarded herewith is the Annual Report for the MIT Research Reactor for the period July 1, 2003 to June 30, 2004, in compliance with paragraph 7.13.5 of the Technical Specifications for Facility Operating License R-37.

'V -

Thomas H. Newton, Jr., PE Edward S. Lau, NE Reactor Engineer Superintendent MIT Research Reactor MIT Research Reactor hn A. Bernard, Ph.D. PE, CHP Director of Reactor Operations MIT Research Reactor JAB/gw

Enclosure:

As stated cc: USNRC - Senior Project Manager, Research and Test Reactors Section New, Research and Test Reactors Program Division of Regulatory Improvement Programs, ONRR USNRC - Senior Reactor Inspector, ADo(

Research and Test Reactors Section New, Research and Test Reactors Program Division of Regulatory Improvement Programs, ONRR

MIT RESEARCH REACTOR NUCLEAR REACTOR LABORATORY MASSACHUSETTS INSTITUTE OF TECHNOLOGY ANNUAL REPORT to United States Nuclear Regulatory Commission for the Period July 1, 2003 - June 30, 2004 by REACTOR STAFF

Table of Contents Section Page Introduction................................................................................................................... 1 A. Summary of Operating Experience. 3 B. Reactor Operation .10 C. Shutdowns and Scrams .11 D. Major Maintenance .13 E. Section 50.59 Changes, Tests, and Experiments .16 F. Environmental Surveys .21 G. Radiation Exposures and Surveys Within the Facility .22 H. Radioactive Effluents .23 I. Summary of Use of Medical Facility for Human Therapy .27

MIT RESEARCH REACTOR ANNUAL REPORT TO U. S. NUCLEAR REGULATORY COMMISSION FOR THE PERIOD JULY 1. 2003 - JUNE 30 2004 INTRODUCTION This report has been prepared by the staff of the Massachusetts Institute of Technology Research Reactor for submission to the United States Nuclear Regulatory Commission, in compliance with the requirements of the Technical Specifications to Facility Operating License No. R-37 (Docket No. 50-20), Paragraph 7.13.5, which requires an annual report following the 30th of June of each year.

The MIT Research Reactor (M1TR), as originally constructed, consisted of a core of MTR-type fuel, enriched in uranium-235 and cooled and moderated by heavy water in a four-foot diameter core tank, surrounded by a graphite reflector. After initial criticality on July 21, 1958, the first year was devoted to startup experiments, calibration, and a gradual rise to one megawatt, the initially licensed maximum power.

Routine three-shift operation (Monday-Friday) commenced in July 1959. The authorized power level was increased to two megawatts in 1962 and to five megawatts (the design power level) in 1965.

Studies of an improved design were first undertaken in 1967. The concept which was finally adopted consisted of a more compact core, cooled by light water, and surrounded laterally and at the bottom by a heavy water reflector. It is under-moderated for the purpose of maximizing the peak of thermal neutrons in the heavy water at the ends of the beam port re-entrant thimbles and for enhancement of the neutron flux, particularly the fast component, at in-core irradiation facilities. The core is hexagonal in shape, 15 inches across, and utilizes fuel elements which are rhomboidal in cross section and which contain UALx intermetallic fuel in the form of plates clad in aluminum and fully enriched in uranium-235. Much of the original facility, e.g., graphite reflector, biological and thermal shields, secondary cooling systems, containment, etc., has been retained.

After Construction Permit No. CPRR-1 18 was issued by the former U.S.

Atomic Energy Commission in April 1973, major components for the modified reactor were procured and the MITR-I completed its mission on May 24, 1974, having logged 250,445 megawatt hours during nearly 16 years of operation.

The old core tank, associated piping, top shielding, control rods and drives, and some experimental facilities were disassembled, removed, and subsequently replaced with new equipment. After preoperational tests were conducted on all systems, the

2 U.S. Nuclear Regulatory Commission issued Amendment No. 10 to Facility Operating License No. R-37 on July 23, 1975. After initial criticality for MITR-l on August 14, 1975, and several months of startup testing, power was raised to 2.5 MW in December. Routine 5-MW operation was achieved in December 1976. Three shift operations, Monday through Friday, was continued through 1995 when a gradual transition to continuous operation (24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> per day, 7 days per week with a shutdown for maintenance every 4-5 weeks) was initiated. The current operating mode is continuous operation at full power.

In July 1999, an application to relicense the reactor for twenty years and to upgrade its power level to 6 MW was submitted to the U.S. Nuclear Regulatory Commission. That request is now being processed. In December 2000, a fission converter medical facility was commissioned. This facility generates the best epithermal beam in the world for use in the treatment of certain types of cancer.

This is the twenty-ninth annual report required by the Technical Specifications, and it covers the period July 1, 2003 through June 30, 2004. Previous reports, along with the "MIITR-ll Startup Report" (Report No. MITNE-198, February 14, 1977) have covered the startup testing period and the transition to routine reactor operation. This report covers the twenty-seventh full year of routine reactor operation at the 5-MW licensed power level. It was another year in which the safety and reliability of reactor operation met and exceeded requirements and expectations.

A summary of operating experience and other activities and related statistical data are provided in Sections A through I of this report.

3 A.

SUMMARY

OF OPERATING EXPERIENCE

1. General The MIT Research Reactor, MITR-ll, is operated to facilitate experiments and research including medical studies and clinical trials, bulk material irradiation testing and damage studies, and neutron activation analyses. It is also used for student laboratory exercises and student operator training, and accommodates the medical program on boron neutron capture therapy for cancer-treatment studies. When operating, the reactor is normally maintained at a nominal 5 MW. For this reporting period, the reactor full power operating cycle continued to be four weeks at a time, followed by a shutdown lasting half a day to five days, for reactor and experiment maintenance and other necessary outage activities. The reactor would then be re-started to full power and maintained there for another four to five weeks. The period covered by this report is the twenty-seventh full year of normal operation for MITR-_I.

