ML17181A173

Univ. of California-Davis/McClellan - 2016 Annual Report

ML17181A173
Person / Time
Site:	University of California-Davis
Issue date:	12/31/2016
From:	McClellan Nuclear Research Center
To:	Office of Nuclear Reactor Regulation
Shared Package
ML17181A167	List: ML17181A171 ML17181A173 ML17181A174
References
Download: ML17181A173 (25)

Text

2016 ANNUAL REPORT Docket Number 50-607 License Number R-130

UCD/MNRCANNUALREPORTFOR20!ffj

1. Introduction The University of California , Davis, McClellan Nuclear Research Cen ter (MNRC) consists of a research reactor, associated radiography and positioning equipment, and a wide variety of equipment to support broad-based resear ch act i vities. Thi s MNRC Annual Report i s published each year in support of the license provided by the United States Nuclear Regulatory Commissi o n (NRC).

The aforementioned license is for the opera ti on of a steady-state TRIGA' reactor with pulsing and square wave capability.

It is the primary intent of this document to provide information relevant t o the safe operation of the UCD/MNRC. A brief description of the MNRC facility and administration is f ollowed by operat i o nal events and health physics information co n cerning this facility during CY 2016.

2. UCD/MNRC Facility Description The UCD/MNRC i s located on the McClellan Industrial Park site; the react or is housed in Building 258. The McClellan Industrial Park site is approximately 2600 acres , l ocated eight miles northeast o f Sacramento, Cal ifornia .

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 f or radiography and other research and commercial act i v iti es. All four bays are capab le of using radiography film techniques, but 3 normally uses electronic imaging devices. Space , sh ielding and environmenta l contro ls are provided by the enclosure for neutron radiography operations performed on a va ri ety o f samp les. Adequate room has been provided to handle the components in a safe manner.

In addition to the radiography bays, the UC D/MNRC reactor also has several in - core facil itie s ranging from a pneumati c 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 commi ssion (NRC) to operate under the provisions of operating li cense R-130.

The University of Ca liforn ia Regents have designated the Chancellor at UC Davis to be the license holder. The UCD Chance ll or has in-turn delegated the Vice Chancellor for Research to be the licensee of record.

The UCD / MNRC is under the d ire ction of the UCD/MNRC Director.

UCDIMNRC A nnual Rllf)Oft 2016 1

MNRC$ UCD/MNRC ANNUAL REPORT FOR 2016 4.0 Facility Modifications (Section 50 . 59 of 10CFR Part 50), and experiments .

None 5.0 Approved Changes to Experiments None 6.0 Licensing and Regulatory Activities 6.1 NRC Items

a. The Nuclear Regulatory Commission condu cted a semi -ann ual audit the week of 09 February 2016. No signif i cant f i nd i ngs r e p orted.

b . The Nuc l ear Regulatory Commission condu c t ed an a u dit the week of 29 Aug 2016 . No significant findings reported.

c . On 24 June 2016 the Nuclear Regulatory Commission requested the LAR submitted 15 July 2011 be withdrawn and incorporated or folded into the 2018 Relicensing package. The LAR has been withdrawn.

d. On June 2 , 2016 , relicensing packages were submitted to the NRC for 2 SRO license renewals . These have been completed and both SRO's are relicensed until 2022 .

6.2 Nu clear Safety Committee (UCD/NSC)

a. The Nuclear Safety Committee he l d its semi-annual meetings on 2 February and 12 August 2016.

b. The Nuclear Safety Committee performed an Operations audit for 2016 on 11 January 2017 .

c. The Nuclear Safety Committee performed an audit of the Radiation Safety Program on 25 and 28 October 2016.

d . The Nuclear Safety Committee performed a Secur i ty audit on 11 October 2016.

