Text

Examination Report No. 50-326/OL-13-01, University of California - Irvine
	ML13088A150
Person / Time
Site:	University of California - Irvine
Issue date:	04/05/2013
From:	Gregory Bowman; Research and Test Reactors Branch B
To:	Geoffrey Miller; University of California - Irvine
	Nguyen, J
Shared Package
ML11327A043	List: ML12145A109; ML12145A114; ML13088A150; ML13088A215;
References
	50-326/OL-13-01
	Download: ML13088A150 (40)
	v • d • e

April 5, 2013 Dr. George E. Miller Department of Chemistry 516 Physical Sciences 1 University of California, Irvine Irvine, CA 92697-2025

SUBJECT:

EXAMINATION REPORT NO. 50-326/OL-13-01, UNIVERSITY OF CALIFORNIA - IRVINE

Dear Dr. Miller:

During the week of March 11, 2013, the U.S. Nuclear Regulatory Commission (NRC) administered operator licensing examinations at your University of California - Irvine TRIGA reactor. The examinations were conducted in accordance with NUREG-1478, Operator Licensing Examiner Standards for Research and Test Reactors, Revision 2. Examination questions and preliminary findings were discussed at the conclusion of the examination with those members of your staff identified in the enclosed report.

In accordance with Section 2.390 of Title 10 of the Code of Federal Regulations, a copy of this letter and the enclosures will be available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records component of NRCs Agencywide Documents Access and Management System (ADAMS). ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).

The NRC is forwarding the individual grades to you in a separate letter which will not be released publicly. If you have any questions concerning this examination, please contact Mr.

John T. Nguyen at (301) 415-4007 or via e-mail John.Nguyen@nrc.gov.

Sincerely,

/RA/

Gregory T. Bowman, Chief Research and Test Reactors Oversight Branch Division of Policy and Rulemaking Office of Nuclear Reactor Regulation Docket No. 50-326

Enclosures:

1. Examination Report No. 50-326/OL-13-01

2. Written Examamination cc: w/o enclosures: See next page

April 5, 2013 Dr. George E. Miller Department of Chemistry 516 Physical Sciences 1 University of California, Irvine Irvine, CA 92697-2025

SUBJECT:

EXAMINATION REPORT NO. 50-326/OL-13-01, UNIVERSITY OF CALIFORNIA - IRVINE

Dear Dr. Miller:

During the week of March 11, 2013, the U.S. Nuclear Regulatory Commission (NRC) administered operator licensing examinations at your University of California - Irvine TRIGA reactor. The examinations were conducted in accordance with NUREG-1478, Operator Licensing Examiner Standards for Research and Test Reactors, Revision 2. Examination questions and preliminary findings were discussed at the conclusion of the examination with those members of your staff identified in the enclosed report.

In accordance with Section 2.390 of Title 10 of the Code of Federal Regulations, a copy of this letter and the enclosures will be available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records component of NRCs Agencywide Documents Access and Management System (ADAMS). ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).

The NRC is forwarding the individual grades to you in a separate letter which will not be released publicly. If you have any questions concerning this examination, please contact Mr.

John T. Nguyen at (301) 415-4007 or via e-mail John.Nguyen@nrc.gov.

Sincerely,

/RA/

Gregory T. Bowman, Chief Research and Test Reactors Oversight Branch Division of Policy and Rulemaking Office of Nuclear Reactor Regulation Docket No. 50-326

Enclosures:

1. Examination Report No. 50-326/OL-13-01

2. Written Examination cc: w/o enclosures: See next page DISTRIBUTION:

PUBLIC RidsNrrDprPrta RidsNrrDprPrtb Facility File (CRevelle) O-07 F-08 ADAMS ACCESSION #: ML13088A150 TEMPLATE #: NRR-079 Office PROB/CE IOLB/OLA PROB/BC Name JNguyen CRevelle GBowman Date 3/26/13 4/03/13 4/05/103 OFFICIAL RECORD COPY

University of California at Irvine Docket No. 50-326 cc:

Dr. Scott Rychnovsky, Chair Department of Chemistry University of California, Irvine Irvine, CA 92697-2025 Radiological Health Branch State Department of Health Services P.O. Box 9442732 Sacramento, CA 94234-7320 Test, Research, and Training Reactor Newsletter University of Florida 202 Nuclear Sciences Center Gainesville, FL 32611

EXAMINATION REPORT NO: 50-326/OL-13-01 FACILITY: UNIVERSITY OF CALIFORNIA - IRVINE FACILITY DOCKET NO.: 50-326 FACILITY LICENSE NO.: R-116 SUBMITTED BY: ______________/RA/______________ 4/02/2013 John T. Nguyen, Chief Examiner Date

SUMMARY

During the week of March 11, 2013, the NRC administered operator licensing examinations to five license candidates including four Reactor Operator (RO) and one Senior Reactor Operator -

Upgrade (SRO-U) license candidates. One RO candidate failed Section B of the written examination and one SRO-U failed the operating test. All the other candidates passed all portions of the examinations.