The reactor averaged 94 hours0.00109 days <br />0.0261 hours <br />1.554233e-4 weeks <br />3.5767e-5 months <br /> per week at power compared to 129 hours0.00149 days <br />0.0358 hours <br />2.132936e-4 weeks <br />4.90845e-5 months <br /> per week for the previous year and 133 hours0.00154 days <br />0.0369 hours <br />2.199074e-4 weeks <br />5.06065e-5 months <br /> per week two years ago. The lower number of average hours per week was due to a shutdown from July 25 through September 25, 2003, and a two-week MIT institute closing in late December 2003 to early January 2004, followed by an additional two weeks for replacement of the primary and secondary main pumps.

The reactor was operated throughout the year with 24 elements in the core.

The remaining three positions were occupied by solid aluminum dummies or in-core experiments. During FY2004, compensation for reactivity lost due to burnup was provided by three refuelings. These followed standard MITR practice which is to introduce fresh fuel to the inner portion of the core (the A- and B-Rings) where peaking is least and to place partially spent fuel in the outer portion of the core (the C-Ring). In addition, elements were inverted and rotated so as to achieve more uniform bumup gradients in those elements. Nine new elements were introduced into the reactor core during FY2004.

The MITR-ll fuel management program remains quite successful. All of the original MITR-ll elements (445 grams U-235) have been permanently discharged. The overall bumup for the discharged elements was 42%. (Note: One element was removed prematurely because of excess out-gassing.) The maximum overall bumup achieved was 48%. A total of one hundred fifty-one of the newer, MITR-II elements (506 grams U-235) have been introduced to the core. Of these, eighty-three have attained the maximum allowed fission density and were discharged. However, some of these may be reused if that limit is increased as would seem warranted based on metallurgical studies by DOE. Seven elements have been identified as showing excess out-gassing and two are suspected of this. All nine have been removed from service and returned to an off-site DOE storage facility. The other fifty-nine are either currently in the reactor core, in the fission converter tank, or have been partially depleted and are in the wet storage ring awaiting reuse. During the period of FY2004, no spent elements were returned to an off-site DOE facility.

4 Protective system surveillance tests are conducted whenever the reactor is scheduled to be shut down.

As in previous years, the reactor was operated throughout the period without the fixed hafnium absorbers, which were designed to achieve a maximum peaking of the thermal neutron flux in the heavy water reflector beneath the core. These had been removed in November 1976 in order to gain the reactivity necessary to support more in-core experiment facilities.

2. Experiments The MrTR-ll was used throughout the year for experiments and irradiations in support of research, training and education programs at MIT and elsewhere.

Experiments and irradiations of the following types were conducted:

a) Use of the Fission Converter facility for animal and drug studies funded by

[NIB as a part of the Boron Neutron Capture Therapy research effort to treat cancer tumors.

b) High sensitivity neutron activation analysis of rare-earth elements in various host materials for Naval Research Laboratory.

c) Activation of gold foils and iron wires for thermal neutron flux calibration for MITR's pneumatic tubes and 3GV beam ports.

d) Activation of yttrium foils for an on-going DOE clinical trial at the Massachusetts General Hospital for spinal cord cancer removal therapy.

e) Production of gold-198 and copper-64 seeds for DOE and NIH clinical trials /

medical research at the Boston Children's Hospital.

f) Production of iodine-125 seeds in xenated silicon chips and vascular stents with activated iridium-1 92 for DOE clinical trials at the Massachusetts General Hospital for medical research.

g) Study of BPA drug uptake and distribution pattern in live animals using the reactor's 4DH1, 4DH3, Fission Converter, and Thermal Beam facilities. These analyses support neutron capture therapy and studies of radiation synovectomy for treatment of arthritis.

h) High sensitivity neutron activation analyses of scintillator detection medium in support of U.S. and international projects on double-beta decay research (partially funded by DOE).

5 i) Activation of uranium foils for detector calibration at the Los Alamos National Laboratories, New Mexico, and other national DOE facilities.

j) Gamma activation of ammonium hydroxide solutions for polymerization studies by General Electric.

k) Autism studies using neutron activation analysis to measure mercury and other trace elements in human hair and biopsy-derived brain tissues.

1) Neutron activation of thulium on nucleopore filters for marine biology and oceanic sediment studies at the Woods Hole Oceanographic Institute.

m) Measurements of leakage neutron energy spectrum to determine reactor temperature using a mechanical chopper in the 4DH1 radial beam port facility.

Measurement of neutron wavelength by Bragg reflection permits demonstration of the DeBroglie relationship for physics courses at MIT and other universities. Time-of-flight measurements are also -performed by students from the MIT Nuclear Engineering Department.

n) Gamma irradiation of seeds and perishable foods for demonstration of radiation effects on plants and organic substances.

o) Use of the reactor's 3GV facility at low power to perform track-etch analyses of brain tissues treated with a boron-containing drug for microdosimetry study.

p) Irradiation of geological materials to determine quantities and distribution of fissile materials using solid state nuclear track detectors.

q) Use of the reactor's 3GV facility to activate geological samples for earth, atmospheric and planetary studies.

r) Use of in-core irradiation location for shadow corrosion studies.

s) Neutron activation of standard environmental materials containing trace amount of natural uranium for the US DOE New Brunswick Laboratory in a national program for laboratory capabilities assessment.

t) Neutron activation of thorium foils to study neutron transmutation properties of long-lived radioactive waste.

u) Neutron activation of aluminum and tin specimens to determine iron oxide contamination for geological studies at Harvard University.

v) Use of the reactor facility for training of MIT student reactor operators and for nuclear engineering classes (22.09/22.104 - Principles of Nuclear Radiation Measurement and Protection, and 22.06 - Engineering of Nuclear Systems),

and a Junior Physics lab course (8.13/8.14).

6 In addition to the above list, the MIT reactor has been used to provide fission-spectrum neutron irradiation in the core for dose reduction studies for the light-water nuclear power industry. Beginning in 1989, after much planning and out-of-core evaluation, the MIT reactor has designed and operated nine in-core experiments.

These studies entail installing experimental cooling loops in the reactor core to investigate the chemistry of corrosion and the transport of radioactive crud. Loops that replicate both pressurized (PWR) and boiling water reactors (BWR) were built. The PWR loop has been operational since August 1989. The BWR loop became operational in October 1990. A third loop, one for the study of irradiation-assisted stress corrosion cracking (IASCC), became operational in June 1994. A fourth one, also for the study of crack propagation (SENSOR), began operation in April 1995.

