ML13169A248

University of California Davis, Mcclellan Nuclear Research Center, Submittal of 2012 Annual Operating Report

ML13169A248
Person / Time
Site:	University of California-Davis
Issue date:	06/07/2013
From:	Klein B McClellan Nuclear Research Center
To:	Document Control Desk, Office of Nuclear Reactor Regulation
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Download: ML13169A248 (25)

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5335 PRICE AVENUE, BUILDING 258 McCLELLAN, CA 95652 PHONE: (916) 614-6200 FAX: (916) 614-6250 WEB: http://mnrc.ucdavis.edu MNRC McCLELLAN NUCLEAR RESEARCH CENTER SACRAMENTO, CA 95652 PHONE: (916) 614-6200 FAX: (916) 614-6250 7 June, 2013 United States Nuclear Regulatory Commission Attn: Document Control Desk US Nuclear Regulatory Commission Washington, D.C. 20555-001 Re: 2012 Annual Report for University of California Davis/ McClellan Nuclear Research Center, Docket No. 50-607, License No. R-130 To Document Control Desk:

Attached is the 2012 annual report for the McClellan Nuclear Research Center, submitted in accordance with the reporting requirements of the Technical Specifications document MNRC-0004-DOC-13 paragraph 6.7.1.

anks and Regards, Dr. Barry M. Klein, Director, McClellan Nuclear Research Center 4c,;-oo

1 C DAVIS MNRC' 2012 ANNUAL REPORT Docket Number 50-607 License Number R-130

UCMAVIS MNRCN M N- C9"' UCD/MNRC ANNUAL REPORT FOR 2012

1. Introduction The University of California, Davis, McClellan Nuclear Research Center (MNRC)

-consists of a research reactor, associated radiography and positioning equipment, and a wide variety of equipment to support broad-based research activities. This MNRC Annual Report is published each year in support of the license provided by the United States Nuclear Regulatory Commission (NRC).

The aforementioned license is for the operation of a steady-state TRIGA" reactor with pulsing and square wave capability.

It is the primary intent of this document to provide information relevant to the safe operation of the UCD/MNRC. A brief description of the MNRC facility and administration is followed by operational events and health physics information concerning this facility during CY 2012.

2. UCD/MNRC Facility Description The UCD/MNRC is located on the McClellan Industrial Park site; the reactor is housed in Building 258. The McClellan Industrial Park site is approximately 2600 acres, located eight miles northeast of Sacramento, California.

The UCD/MNRC facility is a three level 14,720 sq. ft. rectangular-shaped enclosure that surrounds a 2 MW research reactor. The UCD/MNRC provides four neutron beams to four bays for radiography and other research and commercial activities. All four bays are capable of using radiography film techniques, but Bays 1 and 3 normally use electronic imaging devices. Space, shielding and environmental controls are provided by the enclosure for neutron radiography operations performed on a variety of samples. Adequate room has been provided to handle the components in a safe manner.

In addition to the radiography bays, the UCD/MNRC reactor also has several in-core facilities ranging from a pneumatic tube system to a central irradiation facility.

For more detailed information on the UCD/MNRC project, the reader is referred to the UCD/MNRC Safety Analysis Report.

3.0 UCD/MNRC Administration UCD/MNRC Organization. The UCD/MNRC is licensed by the Nuclear Regulatory commission (NRC) to operate under the provisions of operating license R-130.

The University of California Regents have designated the Chancellor at UC Davis to be the license holder. The UCD Chancellor has in-turn delegated the Vice Chancellor for Research to be the licensee of record.

The UCD/MNRC is under the direction of the UCD/MNRC Director.

4.0 Facility Modifications (Section 50.59 of 10CFR Part 50), and experiments.

1. None UCDMNRC Annual Repor 22 M

LCDAVIS MNRC* UCD/MNRC ANNUAL REPORT FOR 2012 5.0 New Approved Experiments

1. Experiment Review Board (ERB) conducted for GE in-core detector experiment. Experiment authorized under K-4-43.

2. K-4-50 Irradiation of lubricant-coated aluminum coupons 6.0 Licensing and Regulatory Activities 6.1 NRC Items

a. The Nuclear Regulatory Commission (NRC) conducted their semi-annual audit during the week of 24 January, 2012. No significant findings were noted.

b. The Nuclear Regulatory Commission (NRC) conducted an unannounced security audit on 1 May 2012 during the performance of area wide First Responders and FBI training.

c. The Nuclear Regulatory Commission conducted an audit during the week of 10 July.

d. The Nuclear Regulatory Commission Project Manager for UCD/MNRC conducted a site visit during the month of July.