REPORT DETAILS

1. Examiner: John T. Nguyen, Chief Examiner

2. Results:

RO PASS/FAIL SRO PASS/FAIL TOTAL PASS/FAIL Written 3/1 0/0 3/1 Operating Tests 4/0 0/1 4/1 Overall 3/1 0/1 3/2

3. Exit Meeting:

George Miller, UCINRF, Reactor Supervisor Jonathan T. Wallick, UCINRF, Senior Reactor Operator John Nguyen, NRC, Chief Examiner Taylor Lichatz, NRC, Examiner in Training The NRC Examiner thanked the facility for their support in the administration of the examinations. The examiner discussed with the Reactor Supervisor regarding the training program, updating of the procedures, and the generic weaknesses observed during their operating tests. The facility licensee had no comments on the written examination.

Enclosure 1

U. S. NUCLEAR REGULATORY COMMISSION RESEARCH AND TEST REACTOR OPERATOR LICENSING EXAMINATION FACILITY: UNIVERSITY OF CALIFORNIA - IRVINE REACTOR TYPE: TRIGA DATE ADMINISTERED: 03/12/2013 CANDIDATE:

INSTRUCTIONS TO CANDIDATE:

Answers are to be written on the answer sheets provided. Points for each question are indicated in brackets for each question. You must score 70% in each section to pass. Examinations will be picked up three (3) hours after the examination starts.

% of Category % of Candidates Category Value Total Score Value Category 18.00 33.33 A. Reactor Theory, Thermodynamics and Facility Operating Characteristics 18.00 33.33 B. Normal and Emergency Operating Procedures and Radiological Controls 18.00 33.33 C. Plant and Radiation Monitoring Systems 54.00 FINAL GRADE

% TOTALS All work done on this examination is my own. I have neither given nor received aid.

Candidate's Signature Enclosure 2

NRC RULES AND GUIDELINES FOR LICENSE EXAMINATIONS During the administration of this examination the following rules apply:

1. Cheating on the examination means an automatic denial of your application and could result in more severe penalties.

2. After the examination has been completed, you must sign the statement on the cover sheet indicating that the work is your own and you have neither received nor given assistance in completing the examination. This must be done after you complete the examination.

3. Restroom trips are to be limited and only one candidate at a time may leave. You must avoid all contacts with anyone outside the examination room to avoid even the appearance or possibility of cheating.

4. Use black ink or dark pencil only to facilitate legible reproductions.

5. Print your name in the blank provided in the upper right-hand corner of the examination cover sheet and each answer sheet.

6. The point value for each question is indicated in [brackets] after the question.

7. If the intent of a question is unclear, ask questions of the examiner only.

8. To pass the examination you must achieve a grade of 70 percent or greater in each category.

9. There is a time limit of three (3) hours for completion of the examination.

10. When you have completed and turned in you examination, leave the examination area

EQUATION SHEET

Q = m c p T = m H = UA T (- )

2 P max = * -4

= 1 x 10 seconds 2 (k)

S CR 1 (1 - K eff 1 ) = CR 2 (1 - K eff 2 )

SCR =

1 - K eff eff = 0.1 sec-1 eff SUR = 26.06 1 - K eff 0 1 CR1

- M= M= =

1 - K eff 1 1 - K eff CR 2 P = P0 10 SUR(t) P = P0 e t

(1 - )

P= P0 (1 - K eff ) * -

SDM = = =

+

K eff -

eff K eff 2 - K eff 1 0.693 ( K eff - 1)

T=

k eff 1 x K eff 2 K eff 6CiE(n) 2 DR1 d 1 = DR 2 d 2 2

DR = DR0 e - t DR = 2 R

2

( 2 - )2 ( 1 - )

=

Peak 2 Peak 1 1 Curie = 3.7 x 1010 dis/sec 1 kg = 2.21 lbm 1 Horsepower = 2.54 x 103 BTU/hr 1 Mw = 3.41 x 106 BTU/hr

1 BTU = 778 ft-lbf EF = 9/5 EC + 32 1 gal (H2O) . 8 lbm EC = 5/9 (EF - 32)

Section A L Theory, Thermo, and Facility Characteristics ANSWER SHEET Multiple Choice (Circle or X your choice)

If you change your answer, write your selection in the blank.