7.0 OPERATIONS OPERATING HISTORY :

TOTAL OPERATING HOURS THIS YEAR: 1028 . 08 TOTAL OPERATING HOURS: 50500.14 TOTAL MEGAWATT HOURS THIS YEAR : 942 . 74 TOTAL MEGAWATT HOURS: 65159.88 TOTAL NUMBER OF PULSES PERFORMED THI S YEAR : 0 TOTAL NUMBER OF PULSES PERFORMED: 484 UCD/MNRC Annual Report 2016 2

MNRC~ UCD/MNRC ANNUAL REPORT FOR 2016 7.1 UNSCHEDULED REACTOR SHUTDOWNS and NOTED PROBLEM AREAS:

In 2016 , there were four (4) unscheduled shutdowns at the MNRC reactor facility . The following is a list of the unscheduled shutdowns :

20 16 UNSCHEDULED REACTOR SHUTDOWNS Type of Failures Total Number csc 0 Other 4 TOTAL NUMBER OF UNSCHEDULED SHUTDOWNS IN 2016 4 Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec csc 0 0 0 0 0 0 0 0 0 0 0 0 Other 1 0 0 1 1 0 0 0 0 0 0 1 Notes 1 2 3 2 Notes :

1: Off Site Power spike /bump caused the reactor CAM to reboot .

2: Scram-Database Timeout 3 : Rx Room RAM pegged high . GM tube failure.

January

1. There was one unscheduled shutdown in the mo nth of Januar y.

a. Rx CAM Particulate Channel alarmed after power spike . Rx manually scrammed .

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

a . Transmit Trouble (Security System) , cleared on acknowledgement .

February

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 n o unsc hedul ed shutdowns in the month of Mar ch .

2. There were two cal lbacks to the facility in March .

a . UPS faults, both cleared on acknowledgement April

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

a . NM- 1000 , Database time o ut message cleared on ackn owledgment .

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

May

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

a . Reactor Room RAM pegged High momentari ly, See Anomaly report 2 . There were no callbacks to the facility in the month of May .

UCD/ MNRC Annual Report 2016 3

MNRC~ '(Qco/MNRC ANNUAL REPORT FOR 2016 June 1 . There were no unscheduled shutdowns in the month of June.

2 . Ther e were f our(4)ca llbacks t o the facility in the month of June .

a . Stack CAM Fault High Air Fl ow .

b. CSC Alarm , improper reset .

c. UPS fault-area wide power failure.

d . Stack CAM fault Low Flow Alarm

1. There were no unscheduled shutdowns in July .

2. There was o ne callback to the facility in the month of Ju l y .

a . Rod Withdrawal Prohibit a l ert . Cl eared on acknowledgement .

August

1. There were no unscheduled shutdowns in the month o f August .

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

a. Rod Withdrawal Prohibit alert. Cleared on acknowledgement .

September 1 . There were no unscheduled shutdowns i n the month o f September.

2. There were two callbacks to the facility in the month of September .

a. Rod Withdrawal Prohibit a l ert. Cl eared on acknowl edgement .

b . Window sensor (Security System) . Cause undetermined .

October

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

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

November

1. There were no unscheduled shutdowns in the month o f November.

2 . There were no callbacks to the facility in the month o f November.

December

1. There was one unscheduled shutdown in December.

a. Scram Database Timeout - See anomaly report.

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

a . Scram Database Timeout - See anomaly report .

UCD/MNRC Annual Report 2016 4

l :v1 MNRC$ UCD/MNRC ANNUAL REPORT FOR 2016

7.2 ANOMALIES

During 2016 , there were 3 reported anomalies at the MNRC facility and two Radiological Incident Investigations . The specifics are listed below :

1. There was one anomaly reported in the month of Apri l. The report is as follows:

Anomaly Report 4/21/2016 0800 Reactor Power Level - Shutdown performing Prestart Checklist NM-1000 Internal display failure .

During the performance of the Presta rt Checks for Reactor Startup, the NM-1000 cabinet display interface (the Burr-Brown terminal) was found to be not function ing. All of the prestart checklist items had been completed satisfactorily, but the NM-1000 Stack fault message could not be cleared from the CSC status monitor. Input commands to the terminal were not accepted and the LED display was non-functional.

Work Order 16-0266 was issued to troubleshoot and repair the display problem .

The Facilities Electronics Engineer began troubleshooting the problem and soon discovered that a component on a communications card that provides the link to the Burr-Brown terminal had failed .

(Basically a burned out resister had caused other components to fa il). See Work order 16-0266.

The communications card was repaired by the Electronics Engineer and the Burr-Brown terminal was replaced with a new identical one.