6.2 Nuclear Safety Committee (UCD/NSC)

a. The Nuclear Safety Committee performed two audits: Security (July), Radiation Safety (December), and the Chairman's audit (12/9/2012)

b. One NSC meeting was held: The NSC conducted their semi-annual meeting August.

7.0 OPERATIONS OPERATING HISTORY:

TOTAL OPERATING HOURS THIS YEAR: 1242.70 TOTAL OPERATING HOURS: 46323.24 TOTAL MEGAWATT HOURS THIS YEAR: 1185.81 TOTAL MEGAWATT HOURS: 61293.91 TOTAL NUMBER OF PULSES PERFORMED THIS YEAR: 0 TOTAL NUMBER OF PULSES PERFORMED: 473 7.1 UNSCHEDULED REACTOR SHUTDOWNS and NOTED PROBLEM AREAS:

In 2012, there were four (4) unscheduled shutdowns at the MNRC reactor facility. The following is a list of the unscheduled shutdowns:

2012 REACTOR SHUTDOWNS Type of Failures Total Number CSC 0 Other 4-TOTAL NUMBER OF SHUTDOWNS IN 2012 4 UICD/MNRC Annual Report2012 2

ICDAVIS MN ,C , UCD/MNRC ANNUAL REPORT FOR 2012 Jan Feb Mar Apr May Jun Jul IAug Sep Oct Nov Dec CSC 0 0 0 0 0 0 0 0 0 0 0 0 Other 0 0 0 1 0 0 0 1 1 0 1 0 Notes 1 2 3 4 Notes:

1: Loss of Shim 3 indications 2: Stack CAM alert/alarm.

3: Lass of Secondary Pump 4: Loss of Secondary Cooling Tower fan belt.

January

1. There were no unscheduled shutdowns in the month of January.

2. There were four callbacks to the facility in January.

a. One (1) Rod Withdrawal Prohibit alert. Alert cleared on acknowledgement.

b. Three (3) Security system faults.

Two (2) Communications check failures. No response required.

One (1) Proximity Reader failure. The alarm company replaced a power supply to correct the problem.

3. The NM-1000 noise issue is still present. Re-routing the Reactor Tank Bulk Temperature probe and cabling was required after signal interference required aborting a startup. Other instances of very low indicated power level (shut down) signal anomalies have required shutting down the DAC/CSC and NM-1000 to resolve. Troubleshooting continues.

February

1. There were no unscheduled shutdowns in the month of February.

2. There were three callbacks to the facility in February.

a. One (1) Rod Withdrawal Prohibit alert, and Stack Fault. Alerts cleared on acknowledgement.

b. One (1) Rod Withdrawal Prohibit alert, cleared on acknowledgment.

c. One (1) Scram-Data base timeout. Unable to reset, repairs were required to NM-1000.

March

1. There were no unscheduled shutdowns in the month of March.

2. There were no callbacks to the facility in March.

April

1. There was one unscheduled shutdown in the month of April.

a. Manual scram due to loss of rod position indication, Shim #3.

See anomaly report.

2. There was one callback to the facility in April

a. Security Alarm, spurious. Investigation showed no apparent cause identified, alarm cleared.

1. There were no unscheduled shutdowns in the month of May.

2. There were two (2) callbacks to the facility in the month of May.

a. Security Alarm, caused by biologics. Panel reset.

b. Rod Withdrawal Prohibit warning, cleared upon acknowledgement June Annu RepW 212 UCD/MNRC 3

t 'CDAVIS MNRC4 UCD/MNRC ANNUAL REPORT FOR 2012

1. There were no unscheduled shutdowns in the month of June.

2. There were two (2) callbacks to the facility in June.

a. Two (2) Rod Withdrawal Prohibit warnings, cleared upon acknowledgement.

July

1. There were no unscheduled shutdowns in July.

2. There were no callbacks to the facility in July.

August

1. There was one unscheduled shutdown in the month of August:

Stack CAM Argon and Noble Gas channels spiked above the alert and alarm set points. Manual scram initiated.

2. There were four callbacks to the facility in August

a. Four (4) Rod Withdrawal Prohibit warning, cleared upon acknowledgement.

September

1. There was one unscheduled shutdown in the month of September:

a. The Secondary System circulating pump motor failed during operation. Subsequent investigation showed one line side lead connector failed. The connector was replaced and the pump returned to service.

2. There was one callback to the facility in September

a. Stack CAM alert and alarm on two channels, with the third channe: 1 operating erratically. Repairs to the Stack CAM were required to return to service.