A001 a b c d __

A002 a b c d __

A003 a b c d __

A004 a b c d __

A005 a b c d __

A006 a b c d __

A007 a __ b __ c __ d __ (0.25 each)

A008 a b c d __

A009 a b c d __

A010 a b c d __

A011 a __ b __ c __ d __ (0.25 each)

A012 a b c d __

A013 a b c d __

A014 a b c d __

A015 a b c d __

A016 a b c d __

A017 a b c d __

A018 a b c d __

Section B Normal/Emerg. Procedures & Rad Con ANSWER SHEET Multiple Choice (Circle or X your choice)

If you change your answer, write your selection in the blank.

B001 a b c d __

B002 a b c d __

B003 a b c d __

B004 a b c d __

B005 a b c d __

B006 a b c d __

B007 a b c d __

B008 a b c d __

B009 a b c d __

B010 a b c d __

B011 a b c d __

B012 a b c d __

B013 a b c d __

B014 a b c d __

B015 a __ b __ c __ d __ (0.25 each)

B016 a b c d __

B017 a b c d __

B018 a b c d __

Section C Facility and Radiation Monitoring Systems ANSWER SHEET Multiple Choice (Circle or X your choice)

If you change your answer, write your selection in the blank.

C001 a b c d __

C002 a b c d __

C003 a b c d __

C004 a b c d __

C005 a b c d __

C006 a b c d __

C007 a __ b __ c __ d __ (0.25 each)

C008 a b c d __

C009 a b c d __

C010 a b c d __

C011 a __ b __ c __ d __ (0.25 each)

C012 a b c d __

C013 a b c d __

C014 a b c d __

C015 a b c d __

C016 a b c d __

C017 a b c d __

C018 a b c d __

- - - - END OF EXAMINATION *****

Section A L Theory, Thermo, and Facility Characteristics QUESTION A.1 [1.0 point]

The reactor is critical at 5 watts. Which ONE of the following correctly describes the reactor behavior when a reactivity worth of 0.02 delta K/K is IMMEDIATELY inserted to the reactor core?

a. Subcritical

b. Critical

c. Supercritical

d. Prompt critical QUESTION A.2 [1.0 point]

Given the following Core Reactivity Data during startup:

Control Total Rod Worth Rod Worth removed at 5 Rod excess at 5 watts Rod ($) watts critical ($) critical ($)

Rod #1 2.50 2.50 0.00 Rod # 2 2.00 1.50 0.50 Rod # 3 2.20 2.00 0.20 Rod # 4 3.50 2.50 1.00 Total Worth 10.20 8.50 1.70 Assume all rods are scrammable. The SHUTDOWN MARGIN in accordance with the UCINRF Technical Specifications for this core is:

a. $1.70

b. $2.5

c. $5.0

d. $6.8

Section A L Theory, Thermo, and Facility Characteristics QUESTION A.3 [1.0 point]

The plot below depicts reactor period as a function of time. What best describes the behavior of REACTOR POWER between points A and B?

a. Constant

b. Continually increasing

c. Continually decreasing

d. Decreasing then increasing QUESTION A.4 [1.0 point]

Which of the following statements is true about Xenon following a reactor scram?

135 135

a. The concentration of Xe will decrease by natural decay into I 135

b. The concentration of Xe will decrease due to reduced nuclear flux 135 135

c. The concentration of Xe will increase due to the decay of the I inventory 135

d. The concentration of Xe will remain constant until it is removed via neutron burnout during the subsequent reactor startup

Section A L Theory, Thermo, and Facility Characteristics QUESTION A.5 [1.0 point]

In every minute reactor power is increasing by a factor of 5. The reactor period is:

a. 65 seconds

b. 37 seconds

c. 26 seconds

d. 13 seconds QUESTION A.6 [1.0 point]

In a subcritical reactor with Keff of 0.931, a reactivity worth of 0.017 k is inserted into the reactor core. Which ONE of the following is the NEW Keff ?

a. 0.925

b. 0.933

c. 0.946

d. 1.001 QUESTION A.7 [1.0 point, 0.25 each]

Fill out the blank with INCREASE or DECREASE due to effects of moderator temperature increase.

a. Slowing down length _____________

b. Thermal non leakage _____________

c. Resonance escape probability _____________

d. Thermal utilization factor _____________

Section A L Theory, Thermo, and Facility Characteristics QUESTION A.8 [1.0 point]

A reactor with Keff = 0.8 contributes 1000 neutrons in the first generation. Changing from the FIRST generation to THIRD generation, the TOTAL neutrons after the third generation are between:

a. 1000 - 1500 neutrons

b. 2000 - 2500 neutrons

c. 3000 - 3500 neutrons

d. 4000 - 4500 neutrons QUESTION A.9 [1.0 point]

Which ONE of the following is a correct statement of why delayed neutrons enhance the ability to control reactor power?