An experiment using the IASCC thimble was installed in-core in February 1999 to study cross-corrosion behaviors of various metal specimens placed in close proximity (shadowing). The first of these experiments was successfully completed in June 1999. Another in-core experiment re-using the IASCC thimble was conducted throughout September and October 2000, irradiating and investigating behavior of new materials (ceramic fiber composites) for cladding of PWR power reactor fuel, with post-irradiation study performed at the reactor facility during 2001. In early 2003, another shadow corrosion experiment operated in-core for a month using this thimble.

A second phase of this shadow corrosion experiment began in early 2004 and was successfully completed in May 2004. A third phase was also successfully completed from May to June 2004, measuring electro-chemical potential difference between Zircaloy and Inconel specimens under neutron and gamma irradiation conditions, to evaluate effects that could reduce shadow corrosion.

In February 2004, a new type of in-core experiment was installed to test performance of innovative annular fuel designs as a part of the Generation-IV power reactor research effort by the MIT Nuclear Engineering Department. This experiment Will continue into FY2005. It is the first irradiation of a fueled test capsule at the MiT reactor, and one of very few undertaken at any university reactor.

Another major resear6h effort ongoing during FY2004 is the Boron Neutron Capture Therapy (BNCT) project. This project is making extensive use of the reactor's fission converter facility, the prompt gamma facility, and the thermal neutron beam facility for drug testing and characterization using cell culture, tissues, and lab mice.

The fission converter facility was also used at the beginning of FY2004 for one more FDA Phase I / II human clinical trial for study of BNCT treatment of glioblastoma (brain cancer) and melanoma (skin cancer). Funding for these clinical trials is provided by the National Institute of Health. Construction of the fission converter facility was funded by DOE and completed by NRL staff in autumn 2000. Major peripheral equipment installation was completed in FY2001. In FY2002 and FY2003, it was used primarily for beam and drug studies by national and international groups.

Many of the beam and drug studies were performed as preparation for BNCT clinical trials. The clinical trials at MIT are a collaborative effort with the Beth Israel-

7 Deaconess Medical Center which is affiliated with the Harvard Medical School. See Section I for more details on the BNCT clinical trial program.

As part of the BNCT project, the epithermal neutron beam at the reactor basement's original medical facility was converted into a thermal beam during FY2002. In FY2003, installation of Ricorad shielding along the thermal beam medical room's inner wall adjacent to the reactor's equipment room was completed, in order to improve shielding to minimize radiation interference in the thermal beam room during operation of the fission converter facility. Construction of a full-size control console away from the outer wall of the thermal beam facility was completed, replacing the original beam control panel. In FY2004, new lighting and wall surfaces inside the medical room were installed.

3. Changes to Facility Design Except for minor changes reported in Section E, no changes in the facility design were made during the year. As indicated in past reports the uranium loading of MITR-ll fuel was increased from 29.7 grams of U-235 per plate and 445 grams per element (as made by Gulf United Nuclear Fuels, Inc., Connecticut) to a nominal 34 and 510 grams respectively (made originally by the Atomics International Division of Rockwell International, California, now by BWX Technologies, Inc., Virginia). With the exception of seven elements (one Gulf, six Al) that were found to be out-gassing excessively, performance of these fuel elements has been good. (Please see Reportable Occurrence Reports Nos. 50-20/79-4, 50-20/83-2, 50-20/85-2, 50-20/86-1, 50-20/86-2, 50-20/88-1, and 50-20/91-1.) The heavier loading results in 41.2 w/o U in the core, based on 7% voids, and corresponds to the maximum loading in Advanced Test Reactor (ATR) fuel. Atomics International completed the production of forty-one of the more highly loaded elements in 1982. Of the forty elements that were used to some degree, thirty-two with about 40% burnup have been discharged because they have attained the fission density limit. Of the other eight, six were, as previously reported to the U.S. Nuclear Regulatory Commission, removed from service because of excess out-gassing and two were removed because of suspected excess out-gassing.

One hundred eleven elements fabricated by BWXT have been received, fifty-nine of which remain in use. One has been removed because of suspected excess out-gassing and fifty-one have been discharged because they have attained the fission density limit.

The MITR staff has been following with interest the work of the Reduced Enrichment for Research and Test Reactors (RERTR) Program at Argonne National Laboratory, particularly the development of advanced fuels that will permit uranium loadings up to several times the recent upper limit of 1.6 grams total uranium/cubic centimeter. Consideration of the thermal-hydraulics and reactor physics of the MITR-II core design show that conversion of MITR-II fuel to lower enrichment must await the successful demonstration of the proposed advanced fuels.

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4. Changes in Performance Characteristics Performance characteristics of the MITR-ll were reported in the "MITR-ll Startup Report." Minor changes have been described in previous reports. There were no changes during the past year. Performance characteristics of the Fission Converter Facility were reported in the "Fission Converter Facility Startup Report".

5. Changes in Operating Procedures With respect to operating procedures subject only to MITR internal review and approval, a summary is given below of those changes implemented during the past year. Those changes related to safety and subject to additional review and approval are discussed in Section E of this report.

a) PM 1.16.2, "MITR Operations Qualification Program for Senior Operators /

Shift Supervisors," and PM 1.16.2, "MITR Operations Qualification Program for Operators," updated the 'qual cards' for the training program to reflect current equipment and practices. Items related to systems and facilities that no longer exist were eliminated; the material covered was not reduced in any other way. (SR#-0-04-5) b) PM 1.19.2, "U-235 Inventory Projection and Verification," created a procedure to verify that projected U-235 inventory does not exceed the R-37 license limit when new fuel elements are ordered. (SR#-0-04-9) c) PM 3.1.2.1, "One Loop Startup (Loop 1A), Mechanical, t" and PM 3.1.2.2, "One Loop Startup (Loop IA), Instrumentation," updated the one-loop startup checklists to reflect current equipment and practices. (SR#-0-03-9) d) PM 3.2.1, "Shutdown from Operation at Power," updated the shutdown checklist to reflect current equipment and practices, primarily as they relate to the secondary system cooling towers and the new main pumps with variable frequency drive controllers. (SR#-0-00-2, SR#-0-04-3) e) PM 3.5, "Daily Surveillance Checklist," updated the 'morning check' to reflect current equipment and practices, especially relating to the secondary system and its cooling towers. Several minor new checks to monitor various systems were added as well. (SR#-0-99-6, SR#-0-02-7) f) PM 7.4.4.6, "Replacement of MM-1 Shaft Seal," updated a maintenance procedure to add detail to the steps, add new sections such as lists of tools and equipment, and add a table to record valve positions. (SR#-0-03-6)