October

1. There were no unscheduled shutdowns during the month of October.

2. There were no callbacks to the facility in the month of October.

3. There is an ongoing issue with the NM-1000 instrument exhibiting noise interference at the low end of the indicating range. This noise occasionally interferes with performing pre-start checks and Rod Withdrawal Interlock checks. Troubleshooting is ongoing, with incremental improvements. This will continue to be one of the primary focus points for Operations until the noise issue is finally resolved.

November

1. There was one unscheduled shutdown in November.

a. Loss of the Secondary Cooling Tower fan drive belt. Belt replaced.

2. There were two callbacks to the facility in November.

a. 11/13/12: UPS fault; cleared on acknowledgment.

b. 11/24/12: UPS fault, Stack CAM alert/alarm; cleared on acknowledgement, December

1. There were no unscheduled shutdowns in December.

2. There were no callbacks to the facility in December.

UCD/MNRCAnnualRepoMt22 4

It DAVI MNRC UCD/MNRC ANNUAL REPORT FOR 2012

3. There is an ongoing issue with the NM-1000 instrument exhibiting noise interference at the low end of the indicating range. The wiring connections within the DAC were checked during the annual maintenance shutdown to attempt to resolve the noise issue. Approximately 8% of the connections in the DAC had issues, primarily in connection tightness.

4. Two fuel elements were found to be sticking in the upper grid plate during the fuel inspection. One element was removed from service due to inability to reseat the element following inspection. The element passed straightness and growth checks satisfactorily. There is no replacement fuel element for this core position, so a graphite element was inserted in the position. MNRC is implementing a quarterly maintenance item to rotate all fuel elements to attempt to alleviate this condition in the future.

7.2 ANOMALIES

During 2012, there were 2 reported anomalies at the MNRC facility. The specifics are listed below January There was one anomaly reported in the month of January. The Health Physics assessment of the Argon-41 released during the anomaly is included in the Health Physics portion of this report.

The Operations anomaly report is as follows:

Anomaly: Failure of the Argon-41 production system causing a release to the reactor room.

Initial conditions: Date 19JAN2012, Reactor had just been shutdown following an 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> irradiation run at 1.5 Megawatts.

On January 19, 2012 an Argon-41 production run was being performed.

At 1348 hours0.0156 days <br />0.374 hours <br />0.00223 weeks <br />5.12914e-4 months <br /> the irradiation part of the run was completed with no problems noted.

At 1358 the reactor was shut down after completion of gas transfer from the in tank target to the liquid nitrogen coil.

At this time all parameters for the evolution were normal.

lAW Special Operating Procedure SOP 07-01 Para IV. 18 radioactive Argon 41 was being transferred from the liquid nitrogen coil to the sample containers. The pressure readings on gage APG-2 went up to 300 psig and no further. The expected reading should have reached 1000 psig.

The Reactor Supervisor entered the Reactor Room to determine the cause of the problem. It was then noted that there was still frost all over the liquid nitrogen coil with the heaters energized and directed at the coil. An attempt was made to reposition the heaters. The heater power supply was cycled to determine their operability. These actions had no effect on the pressure indication on APG-2.

Meter readings on the sample containers indicated that some gas had been transferred.

The decision was made to discontinue the transfer and continue with removing the sample containers.

During this process it was noted that the readings on APG-2 were decreasing.

The liquid nitrogen dewar was raised to transfer any remaining Argon back to the liquid nitrogen coil.

The sample containers were disconnected and moved to the equipment room. During this process it was audibly noted that a CAM was alarming and that the Reactor Room Ventilation system had shifted to recirculation mode.

At this time the RSO was notified of the situation.

All personnel were evacuated from the reactor room and access to the Reactor Room restricted.

UCDANRCAnrmaIRePcft 2012 5

I C-DAVI MNRC -P *-*.'"'UCD/MNRC ANNUAL REPORT FOR 2012 What actions to correct anomaly.

After it was realized by personnel in the equipment room that a CAM was alarming and the Reactor Room ventilation system had shifted into recirculation mode, all personnel were evacuated from the Reactor Room and access restricted. Access was reestablished several hours later when the Reactor Room CAM (Continuous Air Monitor) indicated argon levels had returned to normal.

The entire process/procedure was performed the following day with inert Argon. Each step of the procedure was performed. Extensive leak checks encompassing the entire system yielded no evidence of system leakage during any step of the procedure. The investigation leads to the conclusion that one of the inlet quick disconnect jumpers was inadvertently disturbed during the process of shutting the outlet valves and disconnecting and capping the outlet jumper quick disconnects. Disconnect/capping occurs immediately prior to initiating the transfer of Argon-4 1.

What corrective actions are needed to prevent this anomaly from reoccurring in the future.

All personnel entering the Reactor Room will be retrained to take care to not disturb the system when it is set up.