a. Prompt neutrons are born at lower energy levels than delayed neutrons

b. Prompt neutrons can cause fissions in both U-235 and U-238; whereas delayed neutrons can only cause fissions in U-235

c. Delayed neutrons increase the average neutron lifetime that allows a reactor to be controlled

d. The average number of delayed neutrons produced per fission is higher than the average number of prompt neutrons QUESTION A.10 [1.0 point]

Which ONE of the following correctly describes the SIX- FACTOR FORMULA?

a. K4 = Keff

the reproduction factor ()

b. K4 = Keff

the total non-leakage probability (L f

L th)

c. Keff = K4

the total non-leakage probability (L f

L th)

d. Keff = K4 * (the resonance escape probability (p)* the reproduction factor ())

Section A L Theory, Thermo, and Facility Characteristics QUESTION A.11 [1.0 point]

The reactor is subcritical with the count rate of 100 counts per second (cps) and Keff of 0.950.

The control rods are withdrawn until the count rate is doubled. What is the new value of Keff?

a. 0.952

b. 0.975

c. 0.998

d. 1.020 QUESTION A.12 [1.0 point]

Which ONE of the following combinations of characteristics makes a good reflector?

Scattering Cross Section Absorption Cross Section

a. High High

b. Low High

c. High Low

d. Low Low QUESTION A.13 [1.0 point]

The injection of a sample results in a 100 millisecond period. If the scram setpoint is 250 KILOWATTS and the scram delay time is 0.2 seconds, which ONE of the following is the peak power of the reactor at shutdown?

a. 305 kW

b. 373 kW

c. 680 kW

d. 1847 kW

Section A L Theory, Thermo, and Facility Characteristics QUESTION A.14 [1.0 points]

Reactor is at a power level of 200 kW. The operator immediately scrams the SHIM rod with a reactivity worth of $1.75 back to the core. This action will cause:

Given:

T: reactor period, *: Prompt neutron lifetime; : reactivity insertion; : beta fraction

a. A delayed reactor period to be equal to POSITIVE (+) 80 seconds

b. A number of prompt neutrons equals to a number of delayed neutrons

c. The immediate reactor period to be a function of the prompt neutron lifetime (T=*/)

d. A sudden change of power that equals to the initial power multiplied by (1- )/ ( -)

QUESTION A.15 [1.0 point]

A reactor has an effective delayed fraction (eff ) of 0.0065. If a control rod withdrawal in this reactor increases the effective multiplication (keff ) from 0.998 to 1.005, the reactor is:

a. subcritical.

b. exactly critical.

c. supercritical.

d. prompt critical.

QUESTION A.16 [1.0 point]

Which ONE of the following physical characteristics of the TRIGA fuel is the MAIN contributor for the prompt negative temperature coefficient?

a. As the fuel heats up, a rapid increase in moderator temperature occurs through conduction and convection heat transfer mechanisms which adds negative reactivity

b. As the fuel heats up, the oscillating hydrogen in the Zr-H lattice imparts energy to a thermal neutron, thereby increasing its mean free path and probability of escape

c. As the fuel heats up, the resonance absorption peaks broaden and increases the likelihood of absorption in U-238 and/or Pu-240

d. As the fuel heats up, fission product poisons (e.g., Xe) increase in concentration within the fuel matrix and add negative reactivity via neutron absorption

Section A L Theory, Thermo, and Facility Characteristics QUESTION A.17 [1.0 point]

Which ONE of the following conditions will DECREASE the shutdown margin of a reactor?

a. Higher moderator temperature (assume negative temperature coefficient)

b. Insertion of a negative reactivity worth experiment

c. Burnout of a burnable poison

d. Fuel depletion

Section A L Theory, Thermo, and Facility Characteristics QUESTION A.18 [1.0 point]

Use Figure 3.3 attached. Calculate the effective delayed neutron fraction (-effective). At birth energies, there are 65 delayed neutrons and 9935 prompt neutrons. In the process of slowing down, there are only 56 delayed neutrons and 7352 prompt neutrons at the thermal range. The resultant -effective of Figure 3.3 is:

a. 0.00654

b. 0.00756

c. 0.00762

d. 0.00348 End of Section A

Section B Normal, Emergency and Radiological Control Procedures QUESTION B.1 [1.0 point]

A component or system is defined as operable by Technical Specifications if:

a. it has no outstanding testing requirements

b. a functional test has been performed

c. it is capable of performing its intended function

d. a channel check has been performed QUESTION B.2 [1.0 point]

Per UCINRF SOP, which ONE of the following radioactive gases poses the most significant hazard within the reactor room during NORMAL operations?

a. Tritium

b. Argon-41

c. Xenon-135

d. Iodine-131 QUESTION B.3 [1.0 point, 0.25 each]

