ML20205Q348

Tx A&M Univ Sys Tx Engineering Experiment Station Nuclear Science Ctr 1998 Annual Rept. with

ML20205Q348
Person / Time
Site:	05000128
Issue date:	12/31/1998
From:	Reece W TEXAS A&M UNIV., COLLEGE STATION, TX
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
99-0110, 99-110, NUDOCS 9904210179
Download: ML20205Q348 (27)

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TEX A S E N GIN E E RIN G EX P E RI.\l E NT STATION TEXAS A&M UNIVERSITY COLLEGE STATION, TEXAS 77843-3575

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L NUCLEAR SCIENCE CENTER 409/845-7551 April 14,1999 99-0110 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555

Subject:

Annual Report

Reference:

NRC Facility License R-83, Docket 50-128

Dear Sir:

Attached you will find the 1998 Annual Report for the Texas A&M University System Nuclear Science Center. If you have any questions or comments, please contact me at (409) 845-7551.

Sincerely, ld h -

W. D. Reece, Director t

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Attachment:

1998 Annual Report xc: 12110/ Central File NRC License File NRC Correspondence File l/0 9904210179 981231 PDR -ADOCK O R

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Texas A&Ml University System Texas Engineering Experiment Station Nuclear Science Center 1998 AnnualReport Facility Operating License R-83 1995 Nuclear Science Road CoIIcge Station, Texas 77843-3575 l

1 March 1999

1 Texas A&M University SysternNuclear Science Center 1998 Annual Report i

. Contents 1.0 I n t rod u ct i o n . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4 1.1 Nuclear Science Center Staff....... ...... ... ... . . .. . ... . ... .... .. .............. ... ........ 5 2.0 Reactor Utilization for 1998 .......................... . .. . . ....... ...... .... .. ...... ... ...............6 2.1 Research Enhancement Program ......... ........ ..... ..... ........... .................. ... ... .... 7 2.2 Texas A&M University Academic Support Program ............ ................. . . .......... 7 2.3 Reactor Sharing Program................. .... ...............................................7 2.4 Commercial Activity and External Research... . ....... . .................. .. ............ ..... 7 3.0 Facility and Procedure Changes.. .. ............ .... ... .. . .. .. .. ..... . . .. . .... . ...... .. .. ..... . .. ... .... ..... . .... . 9 3.1 Faci li ty M od i fi cat i ons . . . . . . . . . ... . . . . . . . .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. . . . . . . .. . .. . . . . . .. . . . . 9 3.2 Experiment Authorizations and Modifications ...... .. ..... .....................................12 4.0 Reactor Maintenance and Surveillance............... . .......... ... .... ................... .......... ..... 13 4.1 S ched u led M ai n t enanc e . .. . .. . . . . . .. . .. . . . . . .. . . . .. . . . . .. . . . . . . .. .. . . . . . . . . . . . . . . . . . . . . . . .. . . . . . . . . . . . . . . . 13 4.2 Unscheduled Maintenance ...... ............ .....................................................I3 4.3 Emergency Planning and Review ... .. .. ... . . .. .... ... ...............................14 4.4 Unsched uled S h utdowns . . . . .. . . .. . . . . . . . . .. . . . ... . . . . . . . . . .. . . . . . . . . . . . . . . .. . . . . . .. . . . . . .. . . . . ... . . . . . .. 14 5.0 Health Physics Surveillances .. ... .. ......... . ...... .. . ... . ... .... ... . ........ .. .... .. ................ ........... .. I 8 5.1 Radioac ti ve S hipments. . . . . . ... . . ... .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. . . .. . . .. .. . . . . . .. I 8 5.2 Personnel M onitoring. . .. . . . . . ... .. . . . . . . . . . . . . . . . .. . . . . . . . . . . .. .. . . . . . . . .. . . . . . . . . . . . .. . . . .. .. . . . . . . . .. . .. . . . . . . I 8 5.3 Facili ty Monitoring .. . . .. ... .... . . .. . . . .. . . . . . . . ... . . . . . . . . . . . . . . .. . . . . . .. . ... . . . . . . . . . . . . .. . . .. . . . . . . . . . . . . . . . 1 8 5.4 Particulate Effluent Monitoring .......... .... .. ................................ .. ....... .............19 6.0 E nvironm ental Monitoring. . . . .. . ... .. .. . . . .. ... .. ... . . . . .. . ... . .. . . . . . . . ... . . . . . . . . . . . . . . . . . .. . . . . . . .. . .. . . . . . . . .. . . . . 2 2 6.1 Environmental Survey Samples .... .. ....... .. .... ... ........ . .... .. . ....... .. .. .................. ... .. . 22 6.2 S i te B o undary Do se Rate .. . . . . . . . ... . . . . . . .. . . . . . . .. . . . . . .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . ... . . . ... . . . . . . . . . . . 2 3 7.0 Radioactive Waste Shipments............. ... ..... . . ........ . .... .. . . . . . . . ..... .. .. . .... . .. ... . . ... ..... ... .. 24 8.0 Reacto r S a fety Bo ard . . .. .. . .. . ... . . . .. . . .. .. . . . ... . .. . . . . .. . . . . . . . . .. . . . . . . . . . . . . . . . . . . . . . .. . . . . . . . . . . . . . . . . . . . . . . . . 2 5 s

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. o e, Texas A&M University System Nuclear Science Center 1993 Annual Report f