All Operations and support personnel will be briefed on expected values and receive additional training on immediate actions in the event of alarms.

All Operations personnel will be briefed to announce any alarm whether it is expected or not.

All personnel will be briefed that if the expected pressure readings are not observed (i.e. too low), they will assume a leak and respond accordingly.

RADIOLOGICAL INVESTIGATION REPORT NO. 12-01 TITLE: Argon discharge during transfer for shipment DATE/TIME OF OCCURRENCE: 19 January 2012.

DESCRIPTION: During transfer of Ar-41 from condensing coil to shipping container, Ar-41 was released into the Reactor Room CAUSE: Indeterminate; possibly incomplete quick-disconnect connection or isolation valve at container not fully closed.

IMMEDIATE CORRECTIVE ACTIONS: Reactor Room CAM alarmed, causing reactor room ventilation to shift into recirculation mode. Reactor Room and Equipment Room were evacuated.

Argon released:

NOTE: The actual readings from the Stack CAM were partially a result of the radiation levels at the CAM, due to the Ar-41 in the adjacent reactor room. However, since there is no way to factor this out, it will be assumed that the readings were all from Argon in the sample chamber of the CAM Using the dilution factor from the SAR, the highest level reached in an unrestricted area(averaged over the first hour) was I.97E-08 ptCi/ml. This exceeds the 10CFR20 annual limit for release by just under a factor of two. By the end of the second hour, this level was down to 5.89E-09 JLCi/ml and by the end of four hours was down to 1.08E-09 paCi/ml, at which time the Stack CAM AR-41 reading had returned to its normal level.

Since no gas sample was taken in the Reactor Room, the activity was calculated using the formula for dose calculations from a semi-infinite cloud, based on the maximum recorded RAM reading of 160 mrem/hr. This showed the gaseous activity in the room to have been 1.92E-04 pCi/ml.

UCD/MNRC Annual RepWt 2012 6

MNRCz t-C OAVIS & _'

UCD/MNRC ANNUAL REPORT FOR 2012 A 1 liter gas sample was taken in the Equipment Room approximately 47 minutes after the incident and decay corrected back to the time of the incident. This showed the level in the equipment room to have been 2.76E-08

ýiCi/ml.

Personnel exposure:

The pocket dosimeter readings of the people present at the time of the incident read 30 mrem for the one person that was in the Reactor Room, and 10 mrem each for the two people in the Equipment Room.

PERMANENT CORRECTIVE ACTION;

a. Train operators on detailed actions for CAM alarms, including documenting readings in log and taking one minute histories on affected CAMs within 30 minutes of alarming.

b. Update Argon procedure to state that if any abnormal indication occurs during transfer, either from tank to coil or from coil to shipping containers that is accompanied by either a Stack CAM and/or Reactor Room CAM alert and/or alarm, to abort the procedure and place in a safe condition without entering the Reactor Room

c. Develop procedure to take a I liter gas sample in the Reactor Room from the Equipment Room.

April There was one anomaly reported in the month of April, included below.

Anomaly Report for Loss of Shim 3 Limit Switch Indication Time: 18 April, 2012 at 0845 Reactor conditions prior to the anomaly and what occurred during the anomaly:

The reactor was at 1 Megawatt steady state in automatic control for radiography operations. The operator saw the rod position indicator for the Shim 3 off the bottom (Green Bar on Hi Resolution Monitor) turn black, indicating the control rod had decoupled from the scram magnet and dropped into the core. The digital position indication did not change, and the Regulating Rod did not start driving out to compensate for the loss of Shim 3. The operator scrammed the reactor for loss of rod position indication.

Previous to this occurrence, Shim 3 would not indicate engaged during the Pre-Start checks at 0600. Visual inspection showed the control rod was latched and moved when withdrawn at the CSC, but the limit switch indications showed the control rod on the core bottom. Wire connector tightness checks and a reboot of the CSC computer restored proper indication. A rod operability check was successfully performed on Shim 3, and the rod drop time was 0.41 seconds. Multiple latch and withdrawal checks were performed on Shim 3 with no failures.

The Pre-Startup Checklist was performed successfully. At this time, the Senior Reactor Operator granted permission to continue operations.

The reactor was started up for radiography at 0656, with all indications normal on the startup. No indications of malfunction occurred until the time of the anomaly.

What actions were taken to correct this anomaly:

The reactor was scrammed. Subsequent troubleshooting found a high resistance connection between the limit switch signal wires and a connector strip in the Data Acquisition Cabinet (DAC). The leads were lifted, cleaned of corrosion, and reseated. Other connections on that connector strip were tightness checked. All new and older connector blocks of the style used in the back of the DAC have the same problem. They work well for single wires, but if two or more wires are inserted in one slot, the only way to be sure of making good contact on all the wires is to strip about 5/8" of insulation off all the wires and then twist them tightly around each other before placing them into the compression slot.