Match the following frequently used terms in Column A with their respective definitions in column B Column A Column B

a. Channel 1. An introduction of a signal into the channel to verify that it is operable

b. Channel Calibration 2. A combination of a sensor, lines amplifier and output device which are connected for the purpose of measuring the value of a parameter

c. Channel Check 3. An adjustment of the channel such that its output corresponds with acceptable accuracy to known values of the parameter that the channel measures

d. Channel Test 4. A qualitative verification of acceptable performance by observation of channel behavior

Section B Normal, Emergency and Radiological Control Procedures QUESTION B.4 [1.0 point]

Which ONE of the following events does NOT require the presence of a licensed Senior Reactor Operator in the facility?

a. Fuel relocations within the core region

b. Initial start-up and approach to power

c. Insertion of experiment worth of $0.50

d. Restart following an unplanned shutdown QUESTION B.5 [1.0 point]

While working in an area marked "Caution, Radiation Area," you discover your dosimeter is off scale and leave the area. Assuming you had been working in the area for 45 minutes, what is the MAXIMUM dose you would have received?

a. 3.8 mrem

b. 35.6 mrem

c. 75.0 mrem

d. 100 mrem QUESTION B.6 [1.0 point]

Which one of the following is the definition for Annual Limit on Intake (ALI)?

a. The concentration of a radionuclide in air which, if inhaled by an adult worker for a year, results in a total effective dose equivalent of 100 millirems

b. 10 CFR 20 derived limit, based on a Committed Effective Dose Equivalent of 5 rems whole body or 50 rems to any individual organ, for the amount of radioactive material inhaled or ingested in a year by an adult worker

c. The effluent concentration of a radionuclide in air which, if inhaled continuously over a year, would result in a total effective dose equivalent of 50 millirems for noble gases

d. Projected dose commitment to individuals that warrant protective action following a release of radioactive material

Section B Normal, Emergency and Radiological Control Procedures QUESTION B.7 [1.0 point]

Which ONE of the following statements correctly describes the relationship between the Safety Limit (SL) and the Limiting Safety System Setting (LSSS)?

a. The SL is a maximum operationally limiting value that prevents exceeding the LSSS during normal operations.

b. The SL is a limit on important process variables that assures the integrity of the fuel cladding. The LSSS initiates protective actions to preclude reaching the SL.

c. The LSSS is a limit on important process variables that assures the integrity of the fuel cladding. The SL initiates protective action to preclude reaching the LSSS.

d. The SL is a maximum setpoint for instrumentation response. The LSSS is the minimum number of channels required to be operable.

QUESTION B.8 [1.0 point]

According to the UCINRF Emergency Plan, who is the first person that should be contacted if there is a vague threat of disorder?

a. UCI Police

b. Facility Director

c. Senior Reactor Operator

d. Reactor Operator

Section B Normal, Emergency and Radiological Control Procedures QUESTION B.9 [1.0 point]

What is the HALF LIFE of the isotope contained in a sample which produces the following count rates?

Time (Minutes) Counts per Minute (cpm)

Initial 950 60 702 120 518 180 383 240 283

a. 124

b. 137

c. 201

d. 558 QUESTION B.10 [1.0 point]

What is the MINIMUM level of APPROVAL required for any changes made to the Emergency Plan?

a. Reactor Operator

b. Senior Reactor Operator

c. Facility Director

d. Reactor Operations Committee

Section B Normal, Emergency and Radiological Control Procedures QUESTION B.11 [1.0 point]

During an emergency, the Command Post (CP) is the reactor control room, what is the MINIMUM radiation level for the CP to be moved out of the control room?

a. 10 mrem

b. 25 mrem

c. 100 mrem

d. 150 mrem QUESTION B.12 [1.0 point]

Which ONE of the following conditions requires the NRC APPROVAL for changes?

a. Revise the startup checklist

b. Major changes in the UCINRF SOP 4.1, Reactor Operation

c. Revise the requalification operator licensing examination

d. Reduce the minimum number of the Reactor Operations Committee members from five to four QUESTION B.13 [1.0 point]

Per UCINRF Technical Specifications, which ONE of the following is the frequency for a surveillance requirement of the transient (pulse) rod drive cylinder?

a. Quarterly

b. Semiannually

c. Annually

d. Biennially

Section B Normal, Emergency and Radiological Control Procedures QUESTION B.14 [1.0 point]

A survey instrument with a window probe is used to measure the beta-gamma dose rate from an irradiated experiment. The dose rate is 240 mrem/hour with the window opened and 60 mrem/hour with the window closed. The gamma dose rate is:

a. 60 mrem/hour

b. 180 mrem/hour

c. 240 mrem/hour.

d. 300 mrem/hour QUESTION B.15 [1.0 point]

Match the 10CFR55 requirements for maintaining an active operator license in column A with the corresponding time period from column B.

