ML14183A016

2013 Annual Report for University of California Davis/Mcclellan Nuclear Reseach Center, Docket No. 50-607, License No. R-130

ML14183A016
Person / Time
Site:	University of California-Davis
Issue date:	06/27/2014
From:	Klein B McClellan Nuclear Research Center
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML14183A016 (27)

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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 27 June, 2014 United States Nuclear Regulatory Commission Attn: Document Control Desk US Nuclear Regulatory Commission Washington, D.C. 20555-001 Re: 2013 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 2013 annual report for the McClellan Nuclear Research Center, submitted in accordance with the reporting requirements of the Technical Specifications document MNRC-0004-DOC-1 3 paragraph 6.7.1.

Thanks and Regards, Dr. Iarry M. Klein, Dir ctor, McClellan Nuclear Research Center Ao~o

I ( DAVISi MNRC*f-2013 ANNUAL REPORT Docket Number 50-607 License Number R-130

I ( DAVIS MNRC MW NRCLIN W 5 . ,t UCD/MNRC ANNUAL REPORT FOR 2013

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 TRIGATM 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 2013.

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. Four (4) facility modifications were completed/cleared in January.

a: FM-III-05-01. Bay 3 console and Computed Radiography upgrade UC"~NRC AnnuaI Repcot2013 1

I(DAVIS NRC.4, UCD/MNRC ANNUAL REPORT FOR 2013 b: FM-Ill-07-01. X-ray equipment A/C power distribution c: FM-III-09-01. Security System Modifications d: FM-II1-12-01. 480V temporary power to "Oscar" Motoman robot 5.0 New Approved Experiments

1. Approved K-4-51, Geochronology Sample Irradiation - Cadmium lined sample in the Central Facility 6.0 Licensing and Regulatory Activities 6.1 NRC Items

a. The Nuclear Regulatory Commission conducted a semi-annual audit the week of 15 January 2013. No significant findings reported.

b. The Nuclear Regulatory Commission conducted its first Cyber Security audit at MNRC on 15 January 2013.

c. The Nuclear Regulatory Commission conducted an audit the week of 21 May 2013. No significant findings reported.

d. Nuclear Regulatory Commission EDO and California state regulators toured the facility on 15 August.

e. The Nuclear Regulatory Commission conducted an audit the week of 2 December.

6.2 Nuclear Safety Committee (UCD/NSC)

a. The Nuclear Safety Committee conducted an Operations audit during the month of May.

b. The Nuclear Safety Committee held its semi-annual meetings on 24 January and 1 August.

c. The Nuclear Safety Committee performed an audit of the Radiation Safety Program during the month of December.

7.0 OPERATIONS OPERATING HISTORY:

TOTAL OPERATING HOURS THIS YEAR: 992.87 TOTAL OPERATING HOURS: 47316.11 TOTAL MEGAWATT HOURS THIS YEAR: 828.68 TOTAL MEGAWATT HOURS: 62222.59 TOTAL NUMBER OF PULSES PERFORMED THIS YEAR: 10 TOTAL NUMBER OF PULSES PERFORMED: 484 7.1 UNSCHEDULED REACTOR SHUTDOWNS and NOTED PROBLEM AREAS:

In 2013, there were four (4) unscheduled shutdowns at the MNRC reactor facility. The following is a list of the unscheduled shutdowns:

UCUD NRC AnnuW Report 2013 2

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l.CtAH IfMA4 7 ýIU UCD/MNRC ANNUAL REPORT FOR 2013 2013 UNSCHEDULED REACTOR SHUTDOWNS Type of Failures Total Number CSC 2 Other 2 TOTAL NUMBER OF UNSCHEDULED SHUTDOWNS IN 2013 4 Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec CSC 2 0 0 0 0 0 0 0 0 0 0 0 Other 0 0 0 0 0 0 0 0 0 1 1 0 Notes 1 2 3 Notes:

1: CSC PS-1 faulty wiring 2: NM-1000 cable connection 3: NPP-1000 High Power Scram Janua~

1. There were two unscheduled shutdowns in the month of January.

a Silent scram due to power supply fluctuations in the CSC. See attached anomaly report.

b. Startup aborted prior to reaching 50 watts due to power supply fluctuations in the CSC. See attached anomaly report

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

Februa

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

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

March

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

2. There was one callback to the facility in March.

a. Rod Withdrawal Prohibit (RWP) alert, cleared on acknowledgement.