Figures Figure 1. Nuclear Science Center Staff.... . .. . ........ . . . ..... .... ....... .... ...... . . ...... .. .. .. 5 Figure 2. Annual Reactor Utilization. . . . .. ......... . .. .. . ........................... ...... . . ........... .... .... 6 Figure 3. Nonnal Facility Air Monitor Collection System Lineup. ...... ..... . ........ .. . ..... . .15 Figure 4. Bypassed Normal Facility Air Monitor Collection System Lineup. ............. .......... ..16 Tables Table 1. 1998 Reactor Utilization Summary. ....... . . ..... ..... . ..... . . . . . . . . . . . . . . . . .....6 Table 2. Annual Particulate Effluent Releases... . .. . . . . . . . . . . . . . . . . . . ...................19 Table 3. Annual Gaseous Effluent Releases. . ....... .. . ...... .. ............. ... .... .. . . . ....... .......... 20 Table 4. Annual Liquid Effluent Releases. ............... ............ ................. ... . ... .... . ...... ....... 21 Table 5. Environmental Water Samples. ... . ..... .. .... .. .. . . ......... ....... . ........ ...... . ... . 22 Table 6. Environmental Milk Samples. .... ...........................................................22 Table 7. Environmental Soil Samples..... . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .23 Table 8. S ite Dose Rates. . . ... .. .. . . ... .. .. . . . ........ . . . .. .. .. .. .. .. . .... . ......................23

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e, Texas A&M University Sptem Nuclear Science Center 1998 Annual Report 1.0 Introduction The Nuclear Science Center Reactor (NSCR) is operated by the Texas Engineering Experiment Station as a ervice to the Texas A&M University System (TAMUS) and the state of Texas. The Nuclear Science ~ Center (NSC) is a multi-disciplinary research and education center supporting basic and applied research in all nuclear related fields of science and engineering as well as providing educational opportunities for students in those fields. The NSC also provides services to commercial ventures requiring radiation or isotope production services.

This annual report has been prepared by the NSC staff to satisfy the reporting requirements of Technical Specification 6.6.1 cf the facility operating license R-83 and of the Department of Energy University Reactor Fuel Assistance Program subcontract No. C87-101594 (DE-AC07-76ER02426). The facility license currently extends to March 2003.

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. Tenas A&M University System Nuclear Science Center 1993 AnnualReport 1.1 Nuclear Science Center Staff The staff at the Nuclear Science Center is divided into four primary work groups:

Operations, Health Physics, Maintenance, and Administration. Personnel directly involved with the operation and maintenance of the reactor are NRC-licensed operators. The NSC is committed to its educational responsibilities and many members of the staff are part or full-time students at Texas A&M University.

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, Texas A&M University System Nuclear Science Center 1998 Annual Report 2.0 Reactor Utilization for 1998

. l The Nuclear Science Center reactor has been in operation since 1962. The reactor is a 1 Megawatt MTR converted to TRIGA fuel. The TRIGA fuel is highly enriched uranium (ifEU) enriched to 70%,'but will be converted to 20% enriched fuel when DOE funds become available.

Core VIII-A is the current core configuration and has been in use since March 1986. The NSC reactor is pulse operational and is pulsed up to powers of approximately 1100 MW for nuclear engineering laboratories, staff training, and public tours.

The NSC reactor operated for 2,186 hours0.00215 days <br />0.0517 hours <br />3.075397e-4 weeks <br />7.0773e-5 months <br /> in 1998 with a total imegrated power of 89.3 MW-days. There were 657 irradiations and services performed at the NSC during the reporting period. The NSC provided services to TAMUS departments, other universities, research centers and secondary schools in and outside the state of Texas. Ten departments at TAMU and ten other universities used the reactor regularly in 1998. The NSC reactor had a 90% availability in 1998.

Table 1.1998 Reactor Utilization Summary.

Days of Reactor Opertion 240 Integrated Power (MW-days) 89.3 Number of Hours at Steady-State 2185.67 Number of Pulses 56 Number of Reactor Irradiations 657 Beam Port / Thermal Column Experiment Ilours 1096 Hours Irradiation Cell Use 456 Number of Visitors 2982 l

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Texas A&M University System Nuclear Science Center 1998 Annual Report 2.1 Research Enhancement Program The 70* Texas Legislature established the Research Enhancement Program (REP) in 1987 to

" encourage and provide for research conducted by faculty members." The REP replaced the former " Organized Research" program.

The TAMU Office of the Vice President for Research administers the REP funds. REP funds are generally allocated to the NSC carly in the fiscal year. TAMUS faculty that desire to use the many irradiation services at the NSC reactor must apply at the NSC to receive local funding for each individual project. This proposal method is flexible and does not hinder a project's start-up time.

2.2 Texas A&M University Academic Support Program Texas A&M University provides funding for the reactor for such academic activities as nuclear engineering laboratories, neutron activation analysis demonstrations and laboratories, graduate student thesis and dissertation research, and undergraduate research projects. The program has been very successful and is crucial for many graduate students whose chosen research uses the NSC reactor in some way but is not supported by any research grants.

The NSC's reputation as a multi-disciplinary institution is reflected in the wide range of academic users from the university.

2.3 Reactor Sharing Program The University Reactor Sharing Program provides funds for reactor experimentation to those institutions that do not normally have access to a research reactor. The Nuclear Science Center (NSC) has panicipated in the program since 1980 with great success. During the 1997-1998 contract year, eleven research institutions utilized the NSC with the support of the Reactor Sharing Program. Additionally, the funding pmvided reactor tours and " hands-on" projects to many secondary schools.

The research projects supported by the program range from geological dating to the production of high current superconducting magnets. The funding gave several small colleges and universities the opportunity to use the NSC for teaching courses in nuclear processes, specifically neutron activation analysis and gamma spectroscopy. The Reactor Sharing Program supported the use of the Fast Flux Irradiation Device for multiple users at New Mexico Institute of Mining and Technology and the University of Nevada at Las Vegas. This device has been characterized and has been found to have near optimum neutron fluxes for "Ar/*Ar dating.