A complete visual inspection of the NM-1000 system was performed and no other obvious problems were identified .

After the repairs/inspection was completed, the NM-1000 was re-energized satisfactorily and all the constants were verified SAT. (None had changed). The Burr-Brown terminal display and functions checked out SAT.

The NM-1000 portions of the Presta rt Checklist were all performed SAT.

The Acting Director was briefed on the repa irs and status.

The Reactor Supervisor and Acting Director granted permission to startup the reactor.

UCDIMNRC Annual Report 2016 5

MNRC$ UCD/MNRC ANNUAL REPORT FOR 2016 What Actions were taken to correct this anomaly?

Communications card repaired and the interface terminal was replaced.

What corrective actions are needed to prevent this anomaly from re-occurring?

As components and equipment age, failures will occur. It is not possible to predict exactly which component will fail when. Proper troubleshooting and experienced and knowledgeable staff/technicians are the only way to mitigate these failures when and if they occur.

Note: The original vendor of this equipment (General Atomics-TRIGA group) long ago declared this and other vendor provided equipment obsolete and no longer supports its maintenance or repair. They also no longer carry or provide spare parts.

2. There was one anomaly reported in the month of May. The report is as follows:

Anomaly Report May 25, 2016 The Reactor was operating at 1 MW, with the startup just having been completed at 0920 hrs.

At 0940 on 25 May 2016 the Reactor Room RAM alarmed (Criticality Alarm/ Evacuation Horn sounded))

with indications pegged high.

The readings on the CSC Status monitor were 7.6 E6 and the RMS II module was pegged high at greater than 10,000 mr/hr.

The Reactor was scrammed.

No personnel were in the reactor room at the time of the alarm .

All other CAM and RAM readings were normal, with no alert or alarm conditions.

After a few seconds, the readings from the Reactor Room RAM returned to normal.

The facility evacuation per the Casualty Procedure Immediate Actions was terminated .

Actions to correct Anomaly:

Local radiation survey in the reactor room showed normal readings.

Indications are that this was an electrical spike or possibly a GM tube problem with the instrument.

UCD/MNRC Annual Report 2016 6

MNRC$ UCD/MNRC ANNUAL REPORT FOR 2016 The Reactor Room RAM modules were replaced with the calibrated spare assemblies and source checked SAT.

After replacing the Reactor Room RAM modules all readings were normal with no spikes and stable.

The Radiation Safety Officer and the Reactor Supervisor granted permission to restart the reactor.

3. There was one anomaly reported in the month of December. The report is as follows:

Anomaly Report 5 December 2016 The reactor was started up at 1522 hours0.0176 days <br />0.423 hours <br />0.00252 weeks <br />5.79121e-4 months <br /> and 50% power {lMW) achieved at 1532 hours0.0177 days <br />0.426 hours <br />0.00253 weeks <br />5.82926e-4 months <br />.

At 1542 hours0.0178 days <br />0.428 hours <br />0.00255 weeks <br />5.86731e-4 months <br /> the reactor automatically scrammed with the "Scram-Database Timeout" message displayed on the Control System Console (CSC) status and HiRes monitors.

No other messages were displayed.

The CSC and Data Acquisition Cabinet (DAC) computers were rebooted. All indications were normal. The Reactor Supervisor was notified and concurred with the Senior Reactor Operator that the reactor could be restarted . Permission was grant ed to restart the reactor.

On 6 December 2016 at 0400 hours0.00463 days <br />0.111 hours <br />6.613757e-4 weeks <br />1.522e-4 months <br /> (approximately 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> later) and with the reactor shutdown, the UCD dispatchers contacted the duty SRO and notified him of a console alarm (i.e . a Callback). Upon arriving at the facility, the SRO observed that the CSC status and Hi Res monitors again displaying the "Scram-Database Timeout" message. The SRO again rebooted both the CSC and DAC computers and also inspected the NM-1000 display. After rebooting, all indications were normal.

Further investigation revealed no obvious failure or fau lt that directly results in this particular error message and automatic scram action to occur. The Facilities Electronics Engineer (also a qualified SRO) believes that there might be an issue with one of the CSC or DAC computers dynamic RAM components.

Reactor Prestart checks and NM-1000 diagnostics do not show any issues.