April

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

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

a. Systems malfunction, apparent cause was a power interruption.

b. Security system alarm, alarm spurious clear upon arrival.

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

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

June

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

2. There was one callback to the facility in the month of June.

a. UPS Fault, cleared on acknowledgement.

July

1. There were no unscheduled shutdowns in July.

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, UCD/MNRC ANNUAL REPORT FOR 2013

2. There was one callback to the facility in the month of July.

a. Rod Withdrawal Prohibit alert, cleared on acknowledgement.

August

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

2. There was one callback to the facility in the month of August.

a. Security system alarm. Alarm spurious, cleared upon reset.

September

1. There were no unscheduled shutdowns in the month of September:

2. There was one callback to the facility in the month of September.

a. Security system alarm. Alarm spurious, cleared upon reset.

October

1. There was one unscheduled shutdown in the month of October. See included Anomaly Report

2. There was one callback to the facility in the month of October.

a. Rod Withdrawal Prohibit alert, cleared on acknowledgement November

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

a. NPP-1000 scram during reactor startup. All instrumentation prestart checks for NM-1000 and NPP-1000 verified sat. All conditions and instrumentation satisfactory on subsequent reactor startup.

2. There was one callback to the facility in the month of November.

a. Rod Withdrawal Prohibit alert, cleared on acknowledgement December

1. There were no unscheduled shutdowns in December.

2. There was one callback to the facility in the month of December.

a. Rod Withdrawal Prohibit alert, cleared on acknowledgement.

7.2 ANOMALIES

During 2013, there were 2 reported anomalies at the MNRC facility and 2 Radiological Incident Investigations. The specifics are listed below January There was one anomaly reported in the month of January. The report is as follows:

Anomaly Report for Silent Scram due to CSC PS-l power supply Time: 1135, 15JAN2013 Reactor conditions prior to the anomaly and what occurred during the anomaly:

The reactor was operating for radiography in automatic control at 1 MW for approximately 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />.

UCDMNRC Annu1 Repor 2013 4

t( DAVIS MNRC4 WWAMSN*,. K ,A UCD/MNRC ANNUAL REPORT FOR 2013 The operator saw that all six control rods indicated that they were on the bottom (black indication on the high resolution monitor), but the magnets were still energized with the rod position indications showing the drive motors had not reset from the steady state positions noted immediately prior to the occurrence. The operator noted that reactor power as indicated on the NPP-1000 and NM-1000 was decreasing to less than 1% power, with a negative period indicated on the NM-1000. The operator initiated a manual scram, resetting the drive units, and verifying that the reactor was in fact shutdown.

History Playback showed no alerts or alarms at the time of the rod drop.

Following the shutdown, two operators attempted to cause this to repeat by energizing the control rod magnets, withdrawing one rod to 50 units, and then causing disturbances on the console similar to those that normally occur during operation. No switch or button bump caused the problem to reoccur. Prestart scram checks were performed with no problems noted. The Reactor Supervisor granted permission to return to operation.

The subsequent reactor startup was aborted when the console power dimmed, all lighted buttons flickered, and the latched control rods dropped. The magnet indications flickered but remained energized, with no motion of the drive units to reset them to zero. The reactor was manually scrammed.

Power supply checks found that one lead on the CSC power supply PS-l was corroded/loose.

What actions were taken to correct this anomaly:

The lead was lifted, cleaned, and soldered to the post on PS-l.

Subsequent reactor prestart and scram checks passed with no issues noted. The Reactor Supervisor granted permission to recommence operations.