2.4 Commercial Activity and External Research The NSC provides services to a variety of users who have their own funding. The majority of commercial activities are related to isotope production of radioactive tracers for support of the Texas petroleum and chemical industries. Another commercial activity uses the converted Thermal Column area for the production of micropore filters that are used in ultra-pure water 7

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.; Texas A&M University System Nuclear Science Center 1998 AnnualReport systems in the semiconductor industry. A significant amount of research at the reactor is funded by outside.research grants.

The NSC has many years of experience in the production of radioisotopes and has developed j several custome6 specific methods for radioactive sample handling. The production of  !

radioisotopes generally involves handling high-activity radioactive materials during unloading, j therefore, the staff take many precautions to minimize their exposures during the transfer of j materials to shipping shields.

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g Texas A&M University System Nuclear Science Center 1993 AnnualReport 3.0 Facility and Procedure Changes 3.1 Facility Modifications The following it6ms were authorized facility modifications and maintenance in accordance with 10 CFR 50.59. The approvals were documented in NSC staff meeting minutes or RSB meeting minutes as appropriate.

1. Replacement of the hosing system os the reactor bridge with quick disconnect connections (February 3,1998)

The purpose of this modification was to allow for the complete disconnection and removal of the diffuser pump hose, the transient rod air hose, and the facility air monitoring hose (channel 2:

fission products) connected to the reactor bridge. Previously, all three hoses were disconnected at the floor and looped onto the reactor bridge prior to reactor movement. This has always presented a possible avenue for injury to the hoses when moving the reactor past the MHA wall (located on the north side of the reactor pool). It was discovered that the diffuser pump hose had a considerable kink in it. The hose is constructed of reinforced rubber and did not fail, although the flow through the hose was apparently reduced. The idea of replacing the current system with a system of quick disconnects was developed.

All three connections on the floor and on the reactor bridge were replaced with quick disconnects. Anytime the reactor is to be moved to a point where the hoses must be disconnected, these hoses will be disconnected at both ends (reactor bridge and the floor) and placed onto the reactor bridge itself. This will eliminate the possibility of damaging the hoses.

2. Removal of Beam Port 1 fence, gate, and alarm and placement next to film storage area (February 5, E998)

The company that utilizes the NSCR's thermal column to irradiate polycarbonate film constructed a containment room around the thermal column area in order to replace the irradiator.

After the completion of the work, the containmen: room needed to be decontaminated and removed. The old irradiator was removed from the containment room, however, it had fixed contamination. The company stored their irradiator in their film storage area. In order to maintain control over the area, it was suggested that the Beam Port 1 intrusion alarm and lock could be moved to the film storage area. Beam Port 1 gate and alarm was previously removed in j order to accommodate the containment room. i The idea was discussed and several concems were noted if the alami and lock was moved to the j film storage area, all operators must be aware that an alarm in the control room means that the j film storage area access has been opened. It was decided that the Reactor Operations and the Health Physics staff would be fully informed of the change. l Another concem was the issuance of the Beam Port 1 gate key. It was felt that the key to Beam Port I should be issued only to a member of the Health Physics staff. This would avoid any j inadvertent personnel having access to the storage area.

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< Texas A&M University System Nuclear Science Center 1993 Annual Report I l

l The. placement of the Beam Port I shield plug will remain in place and will not be moved I

without permission from the SRO and the Duty IIP. The crane that positions the shield plug over i

Beam Port I was tagged out so that the shield plug cannot be inadvertently moved.

l 3. Modification of scram circuit system (February 19,1998)

On Wednesday, February 18,1998, the NSC received an e-mail from the Oregon State Reactor stating that they had a reportable occurrence during a routine core excess measurement. They had discovered that one of their reset switches had partially stuck in the closed position and when the reactor was to be manually scrammed, the reactor safety system did not initiate a scram.

They determined that the cause of the switch sticking was due to dirt inside the switch, but more importantly they discovered that the reactor did not scram because the logic and the wiring inside the console was not correct. This single failure disabled all the entire scram system for the l

reactor.

Following reactor shutdown of the NSC reactor later that same day, the SR0 and the RO tested the scram system. The Manual Scram, the Experimenter Scram, and the Fuel Temperature l Scram reset switches were held in place while the appropriate scram was actuated. In all three cases the rcactor failed to scram. These results were recorded and NSC management was informed.

Staff members examined the facility drawings of the scram circuit system. There were two drawings; the first drawing, drawn in 1971, was an extensive wiring diagram. The second drawing, drawn in 1976, was a logic diagram. According to the logic diagram, the reactor scram system was fundamentally sound. The wiring diagram was too complicated to examine, so it was decided that the reactor console would be taken apart and traced out to determine and verify the actual wiring scheme.

l l The NSC redesigned the scram system to rectify the problem. The RSB was asked to approve i the modification. The scram system was thoroughly tested to verify that the reactor protective

! system functions correctly.

4. Operation of the reactor at power levels greater than 100 kW at distances greater than one foot from the irradiation cell window (February 25,1998) l l Due to detector failure or misplacement in the irradiation cell window, a gamma irradiation experiment was not irradiated as planned on Monday, February 23,1998, and Tuesday, February 24,1998. In order to complete the experimental requirement of approximately 50 kGy dose to his samples, use of the reactor near the irradiation cell window as a gamma source was considered.

Experiment Authorization 4," Operation of the NSCR adjacent to the irradiation cell window,"

states "the NSCR will be operated at power levels up to 100 kW with the reactor core three inches from the surface of the radiation window at the west end of the main pool." For this experiment, no filter or void can should be used since the purpose was to sterilize, not activate, 10 b - . . . . ..