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6. Surveillance Tests and Inspections There are many written procedures in use for surveillance tests and inspections required by the Technical Specifications. These procedures provide a detailed method for conducting each test or inspection and specify an acceptance criterion which must be met in order for the equipment or system to comply with the requirements of the Technical Specifications. The tests and inspections are scheduled throughout the year with a frequency at least equal to that required by the Technical Specifications. Thirty such tests and calibrations are conducted on an annual, semi-annual, or quarterly basis.

Other surveillance tests are done each time before startup of the reactor if shut down for more than 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br />, before startup if a channel has been repaired or de-energized, and at least monthly; a few are on different schedules. Procedures for such surveillance are incorporated into daily or weekly startup, shutdown or other checklists.

During the reporting period, the surveillance frequency has been at least equal to that required by the Technical Specification, and the results of tests and inspections were satisfactory throughout the year for Facility Operating License No. R-37.

7. Status of Spent Fuel Shipment In FY2004, no shipments were completed, because of the need to address the requirements of the shipping interim compensatory measures issued by NRC on October 3, 2002. MIT expects this matter to be resolved early in FY2005.

10 B. REACTOR OPERATION Information on energy generated and on reactor operating hours is tabulated below:

Quarter 1 2 l 3 l 4 Total I l 1. Energy Generated (MWD):

a) M 89.2 226.8 194.8 283.6 794.4 (MIT FY2004)

(normally at 4.9 MW) b) MITR-ll2,7.

(MIT FY1976-2003) 23,875.4 c) MITR-I 10,435.2 (MIT FY1959-1974) d) Cumulative, 35,105.0 MITR-I & MITR-l,

2. MITR-ll Operation (hours):

(MIT FY2004) a) At Power

(>0.5-MW) for 628.7 1471.9 1213.1 1618.8 4932.5 Research b) Low Power

(<0.5-MW) for 31.2 14.3 52.7 42.0 140.2 Training(l) and Test c) Total Critical 659.9 1486.2 1265.8 1660.8 5072.7 (1) These hours do not include reactor operator and other training conducted while the reactor is at full power for research purposes (spectrometer, etc.) or for isotope production. Such hours are included in the previous line.

11 C. SHUTDOWNS AND SCRAMS During the period of this report there were 9 inadvertent scrams and 10 unscheduled shutdowns.

The term "scram" refers to shutting down of the reactor through protective system action when the reactor is at power or at least critical, while the term "shutdown" refers to an unscheduled power reduction to subcritical by the reactor.

operator in response to an abnormal condition indication. Rod drops and electric power loss without protective system action are included in unscheduled shutdowns.

The following summary of scrams and shutdowns is provided in approximately the same format as for previous years in order to facilitate a comparison.

1. Nuclear Safety System Scrams Total a) High power level trip on Channel #6 as result of overly conservative setting by operator error. 1 b) Fission converter trip on experimenter testing/training error. 2 c) Spurious trip from noise in fission converter circuitry. 1 Subtotal 4

2. Process System Scrams a) High temperature trip from loss of cooling tower fans due to software error. 2 b) Low flow primary trip upon failure of pump MM-I shaft. 1 c) Low flow secondary trip upon freeze-up of cooling tower sump level controller. 1 d) Low flow secondary trip from cavitation due to air entrained in city water make-up feed. 1 Subtotal 5

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3. Unscheduled Shutdowns a) Shutdown due to loss of offsite electricity. 3 b) Shutdown due to drops of shim blades (#1, #2). 4 c) Shutdown to examine pump DM-2. 1 d) Shutdown due to preliminary finding of fission products in experiment cover gas sample. 1 e) Shutdown due to broken natural gas main at NW12 sidewalk. 1 Subtotal 10 Total 19

4. Experience during recent years has been as follows:

Fiscal Year Scrams 2000 18 2001 17 2002 8 2003 17 2004 9

13 D. MAJOR MAINTENANCE Major maintenance projects performed during FY2004 are described in this Section. Much maintenance was performed to continue the safe, reliable and efficient operation of the MIT Research Reactor, to systematically replace the reactor neutron absorber shim blades, and their drive mechanisms and shim blade magnets, and as preventive effort to upgrade reactor equipment and instrumentation before major degradation. Other maintenance effort was made to support in-core experiments (installation, removal, radiation shielding, repair, gas purge and sampling), irradiated sample analyses, and renovation of the thermal neutron beam facility at the Reactor Basement for advanced BNCT drug studies and certain types of BNCT human clinical trials.

The repair and maintenance of machinery and computer control and monitoring software and hardware for neutron transmutation doping of silicon (NTD Si) also required continued support. This machinery, installed in two of the reactor through-ports, includes two twenty-foot tubes for each port, rotating and pushing mechanisms, billet handling and storage conveyors, electronics, and associated microprocessor-based controllers and computer tracking systems. It was constantly operating whenever the reactor was at power throughout this fiscal year.

Major maintenance items performed in FY2004 were summarized as follows:

1) Shim blade #1, #3, #4, #5 and #6 boron-stainless steel blades were replaced during FY2004. Their guide rods, armature and offset plates were also replaced.

Shim blade #1; #3 and #6 drive mechanisms were rebuilt. Shim blade #1 and #3 electromagnets were replaced as a preventive maintenance measure. (Shim blade #2 and the regulating rod systems will be replaced in FY2005.)