This is a common problem with some of the screw compression terminal blocks, as evidenced with terminal TB 11-2, which was the only 12 volt return path for Shim Rod 3. There were two wires in that slot. The two wires were the UCDdMNRCAnnua Repot 2012 7

C(DAVIS MNRC UCD/MNRC ANNUAL REPORT FOR 2012 same gauge, but one was heavily tinned and the other was not. The tinned wire was preventing good compression of its companion wire. Although the wire worked for many years, there was enough space to allow slow oxidation of the un-tinned wire until it eventually lost good contact.

This is a common problem even for expensive state of the art screw type compression terminal blocks. Two other places in terminal block TB10 were found where a wire from a slot occupied by two wires could be pulled out easily.

Control Rod operability checks were performed successfully on Shim 2, Shim 3, and Shim 4. Control rod drops times for these three rods were 0.36, 0.41, and 0.39 respectively. Shim 2 and Shim 4 were checked due to having their leads lifted during troubleshooting. The Prestart interlock checks for these rods passed. The Reactor Manager granted permission to resume operations at 1250 on 19 April, 2012.

What corrective actions are needed to prevent this anomaly from reoccurring in the future:

Current plans are now in place to lift, inspect, clean, and reconnect/tighten all leads associated with the connector strips in the DAC during the next reactor maintenance shutdown cycle 7.3 MAINTENANCE OTHER THAN PREVENTIVE:

January

1. Replaced expended helium supply bottle.

2. Disconnect/relocate/reconnect the Reactor Tank Bulk Temperature probe to reduce generated noise in the NM-1000 channel.

3. Replace failed communication module in the NM-1000 Nuclear Instrument.

4. Replace the CPU battery in the BAY Continuous Air Monitor (CAM).

All settings were reset sat.

February

1. Corrected three (3) cold solder joints on card Al on the NM-1000.

2 Replaced the NM-1000 nuclear instrument communication module with the original repaired unit.

March

1. Replaced the burned out motor for EF-2 Building Ventilation blower.

2. Replaced the gas control valve and blower motor assembly including the squirrel cage for AC-il (Lab ventilation).

3. Replaced the lower Security Light fixture on the Stack.

4. Replaced/tested satisfactory the Reactor Room normal path HEPA filter.

5. Replaced the failed Photohelic on the Bay CAM.

6. Replaced the Geiger-Muller tube in the spare Radiation Area Monitor.

7. Replaced the CPU card in the Bay CAM April

1. Reseated the Shim 3 Rod Position Indication plug. Rebooted CSC and performed CSC operability checks sat.

2. Fixed a loose ground/return connection in the DAC for Shim 3 Rod Position Indication. Performed the DS064 utilities test on all rod control limit switches.

UCD/MNRC Annual Repod 2012 8

L'CDVI*S MNRC VkLA IL-M-b' UCD/MNRC ANNUAL REPORT FOR 2012

3. Repaired a burned blower motor load connector for EF-2 (Building Ventilation). Phase to ground and motor to ground checks sat.

Replaced the blown motor fuses. Fan rotation verified sat.

1. Replaced the Argon Channel check source solenoid in the Bay Continuous Air Monitor (CAM).

2. Replaced the Bay CAM air flow Photohelic gage.

3. Replaced the Stack CAM Argon Channel SCA card, replaced the failed Photohelic with the Bay CAM unit.

June

1. Replaced failed compressor contactor unit in AC-9 (Radiography Control Room ventilation).

July

1. Replaced the Helium System supply bottle.

August

1. Performed troubleshooting to determine the cause of a loss of UPS power. Troubleshooting showed no outstanding issues.

2. Replaced the Demineralizer conductivity outlet meter with a Thornton 870 unit for troubleshooting.

3. Replaced the Stack CAM Particulate Channel check source solenoid valve.

4. Swapped out the Stack CAM Argon/Noble Gas channel card for the Bay CAM and back for troubleshooting.

September

1. Replaced the Argon/Noble Gas channel circuit card and performed calibration checks sat.

2. Replaced the expended He supply bottle.

3. Replaced the failed/burned electrical connector for one of the Secondary Pump motor windings at the mother terminal box. Meggar checks on all windings checked sat.

October

1. Replaced the Reactor CAM check source air pump.

2. Replaced the Reactor CAM Particulate channel check source solenoid.

3. Troubleshot the Data Acquisition Console (DAC) computer power supply failure. Replaced the computer power supply cooling fan.