Texas A&M University System Nuclear Science Center 1998 Annual Report the samples. Therefore, the water gap of at least one foot should minimize the neutron dose l whjle maximizing the gamma dose to the samples in the cell window. A BF detector 3 was placed t

in the irradiation cell window to monitor the neutron flux in the window. The reactor was initially placed four feet away from the cell window and operated at 100 kW to determine the ,

dose rate and the neutron flux into the cell. No significant flux of neutrons was seen, therefore, the reactor was increased in power by 100 kW increments until a desired dose rate was reached  ;

in order to adequately sterilize the samples in a reasonable amount of time. The dose rates on the l

observation deck and in the control room were monitored to assure that a radiation area was not l ovserved in either location.

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5. Modification of Beam Port I for a neutron dose experiment (March 30,1998) l l

1 l An experimenter wiued to perform a Beam Port 1 experiment to acquire a neutron dose of l approximately 1,000 Gy to an ABS plastic sample. Since Beam Port I had not been operable 1 l since 1995, a list ofitems that needed to be perfomied before the beam port was operable was as follows:

restoration ofpower to the LRL crane ]

construction of beam stop with high density concrete blocks j reinstall vent line for water shutter )

install gamma shutter system  !

l reinstall water shutter control system l

install six inch coupler (BPI to graphite coupler box) j check interlock wiring (BPI gate and interlock is currently connected to the film storage area; it is a concern that the interlock system in the water shutter mechanism may l cause failure of the water shutter)

Additional requirements for operation of the beam port included initial surveys by Health Physics and for the area to be monitored at all times due to the lack of an interlock system on the beam port gates. The LRL would be evacuated and access will be restricted. The film storage area gate will need to remain closed during beam port operation due to the current interlock l

setup.

6. Modification of Chemistry Laboratory to provide air conditioning (June 18,1998)

The working conditions, primarily the temperature, of the chemistry laboratory were getting l worse during iodine seed testing as the temperature outside increased. Due to the laboratory l work requirements, i.e., lab coats, gloves, shoe covers, and the nature of the work, it was becoming very uncomfortable and difficult to work in that laboratory. It was proposed that an air conditioning unit be installed to supply cool air to the room.

The chemistry laboratory has a wall with three glass windows. One of these glass windows was removed to allow for the installation of an air conditioning window unit. It was suggested that the unit should be placed in the window nearest to the demineralizer room and furthest away

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from the door to the chemistry laboratory. The balance of the wall was replaced with plywood.

A section of the plywood accommodated the laser water cooler. As far as the air conditioning 11

Texas A&M University System Nuclear Science Center 1998 Annual Report unit is concemed, an older spare unit was used. The recirculation dampers were physically held in the recirculation position. A filter was placed at the exit of the air conditioning unit to filter out any airbome radiolodine. The water generated will be transferred back to the hot sink. The air conditioner will have an emergency cut off switch.

7. Linear Power Measuring Channel Flux Control Circuitry (September 1,1998)

The Servo control system, which is associated with the linear power measuring channel, receives reactor power signals and controls the regulating rod (a non-scrammable control rod) to maintain reactor power at a desired level. The Servo controller operates in two modes: automatic and ,

manual. During automatic operation, if a received signal is strong enough, the Servo controller l will switch to the manual mode. Due to noise spikes in the reactor console, the Servo control frequently switches from automatic to the manual mode. When this occurs, the reactor operator must answer a visual and audible alarm. The frequency of this evem prevents the intended operation of the Servo control system and is an impediment to the completion of other reactor operator duties.

The modification does not affect any safety control system; change takes place in the Servo response circuitry. Three 10 kohm resistors were replaced with three 1 Megohm resistors and a 1 f capacitor was installed into the flux control circuitry. The results of this change filter out ,

noise spikes that would switch the Servo from the auto mode into the manual mode. All l drawings in the technical manuals were updated and a copy of the revised schematics was  !

enclosed in the modification package. A post modification program was written and ,

incorporated into the modification package.

3.2 Experiment Authorizations and Modifications

1. Iodine Seed Processing / Laser Welding (Chemistry Laboratory)(March 30,1998)

This authorization covers the modifications to the Chemistry Laboratory for its use as an iodine separation and processing laboratory and as a laser welding laboratory. In order to prepare the lab for radioactive material processing, all furniture and cabinets were removed except for the hot cell in the northwest corner. The walls, ceiling, and floor were primed with a heavy duty concrete block filler and then painted with two coats of non-porous epoxy paint. The original furniture and cabinets were replaced with easily decontaminated furniture, including two stainless steel tables and two epoxy countertop steel tables. A new stainless steel foot-operated sink was installed along with a new safety shower and eyewash system, with the waste water for both connected to the liquid radioactive waste disposal system.

2. Iodine-125 Production (October 29,1998)

The NSC was given permission to begin production of 251 for research and cancer therapy. Since i25 1is a decay product ofi25Xe, a new experimental irradiation device was designed and built to hold and irradiate enriched (>99%) Xe gas. The activated gas is immediately cryogenically transferred to a decay chamber following irradiation to collect the 25 I as thei25Xe decays.

Preliminary results are promising; commercial production is planned for 1999.

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Texas A&M University System Nuclear Science Center 1998 Annual Report 4.0. Reactor Maintenance and Surveillance 4.1 Scheduled Maintenance Calibrations wer6 performed on the Fuel Element Temperature Channel, Area Radiation Monitors and the Linear, Log, and Safety Power Channels as required by the Technical Specifications. All surveillances required by the reactor license were performed.

Control rod worth and scram time measurements were performed in September 1998. The total rod worth was found to be $16.94. The most reactive control rod is Shim Safety #4 with a worth of $4.59. The shutdown margin was determined to be $4.38 and core excess was measured as

$6.05. Scram times on all rods were less than 1.2 seconds.