What corrective actions are needed to prevent this anomaly from reoccurring in the future: None August There were no anomaly reports in the month of August, but one Radiological Investigation Report was issued, as follows:

RADIOLOGICAL INVESTIGATION REPORT NO. 13-01 TITLE: SKIN CONTAMINATION DATE/TIME OF OCCURANCE: August 1 5 th 2013 at -15:00 hrs DESCRIPTION: An employee was unable to clear the equipment room hand and foot monitor due to an alarm on the right hand detectors.

Detectable counts were confirmed using a Ludlum Model 3 frisker. A U Annual Report 2013 MDMNRC 5

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MNRC, UCD/MNRC ANNUAL REPORT FOR 2013 gross measurement detected 100 CPM. The employee's hand was decontaminated using tape and hand cleaner until the frisker showed only background counts. After the decontamination, the employee was able to clear the hand and foot monitor.

CAUSE: The employee was one of four individuals inspecting the fuel transfer cask to measure dimensions for a future project. None of the employees were wearing gloves during the inspection. Areas of the cask that were inspected were the lifting lugs, top access hole, the vent and drain holes, and the drawer at the bottom of the cask. It is likely the employee contaminated his right hand when accessing the drawer at the bottom of the cask. A dry swipe of the inner part of the drawer showed no contamination. A wet swipe of the area in the drawer revealed 600 counts above background. No other employees had measureable contamination on them. The root cause is determined to be not posting the transfer cask as internally contaminated. If the cask had been posted as internally contaminated, the employee would have been wearing gloves and a lab coat before touching the internal components of the cask per training.

DOSE CONSEQUENCES: Due to the amount of contamination and the duration of the contamination the external dose to the employee is not significant (i.e. <1 mrem). After interviewing the employee, it is determined that any uptake of contamination was unlikely.

IMMEDIATE CORRECTIVE ACTION: The cask was survey for contamination on its outer surfaces as well as the floor around the cask. No contamination was measured. All access points to the inside of the cask have been taped off and marked as "radioactive".

PERMANENT CORRECTIVE ACTION: The cask shall remain classified and posted as internally contaminated. Minimum personal protective equipment (i.e. gloves and lab coat)shall be worn when access the internals of the cask.

October There was one anomaly report and one Radiological Investigation Report in the month of October. The reports are as follows:

1. Anomaly Report Anomaly Report 3 October 2013 Time: 0940 Reactor Power Level: Performing reactor startup 5% NM-1000, 10 % NPP-1000 in Manual.

Describe the reactor conditions prior to the anomaly and what occurred during the anomaly:

After completing a satisfactory pre-start checklist, a normal reactor startup was commenced at 0930. During the initial portions of the startup all reactor conditions of power level indication and temperature were normal. Core excess was determined to be $5.80.

UCD/MNRC Annual Ro 2"13 6

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MNR.C.. *, UCD/MNRC ANNUAL REPORT FOR 2013 The reactor startup was continued and normal indications of power increase were observed as well as normal indications of core temperature increase above 1% power. Both the NM-1000 and the NPP-1000 indicated the same and tracked from 1% to 5% indicated on the CSC console. As power level was increased above 5% the NM-1000 indication did not increase while the NPP-1000 level continued up to 10 %, this divergence is not normal.

The reactor startup was halted/aborted and power level stabilized in manual and when power indications did not essentially match each other the reactor was shut down.

What actions were taken to correct the anomaly:

The facilities electronic engineer was consulted and quickly began to investigate the problem.

The reactor was shut down to troubleshoot the indication problem.

It was determined that an electrical connector in the lower NM-1000 cabinet was not in the correct location.

The NM-1000 cabinets were inspected the night before (while the reactor was shut down) in an attempt to locate and correct an unknown source of intermittent electronic noise that is only apparent when the reactor is shut down and indications are at the very low end of the indicating range. During these checks, some electrical connectors were disconnected/ inspected. A High voltage cable from the HV Monitoring and Distribution Box was subsequently reinstalled on the wrong connector (J3 vice J2) in the NM-1000 lower cabinet.

The connection error was not noticed by the electrical engineer or the Reactor Supervisor.

All NM-1000 indications appeared normal after the inspections.

The electrical cable was connected to the proper connector and satisfactory prestart checks were performed.