4. There was one Radiological Investigation Report written in February. That report is as follows:

RADIOLOGICAL INVESTIGATION REPORT NO. 16-01 TITLE: Lost Dosimeter in High Radiation Area DATE/TIME OF OCCURANCE : February 5th 2016 at "'10:00 am DESCRIPTION: An employee was performing routine work in the demineralizer area in the equipment room, which is classified as high radiation area. It is estimated that around 10:00 am the employee's UCD/ MNRC Annual R-rt 2016 7

MNRC$ UCD/MNRCANNUALREPORTFOR201:,j OSL badge came off and landed under a segment of the primary piping in the demineralizer area . The employee noticed his badge was missing at 2:30 pm at which time he was able to quickly locate it.

During the N4.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> the employee was not wearing his OSL badge no work was performed that would have resulted in any measureable exposure as indicated by their pocket ion chamber. The employee took an exposure reading at the location where the OSL badge had been and found it to be NlO mrem/hr. It is therefore likely that the badge received N45 mrem of dose that the employee did not.

DOSE CONSEQUENCES: No additional dose was received due to the misplacing of the dosimeter. Based on known radiation levels in the demineralizer area and the amount of time the worker spent in the area the dose the worker received was <1 mrem . This was confirmed by the pocket ion chamber reading. The effected dosimeter was worn for 4 days before this incident. No work by the employee took place during this time that would have incurred more than 1-2 mrem. The spare dosimeter issued to the worker will therefore only differ from the dose the worker received by, at most, 1-2 mrem . This is not considered statistically significant.

IMMEDIATE CORRECTIVE ACTION: The employee recorded their dose received for that day as measured by their pocket ion chamber. This dose was< 1 mrem . The effected dosimeter was taken and a spare dosimeter was issued to the employee .

PERMANENT CORRECTIVE ACTION: The frequency at MNRC when a dosimeter is misplaced in a high radiation area is very low (i.e. much less than once per year) . Furthermore, the frequency when an employee is performing work, which would incur a significant dose, when they are not wearing their OSL/TLD dosimeter, is essentially zero . This incident does not appear to be indicative of a larger issue and no permanent corrective action, beyond reminding MNRC radiation workers to periodically check to see that the ir dosimetry is in place while in a high radiation area, is required.

5. There was one Radiological Investigation Report written in June. That report is as follows :

RADIOLOGICAL INVESTIGATION REPORT NO. 16-02 TITLE: Uncontrolled decompression of ArAr dating sample (IR-0513)

DATE/TIME OF OCCURANCE: June 29th 2016 at N13:30 hrs (reactor shutdown)

DESCRIPTION: IR-0513 is an ArAr dating experiment that was irradiated in the central facility for N40 MWhrs before it was removed and allowed to "cool" in the reactor tank for N3 weeks. The experiment encapsulation is comprised of a reusable inner and outer aluminum cyl inder. The seal on both cylinders is opened by impacting the top of the seal with a dead-blow hammer. This encapsulation had been used successfully once before for a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> irradiation. The previous designed used a disposable aluminum cyl inder sealed by an interference fit. Two workers were involved in dismantling the experiment in the UCD/ MNRC Annual RtJPOrl 2016 8

~CD/MNRC ANNUAL REPORT FOR 2016 equipment room. The outer containment was opened without incident. No moisture was found between the two containments. When the seal on the outer container was unseated the contents rapidly decompressed due to an unexpected gas build up. The cap of the inner encapsulation and some of the aluminum foil (used to pack the samples) was ejected 3-4 feet from the worker opening the encapsulation . The packing aluminum foil appeared to have become heavily oxidized by this point.

CAUSE : The cause for the gas buildup is unknown and will likely remain unknown as there is some danger associated with trying to recreate the exact scenario. The cause is thought to be that the protective aluminum oxide layer, which forms on all aluminum exposed to oxygen, became damaged .

Once the metallic aluminum became exposed, moisture in the air sealed inside the sample reacted with the aluminum and generated hydrogen gas. The mechanism for exposing the metallic aluminum could have been radiolytic in nature or been the result of residual corrosive material on the samples. The researcher was contacted and stated that the sample was prepared in an identical manner as the previous samples. It is unclear why this gas buildup was seen in this specific irradiation and not the other ~10 similar ArAr dating experiments.