Column A Column B

a. Renew License 1 year

b. Medical Exam 2 years

c. Pass Requalification Written Examination 4 years

d. Pass Requalification Operating Test 6 years QUESTION B.16 [1.0 point]

Which ONE of the following SCRAMS is NOT required in all modes by Technical Specifications?

a. Manual Button

b. Seismic Switch

c. Reactor Power Level

d. Fuel Element Temperature

Section B Normal, Emergency and Radiological Control Procedures QUESTION B.17 [1.0 point]

The UCINRF Safety Limit is on:

a. the reactor pulse insertion, which is $3.00

b. the temperature at the B-ring, which is 800 °C

c. the reactor pool level, which is 19 ft above core

d. the temperature of fuel cladding, which is 1000 °C QUESTION B.18 [1.0 point]

At the UCINRF, which ONE of the following is NOT an acceptable type of encapsulation material for reactor irradiation experiments?

a. polyvinylchloride

b. polyethylene

c. metal

d. quartz

Section C Plant and Radiation Monitoring Systems QUESTION C.1 [1.0 point]

Which ONE of the following control rods has the highest reactivity worth?

a. Shim rod

b. Regulating rod

c. Fast transient rod

d. Adjustable transient rod QUESTION C.2 [1.0 point]

Per SOP UCINRF 4.7.6, the old resin in the pool water purification system needs to be replaced when:

a. the pH of the reactor tank water is between 6 and 7

b. the flow rate of the purification system is higher than 10 gpm

c. the conductivity of the INLET position is lower than 2 mhos/cm

d. the conductivity of the OUTLET position is higher than 2 mhos/cm QUESTION C.3 [1.0 point]

If the Wide Range Linear Power Channel output is about 3% higher than the calculated thermal power calibration, the reactor operator needs to adjust the Linear Power Channel output by:

a. adjusting the CIC detector high voltage

b. adjusting the channel heat level potentiometer

c. moving the graphite reflector to change the neutron flux near the detectors

d. physically adjusting the height of the Fission detector in the support assembly

Section C Plant and Radiation Monitoring Systems QUESTION C.4 [1.0 point]

Which ONE of the following materials is used for the Adjustable Transient rod follower?

a. Air

b. Cadmium

c. Borate graphite

d. Uranium QUESTION C.5 [1.0 point]

The UCINRF reactor uses the Uncompensated Ion Chamber (UIC) for:

a. Period Channel

b. Startup Channel

c. Power Range Channel

d. Linear Power Channel QUESTION C.6 [1.0 point]

During reactor operation, a tube in the heat exchanger has a leak. Which ONE of the following correctly explains the reactor pool level?

a. Pool level will increase because the Primary pressure is HIGHER than the Secondary pressure

b. Pool Level will increase because the Primary pressure is LOWER than the Secondary pressure

c. Pool Level will be the same because the Primary pressure is EQUAL to the Secondary pressure

d. Pool Level will decrease because the Primary pressure is HIGHER than Secondary pressure

Section C Plant and Radiation Monitoring Systems QUESTION C.7 [1.0 point]

The switch mounted on each drive assembly indicates the control rod at its bottom limit of travel, i.e., fully inserted into the core. This switch is called:

a. the magnet down microswitch

b. the magnet up microswitch

c. the rod down microswitch

d. the rod up microswitch QUESTION C.8 [1.0 point]

Impurity in the reactor cooling water will be made radioactive when the reactor is operated.

Which ONE of the following is the common contaminant that creates impurity? Assume that no fuel leak occurred.

a. N16

b. Na24

c. Ar41

d. I 131 QUESTION C.9 [1.0 point]

Which ONE of the following Experimental Facilities provides the HIGHEST neutron flux?

a. Central Thimble

b. Pneumatic Transfer System

c. Rotary Specimen Rack Assembly

d. In-Pool Facility

Section C Plant and Radiation Monitoring Systems QUESTION C.10 [1.0 point]

To reduce neutron leakage, which ONE of the following materials is inserted in the top and bottom of the active fuel portion of each fuel element?

a. Aluminum

b. Boron

c. Cadmium

d. Graphite QUESTION C.11 [1.0 point, 0.25 each]

Match the inputs listed in column A with their responses listed in column B. (Items in column B may be used more than once or not at all). Assume the reactor is in operation.