The Facility Director was informed of the anomaly and corrective action, permission was given to restart the reactor. On the subsequent startup, again all power readings were as expected and the core excess was again determined to be $5.80. Reactor power increase was as expected and normal up to 50 % (1 MW) on both the NM-1000 and the NPP-1000.

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

There are only two places this cable can connect to in this cabinet.

The incorrect connector has been positively identified and capped to prevent this anomaly from recurring.

The facilities Electronics Engineer will continue to perform troubleshooting and diagnostics in order to identify the intermittent source of the noise in the NM-1000.

UC4WNRC Am.W Repod 2013 7

L CDAVIS MNRC4 MN C>....

LI - -ILM tt UCD/MNRC ANNUAL REPORT FOR 2013 This is an ongoing maintenance item that ultimately is retested by performing the startup checklist and starting up the reactor to verify indications and successful troubleshooting.

2. Radiological Investigation Report RADIOLOGICAL INVESTIGATION REPORT NO. 13-02 TITLE: Contamination Associated with Irradiation Request 13-1975 DATE/TIME OF OCCURANCE: October 2 nd 2013 at -16:00 hrs DESCRIPTION: Potassium/Argon date is an established method to determine the age of geological samples. While this experiment is routinely performed at other TRIGA reactors, it had never been performed at MNRC. The experiment was evaluated for safety and feasibility. The geological samples were surrounded with approximately 50 grams of bare cadmium, placed in an inner aluminum canister, and then sealed in an outer aluminum canister. It was known that the outer aluminum canister would have to be cut open in order to recover the sample after the irradiation.

The sample was irradiated for 12 MW hours in the central irradiation facility per the request of the customer. After irradiation the sample was transfer from the central irradiation facility to the side of the reactor tank where is decayed in place. After a cool down period of 13 days, the sample was removed from the reactor tank. Exposure readings were near anticipated levels, indicating that no strongly neutron absorbing material had been present in the experiment other than the cadmium. At this time, it was determined to proceed with the disassembly of the experiment. The experiment was then moved to the equipment room where both ends of the outer aluminum canister were removed, via a small pipe cutter, in open air over a bag to collect contaminated/activated material. The disassembly time was approximately 15-20 minutes. Two workers were involved in the disassembly of the experiment and a third was inside the reactor room working on unrelated equipment. No other employees were upstairs during the event. Periodically, the workers' gloves were frisked in order to check for contamination. No contamination was found on the workers' gloves from machining on the outer aluminum canister. At this point the inner container was removed and the three pieces of cadmium (top, side, and bottom pieces) were removed and placed in a plastic bag. A frisk of the workers gloves (who handled the cadmium) revealed contamination levels of 250,000 dpm/frisk. At this time some fraction of the contamination fell on to the detector itself and the health physics staging area in the equipment room.

Once the contamination was discovered a third employee inside the reactor room was asked to retrieve the materials for decontamination.

UCDMNRC Annual Report 2013 8

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MNR , UCD/INRC ANNUAL REPORT FOR 2013 After this the third employee frisked clean on the hand and foot monitor and left the equipment room. Decontamination of the health physics staging area took place. Approximately 2 square feet of area required decontamination. Large area swipes of the floor were taken.

The first large area swipe indicated contamination level of approximately 10,000 dpm/frisk. Subsequent large area swipes gave no indication of removable contamination. All material from the disassembly of the experiment was placed in bags and labeled as radioactive material. Swipes of the work bench where the disassembly took place did not indicate any contamination. Upon completion of the decontamination of the equipment room it was discovered a single employee had contamination on one wrist at a level of 10,000 dpm/frisk.

The size of the contaminated area was approximately 1-2 square inches.

At this time personal decontamination took place until the individual successfully completed a whole body frisk with no contamination detected.

CAUSE: It was not anticipated that a layer of loose radioactive oxide would form on the outside of the cadmium used in the experiment.

Therefore, the removal of the experiment from the primary, secondary, and cadmium layer were not performed inside of a fume hood. A more thorough planning of the disassembly of the experiment may have prevented the contamination event in a non-posted contamination area.