DOSE CONSEQUENCES: One of the workers received 5 mrem whole body and the second worker received 2 mrem whole body. This does is typical of the doses received while dismantling previous ArAr experiments. Therefore, no measurable external dose from this occurrence was received by either employee. Given that both workers found no contamination (other than on their gloves) on themselves immediately after the occurrence or after decontaminating the equipment room, the likelihood of uptake of rad iological material is small.

IMMEDIATE CORRECTIVE ACTION : The two workers restricted access to the area of potential contamination . All material ejected from the experiment containment was collected and segregated as radioactive material. Standard decontamination procedures were implemented . Decontamination took approximately 1.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> and was followed by a survey that found no measureable contamination in the area .

PERMANENT CORRECTIVE ACTION : Unless the exact cause of the gas buildup can be determined all future similar experiments shall be sealed in a moisture free environment and shall be opened "semi-remotely" in a radiological fume hood. This restriction includes experiments containing cadmium.

UCDIMNRC Annual R~rt 2016 9

UCD/MNRC ANNUAL REPORT FOR 2016 7.3 MAINTENANCE OTHER THAN PREVENTIVE :

January System# Description Work Performed Replaced Scram Check Relays K1, K3, and K4 on Data Acquisit ion 5320 the Action Pak drawer and K 1 relay on the DC and Control (DAC) input/output drawer in the DAC February System# Description Work Performed 1001 Reactor CAM Replaced failed Rx CAM monitor March System# Description Work Performed 1800 Reactor Ventilation DOP test Reactor Room Exhaust HEPA filters 1803 Rad-Vac DOP test Radiological Vacuum Cleaner 5490 Helium Supply Replace expended Helium Supply bottle 5720 Security System Replace Keypad at East Gate System# Description Work Performed Troubleshot and Repaired interface problem with Nuclear the NM- 1000. Component failures on 5330 Instrumentation communications card to the Burr-Brown terminal.

See anomaly report.

System# Description Work Performed 5490 Helium Supply Replaced expended helium supply bottle Radiation Area Replaced failed Reactor Room RAM system with 5710 Monitoring (RAM) calibrated spare modules.

UCD/MNRC Annual R.,,alf 2016 10

UCD/MNRC ANNUAL REPORT FOR 2016 June System# Description Work Performed Radiation Area Replaced failed Spare (ex Reactor Room) RAM GM 5710 Monitoring (RAM) tube recalibrated SAT.

Fire Protection 5740 Replaced failed Air Compressor System System# Description Work Performed 5490 Helium Supply Replaced expended helium supply bottle August

1. MNRC completed the annual reactor maintenance shutdown during the month of August. 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 Rod: $1.94 Shim 1: $2.66 Shim 2: $2.60 Shim 3: $2.68 Shim 4: $2.98 Regulating Rod: $2. 76 Control Rod Scram Drop Times:

Transient Rod: 0.34 sec Shim 1: 0.39 sec Shim 2: 0.37 sec Shim 3: 0.41 sec Shim 4: 0.39 sec Regulating Rod: 0.36 sec Shutdown Margin: $6.00 The normal nuclear instrument calorimetric calibration was performed. Both the NPP channel and the NM-1000 channels of the Nuclear Instruments were satisfactory, and no adjustments were required.

At Power Scram values: NPP-1000: 108% indicated, NM-1000: 104% indicated.

System# Description Work Performed Reactor Room 1001 Troubleshot and repaired Rx Rm CAM CRT failure.

CAM Makeup Water 5110 Replaced Makeup Water tank outlet resin bottle.

System Auxiliary Makeup 5170 Replaced propane gas line.

Water System UCD/MNRC Annual Report 2016 11

MNRC$ UCD/MNRC ANNUAL REPORT FOR 2016 September System# Description Work Performed 5490 Helium Supply Replaced expended helium supply bottle Auxiliary Makeup 5170 Replaced Depleted Resin bottles Water System October System# Description Work Performed 5490 Helium Supply Replaced expended helium supply bottle November System# Description Work Performed 5490 Helium Supply Replaced expended helium supply bottle December System# Description Work Performed Emergency Replaced 2 emergency lights and replaced 5350 Lighting batteries in 1 other.

