Text

Examination Report Letter No. 50-252/OL-23-01, University of New Mexico
	ML23079A230
Person / Time
Site:	University of New Mexico; (R-102)
Issue date:	03/21/2023
From:	Travis Tate; NRC/NRR/DANU/UNPO
To:	Willis C; Univ of New Mexico, Nuclear Engineering Department
References
	50-252/23-01 50-252/OL-23
	Download: ML23079A230 (2)
	v • d • e

Carl Willis, Chief Reactor Supervisor Nuclear Engineering Department 1 University of New Mexico, MSC-01-1120 Albuquerque, NM 87131-0001

SUBJECT:

EXAMINATION REPORT NO. 50-252/OL-23-01, UNIVERSITY OF NEW MEXICO

Dear Carl Willis:

During the week of January 17, 2023, the U.S. Nuclear Regulatory Commission (NRC) administered operator licensing examinations at your University of New Mexico Reactor. The examinations were conducted according to NUREG-1478, "Operator Licensing Examiner Standards for Research and Test Reactors," Revision 2. Examination questions and preliminary findings were discussed with those members of your staff identified in the enclosed report at the conclusion of the examination.

In accordance with Title 10 of the Code of Federal Regulations, Section 2.390, 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 (PARS) component of NRC's Agencywide Documents Access and Management System (ADAMS). ADAMS is accessible from the NRC website at http://www.nrc.gov/reading-rm/adams.html. The NRC is forwarding the individual grades to you in a separate letter which will not be released publicly. Should you have any questions concerning this examination, please contact Michele C. DeSouza at 301-415-0747 or via email at Michele.DeSouza@nrc.gov.

Sincerely, Travis L. Tate, Chief Non-Power Production and Utilization Facility Oversight Branch Division of Advanced Reactors and Non-Power Production and Utilization Facilities Office of Nuclear Reactor Regulation Docket No. 50-252

Enclosures:

1. Examination Report No. 50-252/OL-23-01

2. Written examination cc: w/o enclosures: See next page March 21, 2023 Signed by Tate, Travis on 03/21/23

Purdue University Docket No. 50-252 cc:

Dr. Mark Lundstrom Interim Dean of Engineering Armstrong Hall of Engineering, Suite 3000 701 West Stadium Avenue West Lafayette, IN 47907-2045 Mayor City of West Lafayette 1200 N. Salisbury Street West Lafayette, IN 47906 John H. Ruyack, Manager Epidemiology Res Center/Indoor & Radiological Health Indiana Department of Health 2525 N. Shadeland Avenue, Suite E3 Indianapolis, IN 46219 Howard W. Cundiff, P.E., Director Consumer Protection Indiana State Department of Health 2 North Meridian Street, 5D Indianapolis, IN 46204 Test, Research and Training Reactor Newsletter Attention: Amber Johnson Dept of Materials Science and Engineering University of Maryland 4418 Stadium Drive College Park, MD 20742-2115

ML23079A230 NRR-079 OFFICE NRR/DANU/UNPO/CE NRR/DANU/UNPO/OLA NRR/DANU/UNPO/BC NAME MDeSouza NJones TTate DATE 3/20/2023 3/20/2023 3/21/2023

U.S. NUCLEAR REGULATORY COMMISSION OPERATOR LICENSING INITIAL EXAMINATION REPORT REPORT NO.:

50-252/OL-23-01 FACILITY DOCKET NO.:

50-252 FACILITY LICENSE NO.:

R-102 FACILITY:

University of New Mexico EXAMINATION DATES:

January 17, 2023 SUBMITTED BY:

01/18/2023 Michele C. DeSouza, Chief Examiner Date

SUMMARY

During the week of January 17, 2023, the NRC administered operator licensing examinations to one Reactor Operator (RO) and one RO written retake candidates. Two RO candidates passed all applicable portions of the examinations and tests.

REPORT DETAILS 1.

Examiner:

Michele C. DeSouza, Chief Examiner, NRC 2.