DOSE CONSEQUENCES: It was estimated that after a 2 week cool down time, approximately 2-3 mCi of cadmium would remain in the cadmium filter. It was also estimated that approximately 30-60 minutes would be required for two workers to disassemble the experiment and that each work would receive approximately 10 mrem. Based on TLD dosimetry two workers received 13 mrem and less than 10 mrem (dose reporting threshold) whole body respectively. Based on the level and location of the personal contamination it is unlikely there was any uptake of contamination by either worker. The extremity dose of the worker, that was primarily handling the experiment, was determined to be 302 mrem during the month during this incident. Given the other radiological work occurring during that month, it is likely that the majority of this extremity dose was from this single incident.

IMMEDIATE CORRECTIVE ACTION: The two workers involved in the contamination were retrained in health physics procedures. It was emphasized that thorough planning of experimental disassembly is a requirement in current MNRC health physics procedures.

PERMANENT CORRECTIVE ACTION: This type of geological dating experiment shall not be performed where there is a reasonable risk of spreading contamination outside of a posted contamination area (i.e. PTS fume hood). In order for this type of experiment to be performed in the future, the source of potential contamination (i.e. oxidation layer on UMUNRCAnnuW RepM~2013 9

I (DAVIS MNRC UCD/MNRC ANNUAL REPORT FOR 2013 the cadmium filter) must be eliminated. This can be accomplished by increasing the decay time of the experiment inside the reactor pool until the vast majority of the Cd-115 decays away. This would require an additional 2-3 week cool down time. Alternatively the cadmium filter can be sealed before irradiation so that all contamination that may be produced is contained. Regardless all subsequent disassembles of experiments of this type should be performed inside of a fume hood so other unanticipated contamination can be contained. Furthermore, the design of future experiments of this type should also allow for rapid disassembly (< 5 minutes) and/or the use of long handled tools for use in the disassembly to reduce extremity dose.

7.3 MAINTENANCE OTHER THAN PREVENTIVE:

January System # Description Work Performed T/S and repair Fuel Temp 1 failure to reset after 5300 DAC scram test. Replaced 6 pole relay on Action Pak shelf for Fuel Temp 1 scram check relay.

Electrical Installed conduit, boxes, and wiring per FM-III-07-01.

5700 Distribution This completes the Facility Mod for X-Ray equipt. In Bay 4 5490 Helium Supply Replaced expended helium supply bottle 5640 HV-2 (Bay 2 staging Replaced HV-2 heater inducer motor and blower.

____________area) _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

5310 Control System Replaced jumper wire on power supply PS-I. See Console anomaly report.

February System # Description Work Performed 5750 Underwater Camera Adjusted focus meter, range 1 cm to infinity.

Repaired flat panel monitor power supply.

March System # Description Work Performed 5510 EF-3 (Pneumatic 5510______ Transfer System) Replaced Pre-filter and HEPA filter April Work Performed Change out expended He Supply bottle Replace intermittent operating Hubble 10 A 250 V receptacle twist lock plug on Rx CAM pump pigtail.

UCDIMNRC Annual Repod 2013 10

I . DAVIS MNRC* UCD/MNRC ANNUAL REPORT FOR 2013 System # Description Work Performed 5510 EF-3 Equipment Replaced 2 belts Room Ventilation 1001 Bay Continuous Air Replaced Argon channel detector. Performed Monitor (CAM) channel calibration.

1001 Reactor CAM Replace blower fuse holder June System # Description Work Performed 1001 Reactor Continuous Replace twist-lock power receptacle Air Monitor (CAM) 5490 Helium Supply Replace expended He supply bottle T/S and repair intermittent secondary flow 5130 Secondary flow indications. Removed, cleaned, inspected, indication regreased, reinstalled, and retested both secondary system flow transducers July System # Description Work Performed 5510 Pneumatic Transfer Install flow monitor hood 5490 Helium Supply Replace expended He supply bottle, repaired Bay 4 Helium poly-flo tubing leak Equipment Room 1030 Hand and Foot Replace damaged left foot detector tube monitor 5640 HV-1 (Bay 1 5640 Staging Area) Replace failed sump water pump and 15 amp fuse System # Description Work Performed Equipment Room 1030 Hand and Foot Replace "Right Hand" detector tube Monitor 5490 Helium Supply Replace expended He supply bottle 1001 Stack Continuous Replace power supply, installed new printer, source Air Monitor checked satisfactory UCD/MNRC Annual Report 2013 11