Column A Column B

a. Activate seismic switch 1. Indicate only

b. Percent power level in steady state =110 % 2. Interlocks

c. Pool water conductivity = 1 µmho/cm 3. Scram

d. Startup level = 1 x 10 -6 % power QUESTION C.12 [1.0 point]

You are about to depress a fire button for a pulse. You note that the ventilation is NOT operable. For this event, you will:

a. continue to depress a fire button for a pulse because the ventilation operation does NOT require in Tech Spec

b. continue to depress a fire button for a pulse because an exception may be made for periods of time not to exceed two days

c. stop conducting a pulse; immediately report the result to the supervisor because Ventilation system is required by Tech Spec for pulse operation d stop all operations, immediately report the result to the U.S. NRC since it is a reportable occurrence

Section C Plant and Radiation Monitoring Systems QUESTION C.13 [1.0 point]

During a reactor operation, you discover the Continuous Air Monitor (CAM) pump failure. Which ONE of the following is the correct action in accordance with UCINRF Technical Specifications?

a. Continue to operate and you dont have to report to the supervisor because the pump failure does NOT affect the operations of the CAM

b. Report the result to the supervisor and continue to operate because the reactor can operate for 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> with the operable ARM system

c. Immediately shutdown the reactor and report the result to the supervisor because the CAM is NOT operable due to pump failure d Shutdown the reactor, immediately report the result to the U.S. NRC because it is a reportable occurrence.

QUESTION C.14 [1.0 point]

You perform a fuel follower control rod inspection. In measuring the lateral bend, you find the bend of one fuel follower exceeds the original bend by 0.10 inches. For this measurement, you will:

a. continue the fuel inspection because this bend is within TS limit

b. continue the fuel inspection because the UCI Tech Spec requires the elongation measurement only

c. stop the fuel inspection; immediately report the result to the supervisor because it is considered a damaged fuel follower d stop the fuel inspection, immediately report the result to the U.S. NRC since it is a reportable occurrence QUESTION C.15 [1.0 point]

Which ONE of the following is the main function of the demineralizer in the primary purification system?

a. Absorb delayed neutrons, thus increase life of the reactor tank

b. Absorb Ar-41, thus reduce the effluent released to environment

c. Absorb O-16, thus reduce the N-16 dose rate at the reactor tank surface

d. Remove both positive and negative ions to maintain low conductivity in the tank water

Section C Plant and Radiation Monitoring Systems QUESTION C.16 [1.0 point]

Given the configuration of the LIGHTS associated with the SHIM rod/drive as follows: UP:ON, DOWN: OFF, CONT/ON: OFF, and no failure of switch lights. Identify the conditions of the SHIM rod.

a. Normal condition, rod insertion permissible

b. Abnormal condition, misadjusted rod down limit switch

c. Normal condition, either rod insertion or withdrawal permissible

d. Abnormal condition, Rod-down switch not functioning QUESTION C.17 [1.0 point]

Which ONE of the following is the main function performed by the DISCRIMINATOR circuit in the Wide Range Monitor Channel?

a. To convert the signal logarithmic output of the metering circuit to a t (delta time) output for period metering purposes.

b. To generate a current signal equal and of opposite polarity as the signal due to gamma generated within the Wide Range Monitor Channel.

c. To filter out small pulses due to gamma interactions, passing only pulses due to neutron events within the Wide Range Monitor Channel.

d. To filter out small pulses due to neutron events, passing only pulses due to gamma interactions within the Wide Range Monitor Channel.

Section C Plant and Radiation Monitoring Systems QUESTION C.18 [1.0 point]

For calibration of the control rod, which ONE of the following is the MINIMUM change in the summed total integral worth that the operator has to notify the Reactor Supervisor?

a. $0.25

b. $0.50

c. $0.75

d. $1.00

- - - - End of Section C *****************************

- - - - End of the Exam ***************************

Section A L Theory, Thermo, and Facility Characteristics Answer Key A.1 Answer: d

Reference:

Technical Specifications SDM = 3rod worth removed at critical - most reactivity control rod worth= $8.5 -$3.5 = $5.0 or Technical Specifications SDM = total rod worth -(3(rod excesses) + most reactivity control rod worth)= $10.2 -($1.7+$3.5) = $5.0 A.3 Answer: c t

T

Reference:

From point A to B, reactor period is negative, and since Pf=Poe , power will continue to decrease.

A.4 Answer: c

Reference:

Following a reactor shutdown, xenon-135 concentration will increase due to the decay of the iodine inventory of the core.

DOE Handbook, Vol 2, Section 4 A.5 Answer: b

Reference:

P=Poet/ J = 60 sec/ln(5) = 37.28 sec A.6 Answer: c

Reference:

= (Keff1-Keff2)/(Keff1*Keff2). 0.017 = (x-0.931)/(x*0.931); 0.017*0.931*x =x-0.931 0.01583x=x-0.931; 0.98417x =0.931; x=0.931/0.98417; x=0.946

Section A L Theory, Thermo, and Facility Characteristics A.7 Answer: a, Increase b, Decrease c, Decrease d, Decrease

Reference:

DOE Handbook Vol 2, L Theory (Nuclear Parameters), E.O. 1.1 a&b, pg. 9 A.11 Answer: b