7.4 Training January

1. Three Senio r Reactor Opera t o r s comp l eted tra i ning o n Norma l, Abnormal , and Emergency Procedures .

2 . Three Senior Reactor Operators completed training on Administrative Controls Procedures and Reg u lations

3. One Senior Reactor Operator completed training on seve r al Nuclear Theory modules .

February 1 . One Senior Reactor Ope r ato r completed trai ni ng on No rma l, Abn ormal ,

and Emergency Procedures.

2 . One Senior Reactor Operator comp l eted train i ng on several Nuclear Theory modules.

3 . One Senior Reactor Operators completed training on Admi nist ra tive Controls Procedures and Regulations UCD/ MNRC Annual Report 2016 12

~1 MNRC* UCD/MNRC ANNUAL REPORT FOR 2016 March

1. No scheduled training for March .

1 . Hosted and conducted training for University of California Berkeley Nuclear Engineering classes . (Classroom and Practical Lab t r a i ning) 2 . All Senior Reactor Operators satisfactorily completed the Bi ennial Requalification Exam.

1 . All Facility personnel completed Annual ALARA and annual sa f ety tra i ning .

June

1. No scheduled training in June .

1 . MNRC conducted summe r school classes for the University COSMOS program .

2 . Senior Reactor Operators completed training on Fuel and Fuel handli ng August

1. All licensed s u ccess f ully completed t h e An n u a l Operato r s Examination .

September

1. No scheduled training for September .

October 1 . Two Senior Reactor Operators completed training on Normal , Abnormal and Emergency Procedures .

November 1 . Two Senior Reactor Operators completed training on Normal , Abnormal and Emergency Procedures .

December

1. Senior Reactor Operators participated in the annual Security Drill .

UCD/ MNRC Annual Report 2016 13

MNRC$ UCD/MNRC ANNUAL REPORT FOR 2016 Cl Operating Hours 4500 4000 3500 3000 - ~

2500 - - '-- -

2000 '-- '-- - - ~

1500 ~ ~

1000 I 1-1-1 '-- '-- - -

-I f- ~ ~ - - ~ - - -

l 1 1- r 500 - - - - - - - - - - - - - - - - - - - - - -----<

0 I I I I I I I I I I UCDIMNRC Annwl R - 2016 14

MNRC~

!Ot<<tll.>>t "-~~ 'l!:!!L~ ~-<:t,Vll.!( UCD/MNRC ANNUAL REPORT FOR 2016 Unscheduled Reactor Shutdowns 2016 5

0 - Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec ocsc 0 0 0 0 0 0 0 0 0 0 0 0

• Other 1 0 0 1 1 0 0 0 0 0 0 1 0 2016 Total 1 1 1 2 3 3 3 3 3 3 3 4 02015 Total 0 0 1 2 2 2 2 2 2 3 3 3 Months UCDIMNRC Annual Report 2016 15

MNRC$ UCD/MNRC ANNUAL REPORT FOR 2016 Reactor Hours (2016)

Reactor Hours 2016 120 IJl

J 0 100 J:

~

ti) 3:

ti)

O'I QJ

E 80 "O

c ti)

O'I c

p 60 ti)

QJ a.

0 1!:-

.i:::.

40 c

0

E 20 0

Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec

• 2016 Op-Hrs 67.49 92.15 82.03 126.83 87 .87 84 85.78 77.2 64.04 104.54 92.64 63.51

• 2016 Mw-Hrs 61.7 84.4 74.44 122.44 82.86 80.73 83 57.47 61.09 99.78 88.08 46 .75

• 2015 Op-Hrs 84.98 77.8 84 .94 69.25 61.7 102.2 99.51 88.52 90.5 121.85 80.53 93.95

• 2015 Mw-Hrs 81.33 71.66 79.47 65.99 56.31 98 .3 89.62 63.39 85.58 112.12 77.45 80.48 UCD\NJNRC Annual Report 2016 16

MDANRC~

"-0.tll.,l,,tl ....~>>It f0:5L..\~'t<<"l l l.'fll" UCD/MNRC ANNUAL REPORT FOR 2016 Reactor Tank Irradiation Facilities 2016 29 28 27 26 25 24 23 22 21 20 19 18 17 16 15 14 13 12 11 10 9