LfDAVIS MNRC* UCD/MNRC ANNUAL REPORT FOR 2013 September System # Description Work Performed AMUS storage Replace corroded pipe at the bottom of the south tanks tank 5330 NM-1000 Nuclear T/S and repair noisy signal. Replaced Hi voltage Instrument Detector bias supply.

5330 NM-1000 Nuclear C&I. Pulled digital NM-1000 boards, cleaned card Instrument edge connectors October System # Description Work Performed 1001 Reactor Continuous Air Monitor Replace reactor CAM CRT module R/S and repair NM-1000 response and failure on overlap with NPP-1 000. See Anomaly Report 5310 CSC Replace Test Push button switch on Control System Console.

November System # Description Work Performed 1020 Demineralizer Radiation Area Replaced with spare unit to correct inadvertent 1020_RadiatMonitor spiking. RAM calibrations sat.

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

2. Parametric values noted during testing are as follows:

Control Rod Worth:

Transient Shim 1: Shim 2: $2.59 Rod: $1.94 $2.72 Shim 3: Shim 4: Regulating

$2.66 $3.08 Rod: $2.85 Control Rod Scram Drop Times:

Transient Shim 1: Shim 2: 0.37 Rod: 0.47 0.39 sec sec sec Shim 3: Shim 4: Regulating 0.41 sec 0.39 Rod: 0.38 sec sec Shutdown Margin: $5.71 UCD4fNRC Annual Report 2013 12

t CDAVIS MNRC* UCD/MNRC ANNUAL REPORT FOR 2013 At Power Scram values: NPP-1000: 104% indicated, NM-1000: 104%

indicated.

A nuclear instrument calorimetric calibration was performed. Both the NPP channel and the NM-10000 channel of Nuclear Instruments were satisfactory, and no adjustments were required.

System # Description Work Performed 5120 Demineralizer Replace the 2 off service depleted resin bottles

___________ System ______________________

EF-3 (Equipment 5640 Room Ventilation) Replace belt on HV-3 5490 Helium Supply Replace expended He supply bottle 7.4 Training Januar x

1. Reactor Operator trainees attended six (6) sessions of Nuclear Physics and Reactor Theory training.

2. Operations and operator trainees attended multiple online sessions of Design and Operating Characteristics, Instrumentation, Electrical Systems, Administrative, and Procedure Changes training.

3. One person completed IATA training.

February

1. Reactor Operator trainees attended five (5) sessions of Nuclear Physics and Reactor Theory training.

2. Operations and operator trainees attended multiple online sessions of Design and Operating Characteristics, Instrumentation, Electrical Systems, Administrative, and Procedure Changes training

3. Six (6) personnel attended training on Detonator MSDS for handling HazClass 1.4 materials.

March

1. Reactor Operation trainees attended four (4) session of Reactor Physics training.

2. Operations and operator trainees attended multiple online sessions of Design and Operating Characteristics, Instrumentation, Electrical Systems, Administrative, and Procedure Changes training April

1. All facility personnel attended ALARA/Safety/Security training.

2. All Licensed Operators and trainees attended Reactor Pulse training.

3. Operations and operator trainees attended multiple online sessions of Design and Operating Characteristics, Instrumentation, Electrical Systems, Administrative, and Procedure Changes training.