4. Performed troubleshooting to find and repair noisy indications from the DAC to the CSC including the NM-1000. Cleaned card edge connectors of all cards in the DAC computer. Replaced both AI016 cards and verified good ground connections.

5. Performed troubleshooting to repair the DAC top shelf 15 VDC power supply due to noise issues in the DAC output circuits. Tested the power supply when disconnected from the load SAT. Determined the noise signal was coming from the Reactor CAM. Reconnected the old power supply.

6. Troubleshot noise/high motor current on the Reactor CM. Found the ground and L2 leads had been inadvertently switched during Pressure switch replacement. The leads were returned to the proper terminals, all retests sat.

UCaVMNRCAnrnua Repd 20W29

ICbDAVIS f UCD/MNRC ANNUAL REPORT FOR 2012

7. Replaced the printer on the Reactor CAM.

November

1. Replaced the micro-switch assembly on HV-1 (in tank component Helium supply pressure switch), adjusted set point to 9.5 psig on 12.5 psig off. Replaced on service supply bottle December

1. MNRC completed the annual reactor maintenance shutdown during the month of December. Technical Specification required periodic maintenance as well as general maintenance was performed Parametric values noted during testing are as follows:

Control Rod Worth:

Transient Rod: $1.95 Shim 1: $2.63 Shim 2: $2.60 Shim 3: $2.72 Shim 4: $3.08 Regulating Rod: $2.83 Control Rod Scram Drop Times:

Transient Rod: 0.38 sec Shim 1: 0.38 sec Shim 2: 0.37 sec Shim 3: 0.41 sec Shim 4: 0.39 sec Regulating Rod: 0.39 sec Shutdown Margin: $5.56 At Power Scram values: NPP-1000: 103% indicated, NM-1000: 103% indicated.

A nuclear instrument calorimetric calibration was performed. Both the NPP channel and the NM-1 0000 channel of Nuclear Instruments were satisfactory, and no adjustments were required.

3. Replaced the Stack ventilation damper with a new unit.

4. Measured stack air flow and updated the CAM alarm set points and AR-41 effluence tracking spreadsheet 7.4 Training January

1. 3 Senior Reactor Operators attended Ar-41 Course of Action Response to Alarms training.

Februa

1. 2 Senior Reactor Operators attended Ar-41 Course of Action Response to Alarms training.

2. All Senior Reactor Operators completed Facility Design and Operating Characteristics training.

3. All Senior Reactor Operators completed Administrative Controls and Procedures training.

March

1. All licensed Senior Reactor Operators took and passed the Biennial Operators Requalification Exam April UCadMNRC Annual Report 2012 10

M.NRDAVI ..

MV*" * '* UCD/MNRC ANNUAL REPORT FOR 2012 ot

1. All facility personnel attended the annual ALARA and Security training.

1 Participated in a two (2) day area wide security exercise with local first responders and the FBI, conducted by the Department of Energy Y-12 security training group.

2. Two trainees attended Receiving Radioactive Material (Lesson Plan B amendment).

June

1. Hosted and conducted training for the pilot program for the Nuclear Science and Security Consortium (NSSC) Summer School. Conducted multiple training sessions/experiments for the NSSC classes. This included Neutron Activation Analysis, Neutron Transmission studies, and Reactor Neutronics.

July

1. Conducted training sessions/experiments for the UCDavis COSMOS summer school. This included a facility tour, Neutron Activation Analysis, and Principles of Radiation.

2. All Senior Reactor Operators successfully completed the Annual Operators Exam.

3. All Senior Reactor Operators attended training on the new CAM alarm set-points sheet.

August

1. Conducted forklift operator training for two facility personnel September

1. There was no scheduled training for the month of September.

2. The Reactor Supervisor and the Facility Manager attended the annual TRTR conference.

October

1. MNRC coordinated and conducted a contaminated injured man/radioactive spill drill with the Sacramento Metro Fire Department and the University of California Davis Medical Center.

2. Two Reactor Operator trainees/Level I Radiographers attended Use of Irradiation Request Database training.

3. One Reactor Operator trainee attended DOC-73 (Maintenance Program) training.

4. Two Reactor Operator trainees attended Technical Specifications training.

5. All Licensed Operations personnel and trainees attended the 2012 Emergency Drill briefing.

6. Two Reactor Operator trainees and the RSO attended Spill Procedure, including donning and removing Anti-C clothing training.