A calorimetric calibration was performed following each maintenance period. Fuel inspections were performed as required by the Technical Specification with no abnormalities noted.

The cold critical reactivity worth for each reactor experiment was measured prior to full experiment approval. The most reactive fixed experiment has been found to be the Fast Flux Pneumatic Receiver (-$1.35) with the negative worth caused by high boron loading.

4.2 Unscheduled Maintenance 2/19/98 The scram reset circuit was modified in accordance with drawing RE-123, "NSC Reactor Scram Logic," to prevent a stuck reset button from preventing a scram.

3/6/98 The air flow in the Chemistry Laboratory (Lab 1) was reversed to make the air inlet the exhaust and the door vent the inlet. H.E.P.A. and charcoal filters were added to the exhaust and a H.E.P.A. filter was added to the door vent. This made the Chemistry Laboratory a low pressure area with respect to the rest of the buttding and provided a suitable location for iodine seed testing.

4/1/98 Installation of a new water supply, sink, emergency shower and eyewash, and laser cooling system in the Chemistry Laboratory.

4/3/98 Fume hood exhaust line in the Chemistry Laboratory was modified to pull only on the laser welder's workstation so that iodine seed testing could be performed.

4/10/98 Secondary pump circuitry fuse replaced afler repair of burned-out indicator light.

4/13/98 Fuel Vault fan motor was replaced due to failure.

4/13/98 Beam Port 4 shield block was repaired so that an alarm would be activated in the Control Room when opened and the water shutter will flood.

4/30/98 Front gate motor bushing was rebuilt and realigned due to failure to move gate.

5/15/98 Repair of Pneumatic Permit Intercoms due to poor sound transmission between the laboratories and the control room. ,

5/22/98 Contactor and contacts for skimmer pump were cleaned due to inability to shut off l

~ pump.

6/1/98 Vacuum pump for FAM systems repaired due to failure.

7/15/98 Control Rod Drive controller unit 3 wiring was replaced due to oxidation.

Problem was noticed due to flashing " engaged" light.

7/29/98 Control Rod Drive 3 wiring was repaired due to a blown fuse from shorted wire.

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Texas A&M University System Nuclear Science Center 1998 Annual Report l 8/12/98 Heat Exchanger Room sump pump was replaced due to previous failure.

8/1,2/98 , CMOS integrated circuits for control rods 1-4 were replaced due to failure during l

testing.

8/13/98 Cooling tower water line fitting repaired due to crack.

8/17/98 Transient rod interlock mechanism (preventing another rod to be withdrawn at the same time) was replaced.

l 9/1/98 Servo controller altered to accommodate higher ohm resistors and capacitors to correct its overcorrection and subsequent tripping problem.

9/11/98 Quick disconnects installed on reactor bridge for attaching diffuser line, pressurized air line (to transient rod), and FAM Channel 2 suction line.

9/25/98 Bridge interlock cable and connector repaired due to overextension during bridge movement.

10/1/98 Alarm relay for control room / reception room annunciator / alarm for FAM Channel 4 was replaced due to failure.

10/13/98 Repair of Lower Research Level access door lock.

I1/2/98 Heat exchanger room sump pump replaced.

I1/3/98 Motion detector light and TV camera installed adjacent to front gate.

I1/16/98 TV monitor installed in reception room to view smveillance cameras.

l 11/30/98 Encoder in Control Rod Drive Unit 3 replaced due to counting failure.

12/10/98 Encoder in Control Rod Drive Unit I replaced due to counting failure.

12/15/98 Transient Rod interlock repaired.

12/15/98 Rod down light on Control Rod Drive 4 replaced.

12/15/98 C-2 alarm / gate for Irradiation Cell repaired.

4.3 Emergency Planning and Review The Facility Security Plan and Emergency Plan were review by the NSC staff on October 26, 1998, and by the RSB on October 29,1998. All required external audits were completed during the reporting period.

4.4 Unscheduled Shutdowns There were eight unscheduled reactor shutdowns occurred during 1998. Three shutdowns resulted from a loss of facility electrical power. The remaining causes are detailed below:

3/24/98 Noise signal in console during pulsing caused a safety amplifier scram.

7/20/98 Momentary loss of magnet power due to faulty (dirty) magnet.

7/21/98 Momentary loss of magnet power due to faulty magnet.

l 7/22/98 Excessive noise from a bend in a detector cable caused a period scram.

l 9/3/98 Noisy signal from log drawer's switching between its cambelling circuit and diode pump resulted ja a period scram.

4.5 Reportable Occurrences l

There was one reportable occurrence in 1998. On August 26,1998, the Facility Air Monitor for I building particulates (FAM Channel 4) failed the daily FAM alarm checks prior to reactor )

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., Texas A&M University System Nuclear Science Center 1998 AnnualReport operation. This system is required to be in operation as a Limiting Condition of Operation (NSCR Technical Specification 3.5.1). The system was removed from service for troubleshooting and a failed alarm relay was discovered in the NIM module. Spare parts were no lenger available from the manufacturer and an equivalent relay was ordered from another source.

l NSC Management considered FAM Channel 4 to be inoperable and the Reactor Manager was l directed to monitor the building using an equivalent but not required channel (FAM Channel 2).

l The NSC Air Monitor sample transport piping is configured to allow individual detectors to sample from alternate points (Figure 1). Detectors 1,2, and 4 are particulate monitors; detectors 3 and 6 are gaseous detectors.

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The Duty IIcalth Physicist (DHP) intended to line up the system such that FAM Channel 2 would monitor the reacter building particulates. Although the DIIP had performed several

Argon-41 calibrations involving the FAM piping, the valve lineup was positioned incorrectly l (Figure 2).