Results:

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

Exit Meeting:

Carl Willis, Chief Reactor Supervisor, University of New Mexico Rowdy Davis, Training Coordinator, University of New Mexico Michele C. DeSouza, Chief Examiner, NRC Prior to administration of the written examination, based on facility comments, adjustments were accepted. Comments provided corrections and additional clarity to questions/answers and identified where changes were appropriate based on current facility conditions.

Upon completion of all operator licensing examinations, the NRC examiner met with facility staff representatives to discuss the results. At the conclusion of the meeting, the NRC examiner thanked the facility for their support in the administration of the examination.

University of New Mexico Operator Licensing Examination Week of January 17, 2023

U.S. NUCLEAR REGULATORY COMMISSION NON-POWER REACTOR LICENSE EXAMINATION FACILITY:

University of New Mexico REACTOR TYPE:

AGN-201 DATE ADMINISTERED:

01/17/2023 CANDIDATE:

INSTRUCTIONS TO CANDIDATE:

Answers are to be written on the Answer sheet provided. Attach all Answer sheets to the examination. Point values are indicated in parentheses for each question. A 70% in each category is required to pass the examination. Examinations will be picked up three (3) hours after the examination starts.

% OF CATEGORY % OF CANDIDATE'S CATEGORY VALUE TOTAL SCORE VALUE CATEGORY 20.00 33.3 A. REACTOR THEORY, THERMODYNAMICS AND FACILITY OPERATING CHARACTERISTICS 20.00 33.3 B. NORMAL AND EMERGENCY OPERATING PROCEDURES AND RADIOLOGICAL CONTROLS 20.00 33.3 C. FACILITY AND RADIATION MONITORING SYSTEMS 60.00 % TOTALS FINAL GRADE All work done on this examination is my own. I have neither given nor received aid.

Candidate's Signature

Category A: Reactor Theory, Thermodynamics, & Facility Operating Characteristics A N S W E R S H E E T Multiple Choice (Circle or X your choice)

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

A01 a b c d ___

A02 a b c d ___

A03 a b c d ___

A04 a b c d ___

A05 a b c d ___

A06 a b c d ___

A07 a b c d ___

A08 a b c d ___

A09 a b c d ___

A10 a b c d ___

A11 a b c d ___

A12 a b c d ___

A13 a b c d ___

A14 a b c d ___

A15 a b c d ___

A16 a b c d ___

A17 a b c d ___

A18 a b c d ___

A19 a b c d ___

A20 a b c d ___

(***** END OF CATEGORY A *****)

Category B: Normal/Emergency Operating Procedures and Radiological Controls A N S W E R S H E E T Multiple Choice (Circle or X your choice)

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

B01 a b c d ___

B02 a b c d ___

B03 a b c d ___

B04 a b c d ___

B05 a _____ b _____ c _____ d _____ (0.25 each)

B06 a b c d ___

B07 a b c d ___

B08 a b c d ___

B09 a b c d ___

B10 a _____ b _____ c _____ d _____ (0.50 each)

B11 a b c d ___

B12 a b c d ___

B13 a b c d ___

B14 a b c d ___

B15 a b c d ___

B16 a b c d ___

B17 a b c d ___

B18 a b c d ___

B19 a b c d ___

(***** END OF CATEGORY B *****)

Category C: Facility and Radiation Monitoring Systems A N S W E R S H E E T Multiple Choice (Circle or X your choice)

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

C01 a b c d ___

C02 a b c d ___

C03 a b c d ___

C04 a b c d ___

C05 a b c d ___

C06 a b c d ___

C07 a b c d ___

C08 a b c d ___

C09 a b c d ___

C10 a b c d ___

C11 a b c d ___

C12 a b c d ___

C13 a b c d ___

C14 a _____ b _____ c _____ d _____ (0.50 each)

C15 a b c d ___

C16 a b c d ___

C17 a b c d ___

C18 a b c d ___

C19 a b c d ___

(***** END OF CATEGORY C *****)

(********** END OF EXAMINATION **********)

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.

Mark your Answers on the Answer sheet provided. USE ONLY THE PAPER PROVIDED AND DO NOT WRITE ON THE BACK SIDE OF THE PAGE.

7.

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

8.