2) The two main reactor primary coolant pumps were replaced with high-output, energy efficient stainless steel pumps with variable frequency drive controllers.

All associated piping, some valves and some pressure gages were also replaced to conform to the ANSI standards of the pumps.

3) The two main reactor secondary coolant pumps were replaced with high-output, energy efficient stainless steel pumps with variable frequency drive controllers.

All associated piping, some valves and some pressure gages were also replaced to conform to the ANSI standards of the pumps.

4) Gaskets for the reactor containment building's main and auxiliary ventilation intake and exhaust butterfly dampers were replaced.

5) The reactor cooling tower units #1 and #2 were retrofitted with new and upgraded cascade structure and material to improve air flow and cooling efficiency. All eight fan motors of unit #1 were rebuilt, their fan guards replaced with new frames that allow quick-disconnect for ease of access to motor maintenance. All eight water spray / distributor nozzles were upgraded with new rotating units for

14 better cascade distribution. All water seals at the base of the unit were stripped and renewed. Similar actions are continuing for cooling tower unit #2 in FY2005.

6) Reactor floor Hot Cell and Hot Box manipulators were upgraded and refurbished to handle special in-core experiment specimens.

7) A new ventilation duct now links the Hot Box to the Hot Cell HEPA filter ventilation exhaust, which was refurbished for higher air flow. New delta-P manometers are installed for air flow monitoring for both the Hot Cell and Hot Box. The Hot Box has also been equipped with heat sensor and fire suppression units. This work is performed in anticipation of Hot Box and Hot Cell uses for post-irradiation examinations for the annular fuel experiment and other in-core experiments. It is funded by the DOE INIE Program.

8) The perchloric acid hood in the reactor engineering lab was refurbished and its water purge line repaired, for use by reactor coolant corrosion loop experimenters for post-irradiation sample examinations.

9) A double door and three fireproof reinforced steel doors (Fleming, Series H) in various NW12 entrances are now equipped with card-readers as a new security measure for reactor administrative areas. Some access areas are also .now equipped with video surveillance and remote actuation devices.

10) The NW12 parking lot gate was automated to operate with remote transponders.

The personnel gate access is also card-controlled. For the automation work, a three-foot deep trench almost 70 feet long was dug out from the administration building for HV electrical and signal cabling.

11) The reactor emergency battery bank was cleaned with acid neutralizer. Inspection (all emergency lighting) and repair (DC ammeters) were also completed.

12) Stack blowers #1 and #2 were replaced. The equipment room air-sampler pump and flow lines and the plenum blower air flow lines were replaced. The air flow monitor was also adjusted.

13) All three main reactor heat exchangers were chemically cleaned with inhibited phosphoric acid (10% strength) mixed with anti-foaming agents and corrosion inhibitors. The heat exchanger HE-1A had previously developed a small tube leak. After the chemical cleaning, two leaky tubes (out of -900 tubes) were identified using helium leak detection technique and were then isolated. The cleaning of the heat exchangers improved the reactor cooling capability significantly.

14) Gamma dose in the spent fuel storage pool was optimized by new placement of elements. The axial and radial gamma fields were characterized for irradiations.

15

15) The two reactor waste water holding tanks were chemically cleaned to eliminate buildups. Their level probes were individually cleaned with chemicals.

16) The reactor Machine Shop (NW13) was refurbished after two months of outside contractor activities in the Shop to install MIT steam supply pipes for Novartis.

17) A new spent fuel element handling tool was designed, fabricated, and tested. The new tool is 20 feet long and is equipped with a locking mechanism to positively secure the element during handling.

18) A boiler assembly for out-of-core testing of older loop experiments was disassembled. This test rig goes through a floor and spans the height of two stories. It was removed and dismantled for storage to provide space for a new test rig to be installed for testing of a high-temperature gas loop experiment.

19) The electrical heating system for one of the four liquid CO2 supply tanks was replaced. It had been in service since 1995. New style, higher energy efficiency and higher capacity tanks are being reviewed.

20) The secondary coolant flow meter HF-3 was replaced. A large section of its associated piping was also replaced. This meter is used primarily to provide indication of secondary coolant flow for reactor shutdown alignment.

21) The reactor shield coolant flow meter was replaced. The original meter developed a leak after more than fifteen years of use and was beyond repair. The new meter provides remote readout of shield coolant flow in the control room.

22) Reactor primary coolant system valves MV-4A and MV-43 were rebuilt. The latter controls primary cleanup flow during full power and shutdown operations.

23) Several major pressure gages in reactor coolant systems were replaced as preventive maintenance. Pressure snubbers to reduce "chattering" in MP-6 and MP-6A pressure gages were also replaced and tested.

24) Fan belts for the core purge blower, the D2 0 helium recombiner blower, the reactor floor Hot Cell blower, and the primary chemistry hood blower were replaced.

Many other routine maintenance and preventive maintenance items were scheduled and completed throughout the fiscal year.

16 E. SECTION 50.59 CHANGES. TESTS. AND EXPERIMENTS This section contains a description of each change to the facility or procedures and of the conduct of tests and experiments carried out under the conditions of Section 50.59 of 10 CFR 50, together with a summary of the safety evaluation in each case.

The review and approval of changes in the facility and in the procedures as described in the SAR are documented in the M1TR records by means of "Safety Review Forms." These have been paraphrased for this report and are identified on the following pages for ready reference if further information should be required with regard to any item. Pertinent pages in the SAR have been or are being revised to reflect these changes, and they either have or will be forwarded to the Document Control Desk, USNRC.

The conduct of tests and experiments on the reactor are normally documented in the experiments and irradiation files. For experiments carried out under the provisions of 10 CFR 50.59, the review and approval is documented by means of the Safety Review Form. All other experiments have been done in accordance with the descriptions provided in Section 10 of the SAR, "Experimental Facilities."