15 f

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., Texas A&M University System Nuclear Science Center 1998 Annual Report

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A cap for a quick connection was missing and the DHP moved a cap from Detector 6 to that j location. The combination ofincorrect valve arrangement and the missing cap caused a leakage path that bypassed or significantly reduced flow through all particulate detectors. The air leakage flowed through the building and effluent gas detectors and out through the flow meters. The indications to the DHP appeared normal because the air flow meters (rotometers) indicated normal 350 cfh flow. The reactor was operated in this condition for another eight hours. The next day, the DHP questioned the abnonnally low readings on all FAM meters (<5 cps). The Senior Reactor Operator investigated with the DHP and found the incorrect valve line-up. The NSC Director, Reactor Safety Board Chairman and the NRC (Marvin Mendonca) were all informed of the Reportable Occurrence.

Root Cause Analysis

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Several weaknesses were found during a root cause meeting of the NSC staff on August 27, 1998:

There was no written valve lineup procedure for abnormal conditions of the Facility Air Monitoring System.

A certified Duty Health Physicist (DHP) performed valve manipulations without a system check by the on-duty Senior Reactor Operator or Reactor Operator. Although not formally required, usually the SRO confirms valve alignments.

16

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.l Texas A&M University System Nuclear Science Center 1998 AnnualReport Readings were logged in the control room during the eight hour occurrence. These readings clearly indicated a decrease in radioactive counts. The evening shift operators, unfodunately, did not recognize the trend to be a system failure.

Corrective Actions

1. The Reactor Operations and Health Physics Staff are preparing formal written procedures for normal, abnormal and testing configurations of the FAM system. These procedures should be reviewed and approved by the Reactor Safety Board.

2. The NSCR Tag-out and Lock-out procedures were rewritten to require a second check of any tag by a licensed Reactor Operator.

3. The NSCR staff aill be trained on the new procedures, the necessity for system tag-outs for facility and p:.sonnel protection and normal expected indications on all facility equipment.

l 1

I 17

., Texas A&M University System Nuclear Science Center 1998 Annual Report 5.0 IIcalth Physics Surveillance; A dedicated IIcalth Physics group is maintained at the NSC as an integral part of the organization. The licalth Physics group is responsible for chemical and physical safety as well as radiological cbncerns. The TAMU Environmental IIcalth and Safety Department provides additional support to the NSC llealth Physics group upon request. -

5.1 Radioactive Shipments The IIealth Physics monitoring and technical support provided in 1998 assured minimal exposure during sample handling, shipment of radioactive material, and normal reactor operation. IIcalth Physics also maintained state and federal regulatory compliance for the reactor -

and the linear accelerator located on the NSC site. During 1998, there were 377 radioactive sample shipments, of which 196 were sent to various research facilities and 44 to departments on j the campus of Texas A&M University. A total "272 Curies was handled in 1998, almost 80 Curies lower than in 1997.

5.2 Personnel Monitoring Personnel Monitoring was provided to 36 NSC employees. All personnel radiation exposure was below the limit set forth in 10CFR20. One individual did receive greater than 10% of the annual maximum exposure; his exposure was recorded as 1070 mrem of deep dose equivalent for the year. Airborne monitoring during sample handling continued to show no significant airborne activity. Therefore, total effective dose equivalent equals deep dose equivalent for 1998. A total '

of 5.23 man-rem was recorded for all of 1998. When total man-rem / Curie was determined for 1998, the dose per Curie increased from 1997. In 1997, man-rem / Curie equaled 0.0153; in 1998, man-rem / Curie increased to 0.0192.

During 1998,2,982 visitors (130 more than year 1997) toured the Nuclear Science Center.

Minimal exposures were measured with pocket ion chambers worn by these visitors and compared with the pocket ion chamber readings of their respective tour guides.

NSC employees who were exposed to radiation in amounts that are likely to exceed 10% of their total annual dose wore TLDs/ film badges and extremity dosimetry provided by Landauer, a NVLAP accredited supplier. Landauer also provided the analysis reports of the exposure received.

5.3 Facility Monitoring '

Surveys of the Nuclear Science Center facilities were performed to assess radiological hazards to .

NSC workers. Radiation levels and sources of radioactive contamination were frequent!y monitored. Approximately 350 smear samples were collected and evaluated for radiation and contamination levels each month from all accessible areas of the NSC. In areas where contamination was expected, access / egress controls were in place and were evaluated on shorter inten als.

18

1 Texas A&M University System Nuclear Science Center 1998 Annual Report 5.4 Particulate Effluent Monitoring Ra'dioactive particulates were monitored at the base of the central exhaust stack and summarized on a monthly basis. The annual average release concentration was 4.38 x 10'" Ci/cc. Total j 3

activity released-for 1998 was 5.25 x 10 Ci. The following table summarizes annual particulate 1 effluent releases during 1998.