4. One Senior Reactor Operator attended IATA Dangerous Goods shipping training.

5. Hosted and conducted training for University of California Berkeley Nuclear Engineering classes.

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tbAVIS MNRC~ UCD/MNRC ANNUAL REPORT FOR 2013

1. Operations and operator trainees attended multiple online sessions of Design and Operating Characteristics, Instrumentation, Electrical Systems, Administrative, and Procedure Changes training June

1. All licensed Senior Reactor Operators successfully completed and passed the Annual Operators Examination.

2. Operations trainees completed Argon 41 transfer to shipping containers training.

3. Operators and trainees completed ongoing computer based training sessions.

July

1. Senior Reactor Operators attended Radiation Safety Training for SROs.

2. Operators and trainees completed ongoing computer based training sessions.

1. MNRC provided training during the UCDavis NSSC summer program September

1. All licensed operators and trainees attended 6 sessions of computer based training for Technical Specification.

2. All licensed operators attended Operating Instructions Revision 12 training.

October

1. Reactor Operator trainees attended Emergency Room Response to Contaminated Victim. This training included first hand activities at the UCDavis Medical Center.

November

1. Senior Reactor Operators attended Security Maintenance Procedure Revision 5 training.

December

1. All MNRC personnel attended QSP (Quality System Procedure) Revision training.

2. MNRC conducted an all hands Annual Security Drill.

3. MNRC conducted an all hands Annual Facility Emergency Drill.

UCD/MNRC Annual Report 2013 14

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t (DAVIS MNRC* UCD/MNRC ANNUAL REPORT FOR 2013 Reactor Hours (2013)

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t ( AVIS MNRCAi UCD/MNRC ANNUAL REPORT FOR 2013 Reactor Tank Irradiation Facilities Total Number of Irradiations Completed (2013)

-- 4-- Pneumatic ý- Silicon Fixture Central Facility - Argon - Neutron Irradiator - 2013 Total -- 2012 Total ý I

JAN FEB MAR APR MAY JUN JUL AUG SEP OCT NOV DEC UCDWNRCAnnual Report 2013 18

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.3an Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec ImBay 1 331 211 157 81 1106 1117 1113 1133 147 212 16 3 I Bay 2 123 1 54 126 168 158 188 151 1 113 1 133 1 49 1 48 1 21 1 1 Bay 3 12 0 5 7 1 2 2 1 1 5 7 0 n Bay 4 0 2 0 6 2 2 3 12 1 5 0 0 Months UCDWMNRCAnulal Report 2013 19

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Li DAVIS MNRC McCLELLAN NUCLEAR RESEARCH CENTER UCD/MNRC ANNUAL REPORT FOR 2013 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 Liquid Effluents No liquid effluents were released during 2013.

8.2 Airborne Effluents Airborne radioactivity discharged during 2013 is tabulated in Table 1 below.

TABLE 1 2013

SUMMARY

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

Ar-41 UNRESTRICTED CONC. LIMIT FOR UNRESTRICTED DOSE IN RELEASED RELEASED AREA (1)(3) UNRESTRICTED AREA (1) CONSTRAINT PART. WITH AREA (1) FOR FORM HALF-LIFE UNRESTRICTED WITH > 8 DAYS AREA (1)(4) HALF-LIFE

>8 DAYS (Ci) (uCi/ml) (%) (mrem) (%) (Ci) (uCi/ml)

JAN 0.87 4.78E-1 1 0.5% 2.91 E-01 2.91% NONE NONE FEB 0.61 3.38E-1 1 0.3% 2.06E-01 2.06% NONE NONE MAR 0.94 5.16E-11 0.5% 3.14E-01 3.14% NONE NONE APR 1.27 6.99E-1 1 0.7% 4.25E-01 4.25% NONE NONE MAY 1.14 6.43E-1 1 0.6% 3.92E-01 3.92% NONE NONE JUN 1.06 5.94E-11 0.6% 3.62E-01 3.62% NONE NONE JUL 1.01 5.71 E-11 0.6% 3.48E-01 3.48% NONE NONE AUG 0.96 5.43E-1 1 0.5% 3.30E-01 3.30% NONE NONE SEP 1.07 6.01 E- 1 0.6% 3.66E-01 3.66% NONE NONE OCT 0.78 4.39E-1 1 0.4% 2.67E-01 2.67% NONE NONE NOV 0.85 4.77E-1 1 0.5% 2.90E-01 2.90% NONE NONE DEC 0.22 1.25E-1 1 0.1% 7.59E-02 0.76% NONE NONE TOT 10.79 6.02E-10 NONE NONE AVG 0.90 5.02E-11 0.5% 0.31 3.06%