November

1. Two Reactor Operator trainees attended Scrams and interlocks training.

2. Operations personnel attended Fuel training.

December U*.NRC Annual RW, 2M2

UCbAVIS zt0 MNRCV; UCD/MNRC ANNUAL REPORT FOR 2012

1. Two Reactor Operator trainees attended Removal of items from the Reactor Tank training.

2. Operations personnel attended Fuel Handling training.

UM~MNRCAnrn*IWRegWM2 202

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L("DAVIS MNRC* UCD/MNRC ANNUAL REPORT FOR 2012 Reactor Tank IrradiationFacilities Total Number of IrradiationsCompleted (2012)

-- Pneumatic Silicon Fixture Central Facility Argon Neutron Irradiator - 2012 Total - 2011 Total 90 80 70 60 50 40 30 20 10 0

JAN FEB MAR APR MAY JUN JUL AUG SEP OCT NOV DEC UCDMNRC AnnMaL R"I 2012 16

t ( IAVIS UCD/MNRC ANNUAL REPORT FOR 2012 Bay Utilization (Shutter Operations)2012 500 450 i 400 300 2 50 E25(300 o 250 100 150 Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec EBay 1 333 331 441 351 343 279 361 223 169 229 286 114

• Bay2 137 230 108 157 138 200 145 256 191 125 116 42 OBay3 11 6 7 1 2 7 7 4 2 12 9 0 OBay4 2 5 28 13 0 11 4 3 1 23 22 0 Months UCDLNRC Annual Report 2012 17

t ( DAWS MNRC`ý UCD/MNRC ANNUAL REPORT FOR 2012 Bay IrradiationRequests Completed 2012 400 37S 350 I

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UCDAVIS MNRC*

MCCLELLAN NUCLEAR RESEARCH CENTER UCD/MNRC ANNUAL REPORT FOR 2012 8.0 Radioactive Effluents A summary of the nature and amount of radioactive effluents released or discharged to the environment beyond the effective control of the MNRC, as measured at or prior to the point of such release or discharge, include the following:

8.1 Liauid Effluents No liquid effluents were released during 2012.

8.2 Airborne Effluents Airborne radioactivity discharged during 2012 is tabulated in Table 1 below.

TABLE 1 2012

SUMMARY

OF AIRBORNE EFFLUENTS MONTH TOTAL EST.NAX AVG. FRACTION OF EST. DOSE (2) FRACTION OF TOT. EST. AVERAGE EST. CONC. OF APPLICABLE FROM Ar-41 APPLICABLE QUANTIT1Y CONC. OF QUAN. Ar-41 IN 10CFR20 Ar-41 FOR 10CFR20 OF ACT. PART. ACT.

Ar-41 UNRESTRICTED CONC. LI[MT FOR UNRESTRICTED DOSE IN RELEASED RELEASED AREA ()(3) UNRESTRICTED AREA (1) CONSTRAINT PART. WITH AREA (1) FOR FORM HALF-LIFE UNRESTRICTED WITH > 8 DAYS AREA (1X4) HALF-LIFE

>8 DAYS (CI) (uCI/ml) (%) (mrom) (%) (CI) (uCl/mi)

JAN 3.94 2.36E-10 2.4% 1.44E+00 14.38% NONE NONE FEB 1.73 1.11E-10 1.1% 6.75E-01 6.75% NONE NONE MAR 1.75 1.05E-10 1.0% 6.37E-01 6.37% NONE NONE APR 1.82 1.12E-10 1.1% 6.84E-01 6.84% NONE NONE MAY 1.00 6.40E- 1I 0.6% 3.90E-01 3.90% NONE NONE JUN 1.52 9.74E-1 1 1.0% 5.93E-01 5.93% NONE NONE JUL 1.25 8.04E-1 1 0.8% 4.89E-01 4.89% NONE NONE AUG 1.14 7.33E-11 0.7% 4.46E-01 4.46% NONE NONE SEP 0.78 5.03E-1 1 0.5% 3.06E-01 3.06% NONE NONE OCT 0.77 4.92E-11 0.5% 2.99E-01 2.99% NONE NONE NOV 0.93 5.95E-1 1 0.6% 3.62E-01 3.62% NONE NONE DEC 0.34 1.85E-11 0.2% 1.12E-01 1.12% NONE NONE TOT 16.95 1.06E-09 6.43 NONE NONE AVG 0.54 (total 1.41 8.81 E-1 1 0.9% annual dose) 5.36%

(1) This location is 240 meters downwind which is the point of maximum expected concentration based on the worst case atmospheric conditions (see MNRC SAR Chapter 11).

(2) Based on continuous occupancy and the calculation techniques used in Appendix A of the MNRC SAR (Ar-41 at 2.3E-10 uCi/ml continuous for one year equals 1.4 mrem).