8 7

6 5

4 3

I I 2

1 0

I I l.J f- ~

Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec a Pneumatic 13 11 1 2 12 2 4 0 0 1 0 4

• Silicon Fixture 0 0 2 1 1 1 0 2 0 2 0 1 o Central Facility 1 0 0 1 0 1 0 1 1 1 0 2 D Argon 0 0 1 0 0 0 0 0 0 0 0 0

• Neutron Irradlator 3 8 5 2 1 0 0 0 0 6 3 27 0

Month*

UCDIMNRC AnlwNI R - 2016 17

MNRC$ UCD/MNRC ANNUAL REPORT FOR 2016 Bay Utilization (Shutter Operations) 2016 180 160 -

Ill c 140 0 -

ftl

aftl 120 11-1

....0 100 QI

.D E

80 -

- I--- - I---

s _ ,..

z 60 - - ~ I--- - .* I---

40 - - - - - I---

- 1--- - 1--- 1---

20 - - '

i

- -- ~ I---

I--- 1---

0 ...

Jan Feb Mar n 1 Apr May Jun

~

Jul Aug Sep 11 Oct Nov 1---

Dec eBay 1 119 138 100 157 78 45 101 45 49 63 84 96

• Bay 2 27 86 66 144 41 108 86 57 54 118 111 51 DBay 3 0 0 0 10 3 2 1 0 0 0 0 0 DBay 4 0 0 8 0 25 0 1 0 4 0 0 0 Months UCO\MNRC Annual Report 20 16 18

MNRC~ UCD/MNRC ANNUAL REPORT FOR 201.6 Bay Irradiation Requests Completed 2016 75 so - -

.l:

e

~

25 ~ '--- i----

- i----

'--- i----

z j

,, l

~ '*! ,

c I

~ , '

-~

,*i

• 1 ll i

0 ~ .....

' ~ r-r-i ~

~

Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec a Bay 1 68 66 42 71 44 27 61 35 35 43 52 52

• Bay 2 16 51 37 49 18 70 37 41 40 42 39 27 eBay 3 0 0 0 0 1 1 0 0 0 0 0 0 DBay 4 0 0 1 0 1 0 0 0 0 0 0 0 Month*

UCD\MNRC Annual Report 2 0 16 19

MNRC$

McCLELLAN NUCLEAR RESEARCH CENTER UCD/MNRC ANNUAL /iEPORT FOR 2016' 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 2016.

8.2 Airborne Effluents Airborne radioactivity discharged during 2016 is tabulated in Table 1 below.

TABLE 1 2016

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 1 3 AREA < >< > UNRESTRICTED CONSTRAINT PART. WITH AREA <1 >

AREA Cll FOR FORM HALF-LIFE UNRESTRICTED WITH > 8 DAYS AREA <1 H4 l HALF-LIFE

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

JAN 0.70 3.91 E-11 0.4% 2.38E-01 2.38% NONE NONE FEB 1.06 5.91 E-11 0.6% 3.60E-01 3.60% NONE NONE MAR 3.93 2.19E-10 2.2% 1.33E+OO 13.35% NONE NONE APR 1.64 9.13E-11 0.9% 5.56E-01 5.56% NONE NONE MAY 0.89 4.96E-11 0.5% 3.02E-01 3.02% NONE NONE JUN 1.91 1.09E-10 1.1% 6.64E-01 6.64% NONE NONE JUL 1.79 1.03E-10 1.0% 6.25E-01 6.25% NONE NONE AUG 1.20 6.86E-11 0.7% 4.18E-01 4.18% NONE NONE SEP 1.14 6.50E-11 0.7% 3.96E-01 3.96% NONE NONE OCT 1.97 1.13E-10 1.1% 6.87E-01 6.87% NONE NONE NOV 2.06 1.18E-10 1.2% 7.18E-01 7.18% NONE NONE DEC 0.98 5.61 E-11 0.6% 3.41 E-01 3.41% NONE NONE TOT 19.27 NONE NONE AVG 1.61 9.09 E-11 0.9% 0.55 5.53%

(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 lE-8 (Appendix B, Table 2);

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

UCD\MNRC Annu# Report 2016 20

MNRC$

McCLELLAN NUCLEAR RESEARCH CENTER 0

UCD/MNRC ANNUAL REPORT FOR 2016]

8.3 Solid Waste No solid radioactive waste was shipped this year.

9.0 Radiation Exposure Radiation exposure received by facility operations personnel, facility users, and visitors during 2016 is summarized in Table 2 below.