1 Table 2. Annual Particulate Effluent Releases.  !

QuarterMonth Average Diluted Exhaust Total Concentration Concentration Volume Released (pCi/cc) ( Ci/cc) (cc) (Cl)

I January 1.22E-Il 6.12E-14 1.01E+13 1.24E-04 February 1.94E-12 9.70E-15 9.14E+12 1.77E-05 March 6.57E-Il 3.28E-13 1.01E+13 6.64 E-04 Average: 2.66E-Il 1.33E-13 9.79E+ 12 2.69E-04 Total: 2.90E+ 13 8.06E-04 II April 8.63E 11 4.32E-13 9.79E+12 8,45 E-04 May 7.23E-Il 3.62E-13 1.01E+13 7.31E-04 June 3.89E-I l 1.94 E-13 9.79E+12 3.81 E-04 Average: 6.58E-11 3.29E-13 9.90E+12 6.52E-04 Total: 2.98E+13 1.96E-03 l

III July 4.08E-Il 2.04E-13 1.01E+13 4.13 E-04 August 8.71E-Il 4.35E-13 1.01E+13 8.81 E-04 September 4.95E-Il 2.47E-13 9.79E+12 4.84E-I l Average: 5.91E-Il 2.96E-13 1.00E+13 5.93E-04 Total: 2.99E+ 13 1.78E-03 IV October 2.20E-11 1.10E-13 1.01E+13 2.22E-04 November 2.04E 11 1.02E-13 9.79E+12 2.00E-04 December 2.80E-11 1.40E-13 1.01E+13 2.83 E-04 Average: 2.35E-11 1.17E-13 1.00E+13 2.35E-04 Total: 2.99E+13 7.05 E-04 Annual Average: 4.376E-11 2.19E-13 9.93E+12 4.37E-04 Total released: 1.19E+14 5.25E-03 19

lc Texas A&M University System Nuclear Science Center 1998 AnnualReport

! 5.5 Gaseous Efnuents Monitoring Argon-41 is the major gaseous effluent produced and released at the Nuclear Science Center.

This effluent is monitored at the central exhaust stack. Total Argon-41 released during 1998 was 17.41 Ci with arrannual release concentration of 1.458 x 104 pCi/cc. The annual gaseous effluent data is summarized below:

Table 3. Annual Gaseous Effluent Releases.

QuarterMonth Average Diluted Exhaust Total Concentration Concentration Volume Release (pCi/cc) (pCi/cc) (cc) (Cl) 1 January 2.09E-07 1.05E-09 1.01E+13 2.12E+00 February 1.60E-07 8.01E-10 9.14E+12 1.46E+00 March IJilE-07 8.55E-10 1.01E+13 1.74 E+ 00 Average: 1.80E-07 9.01E-10 9.79E+12 1.77E+00 Total: 2.90E+13 5.31E+00 II April 1.39E-07 6.94E-10 9.79E+12 1.36E+00 May 1.12E-07 5.13E-Il 1.01E+13 1.13E+00 June 1.23E-07 6.15E-10 9.79E+12 1.20E+00 i

Average: 1.25E-07 6.23E-10 9.90E+12 1.23E+00 Total: 2.98E+13 3.70E+00 III July 4.01E-07 2.01E-09 1.01E+13 4.06E+00 August 1.35E-07 6.75E-10 1.01E+13 1.36E+00 September 7.36E-08 3.68E-10 9.79E+12 7.20E-01

- Average: 2.03E-07 1.02E-09 1.00E+13 2.05E+00 Total: 2.99E+13 6.14 E+00 IV October 1.42E-08 7.10E-11 1.01E+13 1.43E-01 November 8.33E-08 4.17E-10 9.79E+12 8.15E-01 i December 1.28E-07 6.40E-10 1.01E+13 1.30E+00 Average: 7.52E-08 3.76E-10 1.00E+13 7.51E-01 Total: 2.99E+13 2.25E+00 Annual Average: 1.458E-07 7.29E-10 9.93E+12 1.45E+00 Total released: 1.19E+14 1.74E+41 5.6 - Liqui,d Effluents Monitoring Radioactive Liquid effluents are maintained in collection tanks prior to release from the confines of the Nuclear Science Center. Sample activity concentrations and isotope identifications were determined prior to each release. There were 51 releases in 1998 (36 releases in 1997), totaling 4.59E+05 gallons, excluding dilution from the Nuclear Science Center. Including dilution 20-

F

. i.

Texas A&M University System Nuclear Science Center 1993 Annual Report amounts, the total volume released was 6.426E+05 gallons. The total radioactivity released was I j

3.4,7 x loi Ci with an average concentration of 2.27 x 10-5 Ci/cc. Summaries of the release data are presented in the table below. Radioactivity conceritrations for each isotope found were below the limits specified in 10CFR20 Appendix B.

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Table 4. Annual Liquid Effluent Releases.  !

Radioactivity Average Number of Volume Total Concentration QuarterMontti Releases Released (cc) (Cl) (pCl/cc)

I January 2 2.03E+07 4.26E-05 2.09E-06 February 4 8.18E+07 2.42E-04 2.96E-06 March 1 1.59E+06 4.00E-06 2.51E-06 Total: 7 1.04E+08 2.89E-04 2.79E-06 II April 4 7.85E+07 1.83E-04 2.33E-06 May 3 8.45E+07 6.05E-04 7.17E-07 June 6 2.53 E+ 08 2.95E-04 1.17E-06 Total: 13 4.16E+08 5.39E-04 4.22E-06 III July 7 2.65E+08 9.11E-05 3.44E-06 August 3 1.23E408 4.35E-04 3.53E-07 September 5 2.01 E+08 2.53E-05 1.26E-06 Total: 15 5.89E+08 2.37E-04 5.05E-06 IV October 4 1.49E+08 1.04 E-04 7.00E-07 November 7 2.85E+08 1.02E+01 3.58E-06 December 5 1.95E+08 3.10E-04 1.59E-06 Total: 16 6.29E+08 1.44E-04 5.87E-06 Annual Total: 51 1.74E+09 3.47E-03 2.27E-05 4.

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21

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, Texas A&M University System Nuclear Science Center 1998 Annual Report 6.0 Environinental Monitoring In conjunction with representatives from the Texas State Department oflicalth and the Bureau of Radiation Control, a quarterly environmental survey program is conducted to insure compliance with federal regtilations, This program consists of TLD monitors located at various locations on the NSC site and a background monitor located at the Brazos River,5.25 miles west of the site.