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

9.

When turning in your examination, assemble the completed examination with examination questions, examination aids and Answer sheets. In addition, turn in all scrap paper.

10.

Ensure all information you wish to have evaluated as part of your Answer is on your Answer sheet. Scrap paper will be disposed of immediately following the examination.

11.

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

12.

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

EQUATION SHEET

=

+[

]

DR - Rem, Ci - curies, E - Mev, R - feet 1 Curie = 3.7 x 1010 dis/sec 1 kg = 2.21 lb 1 Horsepower = 2.54 x 103 BTU/hr 1 Mw = 3.41 x 106 BTU/hr 1 BTU = 778 ft-lb

°F = 9/5 °C + 32 1 gal (H2O) 8 lb

°C = 5/9 (°F - 32) cP = 1.0 BTU/hr/lb/°F cp = 1 cal/sec/gm/°C

2 2

max

P 1

sec 1.0

eff

te P

P 0

eff K

S S

SCR

1

sec 10 1

4

eff SUR 06 26

2 1

1 1

2 1

eff eff K

CR K

CR

2 2

1 1

CR CR 2

1 1

1 eff eff K

K M

1 2

1 1

CR CR K

M eff

)

(

0 10 t

SUR P

P

0 1

P P

eff eff K

K SDM

1

2 1

1 2

eff eff eff eff K

K K

K

693

.0 2

1 T

eff eff K

K 1

t e

DR DR

0

2 6

R n

E Ci DR 2

2 2

2 1

1 d

DR d

DR

1 2

2 2

Peak Peak

T UA H

m T

c m

Q P

Category A: Reactor Theory, Thermodynamics, and Facility Operating Characteristics QUESTION A.01

[1.0 point]

Reactor is critical, operating at 100 watts. A control rod is withdrawn to insert a positive reactivity of 0.140%k/k. Which ONE of the following will be the stable reactor period as a result of the reactivity insertion? Given Beta effective = 0.0070 a.

90 seconds b.

80 seconds c.

50 seconds d.

40 seconds QUESTION A.02

[1.0 point]

For the 0 -1 decay of a nuclide, a number of protons of the nuclide will ___________

and its atomic mass number will __________.

a.

decrease by 1, decrease by 1 b.

decrease by 1, be the same

c. increase by 1, be the same c.

increase by 1, increase by 1 QUESTION A.03

[1.0 point]

Which ONE of the following describes the general shape in determining the integral rod worth of a control rod?

a.

Exponentially shaped, with the maximum at the bottom of the core height.

b.

Cosine shaped, with the largest change in the middle of the core height.

c.

S-shaped, with the net change in reactivity from bottom to top.

d.

Parabolic shaped, with the maximum at the top and bottom of the core height.

QUESTION A.04

[1.0 point]

Inelastic scattering can best be described as a process whereby:

a.

A neutron strikes a nucleus, with the nucleus in its ground state, the neutron reappears, the nucleus is left in an excited state, and the nucleus emits one or more gamma rays b.

A neutron is captured by the nucleus and the nucleus emits one or more gamma rays c.

A neutron strikes a nucleus, with the nucleus in its ground state, the neutron reappears, and the nucleus is left in its ground state d.

A neutron is captured by the nucleus and the nucleus splits apart

Category A: Reactor Theory, Thermodynamics, and Facility Operating Characteristics QUESTION A.05

[1.0 point]

The AGN reactor is subcritical with the following values for each of the factors in the six-factor formula:

Fast Fission Factor = 1.03 Fast non-leakage probability = 0.84 Resonance Escape Probability = 0.96 Thermal non-leakage probability = 0.88 Thermal Utilization Factor = 0.69 Reproduction Factor = 1.96 The fueled AGN coarse control rod is inserted to bring the reactor critical. Assuming all other factors remain unchanged, the new value for the Thermal Utilization Factor is:

a. 0.705

b. 0.695

c. 0.702

d. 0.698 QUESTION A.06

[1.0 point]

The reactor is supercritical and increasing in power. Power has increased from 20 mW to 40 mW in 10 seconds. How long will it take at this rate for power to increase from 0.04 W to 1 W?

a.