TABLE 2 2016

SUMMARY

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

FACILITY 7 55 120 111 398 PERSONNEL< 1 >

FACILITY USERS 16 <1.0 1 *

• VISITORS 648 <1.0 2 * *

(1) Only 5 of the 7 facility radiation workers were employed at MNRC after January 2016.

• Extremity monitoring was not required.

UCDIMNRC Annual Report 20 76 21

MNRC$

McCLELLAN NUCLEAR RESEARCH CENTER UCD/MNRC ANNUAL REPORT FOR 2016 10.0 Radiation Levels and Levels of Contamination Radiation levels and levels of contamination observed during routine surveys performed at the MNRC during 2016 are summarized in Table 3 below.

TABLE 3 2016

SUMMARY

OF RADIATION LEVELS AND CONTAMINATION LEVELS DURING ROUTINE SURVEYS AVERAGE HIGHEST AVERAGE HIGHEST (mrem/hr) (mrem/hr) ( dpm/ 100cm 2 ) ( dpm/ 100cm 2 )

OFFICE SPACES <0.1 <0.1 <5000< 1 > <5000< 1 >

REACTOR CONTROL RM <0.1 <0.1 <5000< 1 > <5000< 1 >

RADIOGRAPHY CONTROL RM <0.1 <0.1 <5000< 1 > <5000< 1 >

COUNTING LAB <0.1 <0.1 <5000< 1 > <5000< 1 >

STAGING AREA <0.1 <0.1 <5000< 1 > <5000< 1 >

COMPOUND (I/S Fence) <0.1 <0.1 <5000< 1 > <5000< 1 >

EQUIPMENT RM o.5C4 l 108(5 ) <800< 2 > <800< 2 >

DEMINERALIZER AREA 12.5C4 l 320C5 l <800< 2 > <800< 2 >

REACTOR RM 2.1 C4 l 2000C5 l <800< 2 > <800< 2 >

SILICON STORAGE SHED <0.1 <0.1 <5000< 1 > <5000< 1 >

RADIOGRAPHY BAYS 0.6<3 l 440( 6 ) <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 cm 2 = 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) General area dose rate.

(5) Maximum contact dose rate.

(6) 1 meter dose rate of beam port insert taken behind shielding.

UCDIMNRC Annual R.,xJrt 2016 22

MNRC$

McCLELLAN NUCLEAR RESEARCH CENTER UCD/MNRCANNUALREPORTFOR2016 11.0 Environmental Surveys Environmental surveys performed outside of the MNRC during 2016 are summarized in Tables 4 & 5 below. The environmental survey program is described in the MNRC Facility Safety Analysis Report.

TABLE 4 2016

SUMMARY

OF ENVIRONMENTAL TLD RESULTS (WITH NATURAL BACKGROUN0< 1 > SUBTRACTED)

AVERAGE HIGHEST (mrem) (mrem)

ON BASE (OFF SITE 1-20 & 64) 6 13 ON SITE (SITES 50 - 61 & 65- 71) 14 22 (1) Natural background assumed to be the off base (Sites 27-42) average of 29 mrem.

UCDWNRC Annual Report 2016 23

MNRC$

McCLELLAN NUCLEAR RESEARCH CENTER

'fQ.c o/MNRC ANNUAL REPORT FOR 2016 TABLE 5 2016

SUMMARY

OF RADIOACTIVITY IN WELL WATER ALPHA BETA TRITIUM Cs-137

{pCi/I) {pCi/I) {pCi/I) {pCi/I)

AVERAGE <MDA 2.77 <MDA <MDA HIGHEST <MDA 3.44 <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 1.25 1.90 Beta 1.36 1.92 Tritium 294 354 Cs-137 5.90 15.4 UCD\MNRC Annual Raport 2016 24