The collection, analysis, and evaluation of soil, water, and milk samples are included in the program.

6.1 Environmental Survey Samples The environmental survey samples were collected in accordance with the schedules of the cooperative surveillance program between the Texas State Department of Health and Texas A&M University. These samples were analyzed using an inttinsic germanium detection system for isotopic identification at the NSC. A second set of samples is also analyzed by a Texas Department ofIIcalth lab for comparison to NSC results. Data collected from this analysis reflect the continued positive use of retention facilities and sample analysis for laboratory effluents prior to their release.

Summaries of the environmental survey program for 1998 are presented in the three tables below. Isotopic activity listed was that determined by the NSC. The data is comparable with the analysis performed by the Texas Department of Health.

Table 5. Environmental Water Samples.

Quarter Sample Location Concentration (pCi/ml) 1 Brazos River No isotopes were found II Brazos River No isotopes were found 111 Brazos River No isotopes were found IV Brazos River No isotopes were found Quarter Sample Location Concentration (pCi/ml)

I NSC Creek No isotopes were found 11 NSC Creek No isotopes were found III NSC Creek No isotopes were found IV NSC Creek No isotopes were found Table 6. Environmental Milk Samples.

Quarter Sample Location Concentration (pCi/ml)

I TAMU Dairy No isotopes were found

, 11 TAMU Dairy No isotopes were found 111 TAMU Dairy No isotopes were found IV TAMU Dairy No isotopes were found 22

r . .

y Texas A&M University System Nuclear Science Center 1998 AnnualReport Table 7. Environmental Soil Samples.

Quarter Sample Location Concentration ( Ci/g)

I NSC Soil 6.32 x 10-'

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11 NSC Soil 4.45 x 104 Ill NSC Soil 7.70 x 10-'

IV NSC Soil 8.49 x 10~'

6.2 Site Boundary Dose Rate The environmental survey program measures the integrated radiation exposures at the exclusion area boundaries. These measurements are made for periods of approximately 91 days using TLDs. The dosimeters are provided and processed by Texas Department of Health (TDH),

Bureau of Radiation Control, Division of Environmental Programs. The state background monitor (site #14) is located at a point 5.25 miles west-southwest of the facility and generally at right angles to the prevailing southeasterly winds. Site #14's monitor has recently been moved i approximately 25 yards from the previous location due to the loss of background monitors for the l

last two quarters. Total doses are multiplied by our newly determined occupancy factor (1/16) to

{

determine total deep dose to the general public. j l I

To determine internal exposure to individuals outside the site area, the EPA's approved code COMPLYwas used. The exposure calculated via COMPLYwas 0.3 mrem /yr. This exposure, plus 0.134 mrem /yr calculated from liquid effluent releases, is added to the calculated total deep dose. This total is the dose received by the general public. I 4

Table 8. Site Dose Rates.

Site Location Quarterly Exposure TLD Deep Internal Total

1. Rate Dose Dose Dose Dme (mrem /91 days) (mrem) (mrem) (mn )

2 300 ft. W of reactor building, near 9.0 9.0 10.5 11.9 40.4 - 2.5 0.434 3.0 fence corner 3 250 ft W-SW of reactor building, on 6.0 4.0 8.6 8.9 27.5 1.7 0.434 2.2 SW chain link fence 4 200 ft NW of reactor building, on 18.0 13.0 16.3 2.0 49.3 3.1 0.434 3.5 chain link fence, near butane tank.

5 225 ft NE of reactor building, on 6.0 4.0 7.7 8.9 26.6 1.7 0.434 2.1 l fence N of driveway j 10 190 ft SE of reactor building, near 5.0 3.0 6.7 7.9 22.6 1.4 0.434 1.8 fence corner i 11 300 ft NE of reactor building, near 5.0 2.0 5.7 6.9 19.6 1.2 0.434 1.7 fence corner 18 375 ft NE of reactor building 11.0 7.0 8.6 9.9 36.5 2.3 0.434 2.7 19 320 ft NE of reactor building 11.0 0.0 7.7 10.9 29.6 1.9 0.434 2.3 14 5.25 miles W-SW of reactor 0.0 0.0 0.0 0.0 0.0 0 0.434 0.4 building, at FM 60 bridge over Brazos River 23

=, ,

y Texas A&M University System Nuclear Science Center 1998 AnnualReport 7.0 Radioactive Waste Shipments During 1998, there were no solid waste releases from the NSC for disposal ofTsite.

l i

4 24

p Texas A&M Umversity System Nuclear Science Center 1998 Annual Report 8.0 Reactor Safety Board The Reactor Safety Board is responsible to the licensee for providing an independent review and audit of the safety aspects of the NSCR. The RSB meets at least once a year to review audit reports, security and emergency plans, new experiments and modifications to the facility.

Membership (1998)

Chairman / Licensee:

Dr. B. Don Russell, Deputy Director, Texas Engineering Experiment Station Members:

Dr. Marvin Adams, Professor, Nuclear Engineering Department Dr. William Dennis James, Research Chemist, Chemistry Department I Dr. Robert Kenefick, Professor, Physics Department Dr. Roger Koppa, Associate Professor, Industrial Engineering Department -

Dr. Earl Morris, Professor, Veterinary Medicine-Large Animal Clinic Dr. Ted Parish, Professor, Nuclear Engineering Department Ex-Officio Members:

Mr. Robert Berry, Coordinator, AGN201 Manager Dr. Latha Vasudevan, Radiological Safety Officer, Nuclear Science Center Mr. Chris Meyer, Director, Environmental Health and Safety Dr. Alan Waltar, Professor and Head, Nuclear Engineering Department I Dr. Warren Reece, Director, Nuclear Science Center 25

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