17 Experiments Related to Neutron Capture Therapy SR#0-89-4 (01/23/89), #0-89-8 (03/01/89), #0-91-7 (05/06/91), #0-91-17 (03/06/92),

1. 0-92-3 (03/06/92), #0-92-4 (03/02/92), #M-92-2 (05/14/92), #0-93-5 (05/28/93),

1. 0-93-9 (07/13/93), #0-93-20 (11/30/93), #0-94-19 (12/02/94), #0-96-5 (05/03/96),

1. 0-97-2 (02/18/97), #0-97-11 (08/14/97), #0-97-13 (09/23/97), #0-97-14 (10/03/97),

1. M-98-1 (01/30/98), #0-98-5 (06/24/99) #0-99-7 (02/02/00), #M-00-1 (03/29/00),

1. 0-00-7 (07/28/00), #0-01-1 (02/16/01), #M-01-1 (03/28/01), #0-01-8 (03/25/03),

1. 0-02-1 (10/22/02), #0-02-2 (02/01/02), #0-04-7 (05/06/04)

In conjunction with the Tufts - New England Medical Center (NEMC) and with the support of the U.S. Department of Energy, MUT has designed an epithermal neutron beam for the treatment of brain cancer (glioblastoma). Thermal beams have been used successfully for this treatment in Japan. The reason for designing an epithermal beam is to allow tumor treatment without having to subject the patient to surgery involving removal of a portion of the skull. Also, an epithermal beam gives greater penetration. In October 1991, MIT' hosted an international workshop for the purpose of reviewing proposed beam designs and dosimetry. Subsequent to the receipt of advice from the workshop panel members, a final design was selected for the epithermal filter for the MIT Research Reactor's Medical Therapy Facility beam.

Approvals of the protocol for the conduct of patient trials were received from all requisite MIT and NEMC Committees as well as from the U.S. Food and Drug Administration. Also, a license amendment and quality management plan for use of the MIT Research Reactor's Medical Therapy Facility was issued by the U.S. Nuclear Regulatory Commission as License Amendment No. 27 on February 16, 1993.

Subsequent to the receipt of that license amendment and a similar one in August 1993 for our medical partner, the Tufts - New England Medical Center, procedures for performing BNCT and a preoperational test package were prepared.

The latter was completed during FY94.

Patient trials were initiated in September 1994 as part of a Phase I effort that is required by the FDA. In December 1994, changes were issued to certain of the procedures that had been prepared for conduct of the irradiations. These changes were intended to reduce the signature burden on senior personnel during the trials so that their full attention could be given to the human subject.

Three subjects were irradiated in FY95. One more was done in FY96 in conjunction with NEMC. A change of medical partners then occurred, after which a second irradiation was done in FY96. The new program was a joint effort between MIT and the New England Deaconess Hospital (NEDH), which was affiliated with the Harvard Medical School. This change necessitated an amendment to the NEDH's license for radioactive materials and their use, as well as to the various internal approvals. Subsequent to receipt of these licenses/approvals, the Phase I trial for melanoma was continued. Also, a separate Phase I protocol for glioblastoma multiforme was approved. Patient trials under that protocol were initiated in July

18 1996. In FY97, New' England Deaconess Hospital merged with the Beth Israel Hospital. The resulting organization is Beth Israel - Deaconess Medical Center, which is now also a major teaching hospital for the Harvard Medical School. Under the new partnership, a total of twenty-two human subjects were irradiated through April 1999 up to a dose level of 1420 RBE-cGy.

Technical Specification #6.5, "Generation of Medical Therapy Facility Beam for Human Therapy," and its associated BNCT Quality Management Program were updated in FY97. The change was purely administrative in nature. No substantive changes of any type resulted. The language update in the two documents was to reflect transition from NRC regulation to State regulation of medical use licensees, and thereby to prevent any possible subsequent disruption of the ongoing BNCT research program due to such administrative shift. The change allows MIT to conduct BNCT on human subjects from both NRC and Agreement State (the Commonwealth of Massachusetts) medical use licensees whose licenses contain BNCT-specific conditions and commitments for BNCT clinical trials on human subjects conducted at the MIT reactor. The change was approved by the NRC on April 3, 1997.

On October 3, 1997, a Safety Evaluation Report and associated Technical Specifications were submitted to NRC for the design and construction of a new Medical Therapy Facility utilizing a Fission Converter. Approval for operation of the new facility was received in December 1999. Fuel was loaded into the facility in April 2000 and startup testing was completed by August 2000. This new facility provides MIT with the best epithermal neutron beam for BNCT in the world. Approval to use this beam for patient irradiations was received from the U.S. Nuclear Regulatory Commission on April 2, 2001. Clinical trials of BNCT for both deep-seated melanoma and glioblastoma that use the new fission converter beam began in October 2002 under the auspices of the National Institutes of Health. As of June 30, 2004, one patient with deep-seated melanoma and six patients with glioblastoma multiforme have been irradiated with this beam.

19 Fission Converter SR#0-97-14 (10/03/97), #M-98-1 (01/30/98), #0-98-5 (06/24/99), #0-99-7 (02/02/00),

1. M-00-1 (03/29/00), #0-00-7 (07/28/00), #0-01-1 (02/16/01), #M-01-1 (03/28/01),

1. 0-01-8 (03/25/03), #0-02-1 (10/22/02), #0-02-2 (02/01/02), #0-04-7 (05/06/04)

The safety evaluation report and technical specifications for the fission converter were submitted to the U.S. Nuclear Regulatory Conmmission on October 3, 1997. Approval was received on 21 December 1999. A startup report was submitted on 1 September 2000. Requests for minor changes to some of the test and calibrations of the associated process systems are were approved in March 2003. A lithium metal filter was installed in May 2004 for the purpose of further optimizing the energy spectrum of the neutron beam. This filter is sealed in an aluminum frame and, when not in use, is stored in a protective case outside the fission converter facility. It is tested periodically to verify the absence of leakage. Precautions are in place should there be any leakage.

In-Core Irradiation of Fissile Materials SR#0-01-11 (04/16/03), #0-01-12 (04/16/03), #0-02-8 (02/27/04), #0-03-7 (03/02/04),

1. 0-04-2 (03/02/04)

Technical Specifications for fueled experiments were approved by the U.S.

Nuclear Regulatory Commission on April 16, 2003. A safety evaluation report was prepared for the first such experiment and it has now been operating without difficulty since early in 2004.