(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)]

UCDIMNRC Annual Repod 2013 21

UCDAVIS MNRC McCLELLAN NUCLEAR RESEARCH CENTER UCD/MNRC ANNUAL REPORT FOR 2013 8.3 Solid Waste No waste shipments were made in 2013 9.0 Radiation Exposure Radiation exposure received by facility operations personnel, facility users, and visitors during 2013 is summarized in Table 2 below.

TABLE 2 2013

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 34.8 162 122 705 1

PERSONNEL" )

FACILITY 22 <1 <1 *

• USERS VISITORS 743 <1 2 * *

(1) Only five facility personnel actually received exposure.

• Extremity monitoring was not required.

UCDOIMNRCAnnual Repod 2013 22

LC DAVIS MNRC McCLELLAN NUCLEAR RESEARCH CENTER UCD/MNRC ANNUAL REPORT FOR 2013 10.0 Radiation Levels and Levels of Contamination Radiation levels and levels of contamination observed during routine surveys performed at the MNRC during 2013 are summarized in Table 3 below.

TABLE 3 2013

SUMMARY

OF RADIATION LEVELS AND CONTAMINATION LEVELS DURING ROUTINE SURVEYS AVERAGE HIGHEST AVERAGE HIGHEST (mrem/hr) (mrem/hr) (dpm/1OOcm 2) (dpm/lOOcm 2)

OFFICE SPACES <0.1 <0.1 <5000(l) <5000(l)

REACTOR CONTROL RM <0.1 <0.1 < 5000(l) <5000(l)

RADIOGRAPHY CONTROL RM <0.1 <0.1 < 5000(l) <5000(l)

COUNTING LAB <0.1 <0.1 < 5000(l) < 5000(l)

STAGING AREA <0.1 <0.1 < 5000(l) < 5000(l)

COMPOUND <0.1 <0.1 < 5000(1) <5000(l)

EQUIPMENT RM 1.0 116(4) <800(2) <800(2)

DEMINERALIZER AREA 22 440(4) <800(2) <800(2)

REACTOR RM 1.3 230(4) <800(2) <800(2)

SILICON STORAGE SHED <0.1 <0. 1 <5000(l) <5000(1)

RADIOGRAPHY BAYS 1.05(3 ) 630(3) (4) <800(2) <800(2)

(1) <5000 dpm/100 cm 2 = Less than the lower limit of detection for a scanning survey.

(2) <800 dpm/100 cm2 = Less than the lower limit of detection for a swipe survey.

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

(4) Contact readings UCDWMNRCAnnual Report 2013 23

LJCDAVIS MNRC MCCLELLAN NUCLEAR RESEARCH CENTER UCD/MNRC ANNUAL REPORT FOR 2013 11.0 Environmental Surveys Environmental surveys performed outside of the MNRC during 2013 are summarized in Tables 4 & 5 below. The environmental survey program is described in the MNRC Facility Safety Analysis Report.

TABLE 4 2013

SUMMARY

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

AVERAGE HIGHEST (mrem) (mrem)

ON BASE (OFF SITE 1-20 & 64) 6 15 ON SITE (SITES 50 - 61 & 65-71) 11 21 (1) Natural background assumed to be the off base (Sites 27-42) average of 27 mrem.

UCOWNRC Annual Report 2013 24

UCDAVIS MNRC McCLELLAN NUCLEAR RESEARCH CENTER UCD/MNRC ANNUAL REPORT FOR 2013 TABLE 5 2013

SUMMARY

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

AVERAGE <MDA 3.03 <MDA <MDA HIGHEST <MDA 3.71 <MDA <MDA MDA is the minimum detectable activity at the 95% confidence level.

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

MIN MAX Alpha 1.09 1.97 Beta 1.95 2.18 Tritium 326 366 Cs-137 4.29 7.21 UCDUMNRCAnnual Report 2013 25