Reference:

Count1*(1-Keff1) = Count2*(1-Keff2) 100*(1-0.950) = 200*(1-Keff2) 100*(1-0.95) = 200(1- Keff2); Keff2 = 0.975 A.12 Answer: c

Reference:

Standard NRC Question A.13 Answer: d

Reference:

Section A L Theory, Thermo, and Facility Characteristics A.15 Answer: c REF: Burn, R., Introduction to Nuclear Reactor Operations, © 1982, Section 4.2, page 4-1. Note: For prompt critical, keff has to be 1.0065 A.16 Answer: b

Reference:

TRIGA Fuel Design A.17 Answer c

Reference:

Burnout of a burnable poison will increase the core excess, hence decrease the shutdown margin A.18 Answer: b

Reference:

Section B Normal, Emergency and Radiological Control Procedures Answer Key B.1 Answer: c

Reference:

TS Section 1 B.2 Answer: b

Reference:

UCINRF SOP 5.6.1 B.3 Answer: a,2 b,3 c,4 d,1

Reference:

TS Section 1 B.4 Answer: c

Reference:

TS Section 6.1.3d B.5 Answer: c

Reference:

10 CFR 20.1003, radiation area ranges from 5 ~100 mrem/hr so maximum dose in a radiation area is approximately 100 mrem/hr . For 45 min: 100 mrem/hr at 0.75 hr = 75 mrem B.6 Answer: b

Reference:

10 CFR 20.1003 B.7 Answer: b

Reference:

TS Section 1 B.8 Answer: a

Reference:

UCINRF Emergency Plan Section 7.1.1 B.9 Answer: b

Reference:

, , , = 0.00505 B.10 Answer: d

Reference:

UCINRF Emergency Plan Section 10.3

Section B Normal, Emergency and Radiological Control Procedures B.11 Answer: a

Reference:

Emergency Plan Section 8.1 B.12 Deleted Answer: d

Reference:

10 CFR 50.59, TS Section 6.2.1 B.13 Answer: c

Reference:

UCINRF SOP 4.2 B.14 Answer: a

Reference:

Basic radiation instrumentation B.15 Answer: a=6 b=2 c=2 d=1

Reference:

10 CFR 55 B.16 Answer: c

Reference:

TS Section 3.4 B.17 Answer: d

Reference:

TS Section 2.1 B.18 Answer: a

Reference:

UCINRF SOP 2.4.2

Section C Plant and Radiation Monitoring Systems Answer Key C.1 Answer: a

Reference:

SAR 6.2 C.2 Answer: d

Reference:

SOP UCINRF 4.7.6 C.3 Answer: b

Reference:

SOP UCINRF 4.3.2 C.4 Answer: a

Reference:

SAR figure 4.7 C.5 Answer: c

Reference:

SAR 7.2.6 C.6 Answer: b

Reference:

Knowledge during site visit C.7 Answer: c

Reference:

Instruction Manual for Operation 5.3.2 C.8 Answer: b

Reference:

Instruction Manual for Operation 8.5.4 C.9 Answer: a

Reference:

SAR 10.4 Highest flux due to its location (center of the reactor core)

C.10 Answer: d

Reference:

Instruction Manual for Operation 5.2 C.11 Answer: a(3) b(3) c(1) d(1)

Reference:

TSs 3.2.3 and 3.3 C.12 Answer: c

Reference:

TS 3.2.3

Section C Plant and Radiation Monitoring Systems C.13 Answer: c

Reference:

TS 3.3 C.14 Answer: c

Reference:

TS 4.1 C.15 Answer: d

Reference:

Instruction Manual for Operation 5.6 C.16 Answer: d

Reference:

UCI Instruction Manual for Operators, Table 6.1 C.17 Answer: c

Reference:

SAR 6.2.1 C.18 Answer: b

Reference:

Administrative Procedure 4.4.2

- - - - END OF THE EXAM ********************************

ML13088A150

Text

SUBJECT:

Dear Dr. Miller:

Enclosures:

SUBJECT:

Dear Dr. Miller:

Enclosures:

SUMMARY

T=

Reference:

Reference:

Reference:

Reference:

Reference:

Reference:

Reference:

Reference:

Reference:

Reference:

Reference:

Reference:

Reference:

Reference:

Reference:

Reference:

Reference:

Reference:

Reference:

Reference:

Reference:

Reference:

Reference:

Reference:

Reference:

Reference:

Reference:

Reference:

Reference:

Reference:

Reference:

Reference:

Reference:

Reference:

Reference:

Reference:

Reference:

Reference:

Reference:

Reference:

Reference:

Reference:

Reference:

Reference:

Reference:

Reference:

Reference:

Reference:

Reference:

Reference:

Reference:

Reference:

Reference:

Navigation menu

Search