Zircaloy Corrosion Loop / EPRI Electro-Chemical Potential Loop SR#0-02-6 (02/26/03), #0-03-1 (02/26/03), #0-04-4 (05/17/04)

An in-core loop that replicates PWR conditions was installed for the purpose of evaluating 'shadow corrosion' in power production reactors. The design of this loop was within the envelope of previously-installed PWR-type loops. No new safety issues were raised. The loop operated in the spring of 2003 and again from early 2004 to the present.

Security Plan Update SR #0-03-10 (10/29/03), #0-04-1 (04/02/04)

The Physical Security Plan was updated to reflect the new equipment, current procedure frequencies, and general tightening of security that took place over the previous two years.

20 Shim Blade Drive Mechanism Modification SR #M-03-2 (06/16/04)

The blade drive design for the horizontal, lower, and upper tubes was modified to improve helium purge gas flow inside the drive mechanism, leak tightness from the reactor primary coolant, and ease of removal, maintenance, and re-installation.

Quick-Connect for MM-2 Suction SR #M-03-3 (05/20/04)

A quick-connect fitting was installed on the suction of MM-2 for use in certain emergency cooling configurations. A corresponding inspection procedure was established for the MM-2 suction strainer.

Replacement of Primary and Secondary Pumps SR #M-04-1 (01/14/04)

Primary pumps MM-1 and MM-IA were replaced with 60 HP variable frequency drive 6" x 4" ANSI high efficiency pumps. Secondary pumps HM-1 and HM-1A were replaced with 50 HP variable frequency drive pumps. The new pumps have greater reliability and future flexibility in operation.

Increase of U-235 Possession Limit SR #0-04-10 (06/28/04)

An increase in the U-235 possession limit was requested and received from the U.S. Nuclear Regulatory Commission. The new limit is in accordance with the MITR's relicensing request.

21 F. ENVIRONMENTAL SURVEYS Environmental monitoring is performed using continuous radiation monitors and dosimetry devices. The radiation monitoring system consists of G-M detectors and associated electronics at each remote site with data transmitted continuously to the Reactor Radiation Protection Office and recorded on strip chart recorders. The remote sites are located within a quarter mile radius of the facility. The detectable radiation levels per sector, due primarily to Ar-41, are presented below. Units located at east and south sector were inoperable periodically during the reporting period due to site renovations. These values are adjusted for the period(s) the sites were not operational.

Site Exposure (07/01/03 - 06/30104)

North 0.18 mrem East 0.15 mrem South 0.41 mrem West 0.18 mrem Green (east) 0.24 mrem Fiscal Year Averages 2004 0.2 mrem 2003 0.2 mrem 2002 0.3 mrem 2001 0.4 mremr 2000 0.2 mrem 1999 0.2 mrem

22 G. RADIATION EXPOSURE AND SURVEYS WITHIN THE FACILITY A summary of radiation exposures received by facility personnel and experimenters is given below:

July 1. 2003 - June 30. 2004 Whole Body Exposure Range (reins) Number of Personnel No measurable .................................................... 101 Measurable - <0.1 ............. ........................................ 57 0.1 - 0.25 .......................................................................................... 12 0.25- 0.5 .......................................................................................... 5 0.5 - 0.75 .......................................................................................... 0 0.75 - 1.00 .......................................................................................... 1 1.00 - 1.25 .......................................................................................... 0 Total Person Rem = 5.61 Total Number of Personnel = 176 From July 1, 2003 through June 30, 2004, the Reactor Radiation Protection Office provided radiation protection services for the facility which included power and non-power operational surveillance (performed on daily, weekly, monthly, quarterly, and other frequencies as required), maintenance activities, and experimental project support. Specific examples of these activities included, but are not limited to, the following:

1. Collection and analysis of air samples taken within the containment building and in the exhaust/ventilation systems.

2. Collection and analysis of water samples taken from the secondary, D2 0, primary, shield coolant, liquid waste, and experimental systems, and fuel storage pool.

3. Performance of radiation and contamination surveys, radioactive waste collection and shipping, calibration of area radiation monitors, calibration of effluent and process radiation monitors, calibration of radiation protection/survey instrumentation, and establishing/posting radiological control areas.

4. Provision of radiation protection services during fuel movements, in-core experiments, sample irradiations, beam port use, ion column removal, and fission converter beam installation and testing, etc.

The results of all surveys and surveillances conducted have been within the guidelines established for the facility.

23 H. RADIOACTIVE EFFLUENTS This section summarizes the nature and amount of liquid, gaseous, and solid radioactive wastes released or discharged from the facility.

1. Liquid Waste Liquid radioactive wastes generated at the facility are discharged only to the sanitary sewer serving the facility. The possible sources of such wastes during the year include cooling tower blowdown, the liquid waste storage tanks, and various sinks.

All of the liquid volumes are measured, by far the largest being the 10,061,189 liters discharged during FY2004 from the cooling towers. (Other large quantities of non-radioactive waste water are discharged to the sanitary sewer system by other parts of MIT, but no credit for such dilution is taken because the volume is not routinely measured.)

Total activity less tritium in the liquid effluents (cooling tower blowdown, waste storage tank discharges, and engineering lab sink discharges) amounted to 1.61 E-5 Ci for FY2004. The total tritium was 3.39 E-1 Ci. The total effluent water volume was 10,106,516 liters, giving an average tritium concentration of 0.335 E-6 liCi/ml.

The above liquid waste discharges are provided on a monthly basis in the following Table H-3.

All releases were in accordance with Technical Specification 3.8-1, including Part 20, Title 20, Code of Federal Regulations. All activities were substantially below the limits specified in 10 CFR 20.2003. Nevertheless, the monthly tritium releases are reported in Table H-3.

2. Gaseous Waste Gaseous radioactivity is discharged to the atmosphere from the containment building exhaust stack. All gaseous releases likewise were in accordance with the Technical Specifications and 10 CFR 20.1302, and all nuclides were substantially below the limits after the authorized dilution factor of 3000 with the exception of Ar-41, which is reported in the following Table H-1. The 1,005.05 Ci of Ar-41 was released at an average concentration of 3.66 E-9 ItCi/ml. This represents 36.6% of EC (Effluent Concentration (lxlo-8 1Ci/ml)).