(3) 10CFR20 Limit for concentration is 1E-8 (Appendix B, Table 2);

(4) Constraint for dose is 10 mrem/year [10CFR20.1101(d)]

4JCDWNRCAnrW..Report 2012 19

UCDAVIS MNRC*

McCLELLAN NUCLEAR RESEARCH CENTER UCD/MNRC ANNUAL REPORT FOR 2012 8.3 Solid Waste No waste shipments were made in 2012 9.0 Radiation Exposure Radiation exposure received by facility operations personnel, facility users, and visitors during 2012 is summarized in Table 2 below.

TABLE 2 2012

SUMMARY

OF PERSONNEL RADIATION EXPOSURES NUMBER OF AVERAGE GREATEST AVERAGE GREATEST INDIVIDUALS TEDE INDIVIDUAL EXTREMITY EXTREMITY PER TEDE INDIVIDUAL (mrem) (mrem) (mrem) (mrem)

FACILITY 10 29 56 49 99 PERSONNEL(1 )

FACILITY 10 <1 1 *

• USERS VISITORS 1138 <1 8 * *

(1) Only five facility personnel actually received exposure. Two were not MNRC employees the entire year.

• Extremity monitoring was not required.

UCDVdNRC AnnuWA RP 2012 20

UCDAVIS MNRC MCCLELLAN NUCLEAR RESEARCH CENTER UCD/MNRC ANNUAL REPORT FOR 2012 10.0 Radiation Levels and Levels of Contamination Radiation levels and levels of contamination observed during routine surveys performed at the MNRC during 2012 are summarized in Table 3 below.

TABLE 3 2012

SUMMARY

OF RADIATION LEVELS AND CONTAMINATION LEVELS DURING ROUTINE SURVEYS AVERAGE HIGHEST AVERAGE HIGHEST (mrem/hr) (mrem/hr) (dpm/lOOcm2 ) (dpm/lOOcm 2 )

OFFICE SPACES <0.1 <0.1 <800(l) <800(l)

REACTOR CONTROL RM <0.1 <0.1 <800(l) <800(1)

RADIOGRAPHY CONTROL RM <0.1 <0.1 <800(1) <800(1)

COUNTING LAB <0.1 <0.1 <800(1) <800(1)

STAGING AREA <0.1 <0.1 <800(1) <800(1)

COMPOUND <0.1 <0.1 <800(1) <800(1)

EQUIPMENT RM 0.48 90 <800(1) <800(1)

DEMINERALIZER AREA 24 290 <800(1) <800(1)

REACTOR RM 1.4 540 <800(1) <800(1)

SILICON STORAGE SHED <0.1 <0.1 <800(1) <800(1)

RADIOGRAPHY BAYS 2.0* 730* <800(1) <800(1)

(1) <800 dpm/100 cm 2 = Less than the lower limit of detection for a swipe survey.

• Due to Bay 1 Storage Areas; all other areas and bays are significantly lower (typically <0.1 mrem/hr).

UCDWNRC AnW Report2012 21

IJCDAVIS MNRC*

McCLELLAN NUCLEAR RESEARCH CENTER UCD/MNRC ANNUAL REPORT FOR 2012 11.0 Environmental Surveys Environmental surveys performed outside of the MNRC during 2012 are summarized in Tables 4 & 5 below. The environmental survey program is described in the MNRC Facility Safety Analysis Report.

TABLE 4 2012

SUMMARY

OF ENVIRONMENTAL TLD RESULTS (WITH NATURAL BACKGROUND"1 ) SUBTRACTED)

AVERAGE HIGHEST (mrem) (mrem)

ON BASE (OFF SITE 1-20 & 64) 2 10 ON SITE (SITES 50 - 61 & 65-71) 10 18 (1) Natural background assumed to be the off base (Sites 27-42) average of 28 mrem.

UC&Al RC AnnuefR6poWM 2012 22

UCDAVIS MNRC McCLELLAN NUCLEAR RESEARCH CENTER UCD/MNRC ANNUAL REPORT FOR 2012 TABLE 5 2012

SUMMARY

OF RADIOACTIVITY IN WELL WATER ALPHA BETA TRITIUM Cs-137 (pCi/I) (pCi/I) (pCi/I) (pCi/I)

AVERAGE <MDA 3.60E+00 <MDA <MDA HIGHEST n/a 5.09E+00 n/a n/a MDA is the minimum detectable activity at the 95% confidence level.

The MDA range for the analyzed radionuclides (pCi/L).

MIN MAX Alpha 1.16E+00 1.49E+00 Beta 2.04E+00 2.08E+00 Tritium 3.04E+02 3.49E+02 Cs-137 5.25E+00 7.92E+00 UCD%*NRC AnnuwWRepcd 2012 23