3. Solid Waste No shipments of solid waste were made during the year. The information pertaining to these shipments is provided in Table H-2.

24 TABLE H-1 ARGON-41 STACK RELEASES FISCAL YEAR 2004 Ar-41 Average Discharged Concentration(l)

(Curies) (UCi/ml)

July 2003 84.09 2.36 E-9 August Shut down Shut down September 9.77 3.42 E-10 October 146.30 4.10 E-9 November 150.09 5.26 E-9 December 149.47 5.24 E-9 January 2004 90.28 2.53 E-9 February 95.58 3.35 E-9 March Excessive CO 2 purge no reading April 274.39 9.61 E-9 May 5.08 1.78 E-10 June Low counts 1.78 E-10 Totals (12 Months) 1,005.05 2.76 E-9 EC (Table II, Column I) I x 10-8

% EC 33.6%

(Note: Average concentrations do not vary linearly with curies discharged because of differing monthly dilution volumes.)

25 TABLE H-2

SUMMARY

OF MITR-1I RADIOACTIVE SOLID WASTE SHIPMENTS FISCAL YEAR 2004 Description Volume 0 Weight 0 Activity(l) 0 Date of shipment No Shipment FY-04 Disposition to licensee for burial Waste broker N/A

26 TABLE H-3 LIQUID EFFLUENT DISCHARGES FISCAL YEAR 2004 Total Total Volume Average Activity Tritium of Effluent Tritium Less Tritium Activity Water(l) Concentration (x10-6 Ci) (mCi) (x104 liters) (x10-6 IICi/ml)

July 2003 NDA 0.47 62.7 0.746 Aug. NDA 0.06 1.6 4.02 Sept. 5.15 129 6.5 1980.9 Oct. NDA 43.0 7.6 561.58 Nov. NDA 0.13 9.3 1.34 Dec. NDA 0.53 10.2 5.16 Jan. 2004 NDA 2.83 56.2 5.04 Feb. NDA 2.03 52.8 3.84 Mar. NDA 5.26 158.2 3.33 Apr. NDA 59.8 453.6 13.18 May 7.24 85.3 187.4 45.52 June 3.67 10.8 4.5 238.55 12 months 16.06 339.21 10,106.516 238.60 (1)Volume of effluent from cooling towers, waste tanks, and NW12-139 Engineering Lab sink. Does not include other diluent from MIT estimated at 2.7 million gallons/day.

(2) No Detectable Activity (NDA); less than 1.26x10-6 piCi/ml beta for each sample.

27 I.

SUMMARY

OF USE OF MEDICAL FACILITY FOR HUMAN THERAPY The use of the medical therapy facility for human therapy is summarized here pursuant to Technical Specification No. 7.13.5(i).

1. Investigative Studies During FY2004, the major BNCT effort for human subjects was on continuing Phase 111 trials for glioblastoma as well as melanoma using the Fission Converter Facility. Phase I studies are required by the U.S. Food and Drug Administration. The purpose of these studies is to investigate the toxicity (or lack thereof) of a proposed therapy. No benefit is expected to those participating in these studies. Three Phase I trials have been completed, and a Phase II trial and a Phase I/1 trial are underway.

Each is summarized below.

a) Original Phase I Melanoma Study with Tufts New England Medical Center (NEMC)

This study began in September 1994. The approach used for this protocol implementation was for the subject to be given an oral test dose (400 mg/kg) of the boron-containing drug (BPA). Blood and punch biopsy samples were then taken in order to determine the biodistribution of the boron in both healthy tissue and tumor over time. This was necessary because the uptake of boron in tumor varies markedly from one person to another. The irradiations themselves were done in four fractions.

For each, the subject was orally given 400 mg/kg of BPA and a limited number of blood/biopsy samples were taken to confirm the previously measured uptake curve.

The starting point in the Phase I protocol was a total dose to healthy tissue of 1000 RBE-cGy. After the third subject, this was increased to 1250 RBE-cGy. Four subjects participated during 1994 and 1995, and a summary of their responses was given in our annual reports for FY95 and FY96.

This Phase I protocol was continued under the sponsorship of the Beth Israel -

Deaconess Medical Center (BIDMC).

b) Phase I Melanoma Study with New England Deaconess Hospital (NEDI)

The protocol adopted here was the same as that used for the NEMC study except that: (i) the boronated drug (BPA) was introduced intravenously (V) and the total dose 1250 RBE-cGy was delivered in one fraction. The use of IV BPA greatly increases boron uptake and hence dose to tumor. One subject was irradiated under this protocol, as summarized in the annual report for FY96.

NEDH became part of BIDMC in FY97.

28 c) Phase I Glioblastoma Study with Beth Israel - Deaconess Medical Center (BIDMC)

This protocol is similar to the NEDH melanoma study in that it uses IV BPA.

The total dose is delivered in multiple fractions via calculated, intersecting beam paths. Eight subjects participated in FY97, six in FY98, and eight in FY99 as summarized in our annual reports for those years.

d) Phase II Melanoma Study with BIDMC One subject was irradiated under this protocol, as summarized in the annual report for FY2003. During this reporting period, no subjects were irradiated.

Subject irradiations are continuing under this Phase II protocol.

e) Phase I / Phase II Glioblastoma Study with BIDMC Five subjects were irradiated under this protocol, as summarized in the annual report for FY2003. During this reporting period, one subject was irradiated, at an average brain dose of 770 RBE-cGy. Summary of this irradiation is as follows:

Subject 2004-1 45 year old female, irradiation dates 07/08/03 and 07/09/03.

Location of irradiation: cranium.

Subject irradiations are continuing under this Phase 111 protocol.

2. Human Therapy None.

3. Status of Clinical Trials The Phase I glioblastoma and melanoma trials with BIDMC have been closed because they used the original epithermal beam in the basement medical therapy room.-

A new beam that is superior in both flux and quality is now available from the Fission Converter Facility. New Phase I / Phase II trials (melanoma and glioblastoma) began with that beam in October 2002.