26 seconds b.

46 seconds c.

66 seconds

d. 80 seconds QUESTION A.07

[1.0 point]

If a source strength is 1000 neutrons per second (N/sec) and it produces the stable neutron count rate of 5000 N/sec. What is the multiplication factor (K)?

a. 0.6

b. 0.7

c. 0.8

d. 0.9

Category A: Reactor Theory, Thermodynamics, and Facility Operating Characteristics QUESTION A.08

[1.0 point]

Which ONE of the following conditions will INCREASE the reactivity in the reactor?

a.

Sudden burn-up of Xenon in the fuel element.

b.

Decrease density of U-235 in the fuel element.

c.

Decrease density of the pool water.

d.

Doppler broadening effect.

QUESTION A.09

[1.0 point]

The k-eff for the reactor is 0.975. The reactivity (k/k) needed to bring the reactor to criticality is:

a.

+0.0256 b.

+0.0250 c.

-0.0256 d.

-0.0250 QUESTION A.10

[1.0 point]

Which type of neutron interaction (light nuclei) is most important in moderating fast neutrons to thermal energies?

a.

Radiative capture b.

Elastic scattering c.

Inelastic scattering d.

Charged particle interactions QUESTION A.11

[1.0 point]

The reaction 93Np239 _____ + 94Pu239 is an example of:

a.

Alpha Decay b.

Beta Decay c.

Gamma Emission d.

Electron Capture QUESTION A.12

[1.0 point]

Category A: Reactor Theory, Thermodynamics, and Facility Operating Characteristics Negative Point B Point A Positive Which ONE of the following isotopes has the HIGHEST thermal neutron cross section?

a.

Cd-112 b.

Sm-149 c.

Xe-135

d. U-235 QUESTION A.13

[1.0 point]

Shown below is a trace of reactor period as a function of time. Between points A and B reactor power is:

a.

Continually increasing.

b.

Continually decreasing.

c.

Increasing, then decreasing.

d.

Constant.

QUESTION A.14

[1.0 point]

A reactor is subcritical if:

a.

= 1.0 b.

Keff < 1.0 or < 0.0 c.

K= 1.0, =

d.

Keff > 1.0 or > 0.0 QUESTION A.15

[1.0 point]

What is the kinetic energy range of a thermal neutron?

a.

> 1 MeV b.

100 keV - 1 MeV c.

1 eV - 100 keV d.

< 1 eV QUESTION A.16

[1.0 point]

Category A: Reactor Theory, Thermodynamics, and Facility Operating Characteristics Which ONE of the following types of neutrons has a mean neutron generation lifetime of about 12 seconds?

a.

Prompt b.

Delayed c.

Fast d.

Thermal QUESTION A.17

[1.0 point]

If the multiplication factor, k, is increased from 0.800 to 0.950, the amount of reactivity added is:

a.

0.150 k/k b.

0.197 k/k c.

0.250 k/k d.

0.297 k/k QUESTION A.18

[1.0 point])

Which ONE of the following is the principal source of heat in the reactor after a shutdown from extended operation at full power?

a.

Production of delayed neutrons b.

Subcritical reaction of photoneutrons c.

Spontaneous fission of Uranium-238 d.

Decay of fission fragments QUESTION A.19

[1.0 point]

Energy Yield (Q) from a nuclear fission reaction is in the range of (or is approximately):

a.

< 1 eV b.

1.86 keV c.

200 MeV d.

1000 MeV QUESTION A.20

[1.0 point]

Category A: Reactor Theory, Thermodynamics, and Facility Operating Characteristics Xenon-135 is formed directly by decay of __________?

a.

Iodine-135 b.

Cesium-135 c.

Barium-135 d.

Tellurium-135

(***** END OF CATEGORY A *****)

Category B: Normal/Emergency Operating Procedures and Radiological Controls QUESTION B.01

[1.0 point]

In an emergency, 10 CFR 50.54 allows reasonable action that departs from a license condition or a technical specification in an emergency when this action is immediately needed to protect the public health and safety. In this case, what is the minimum level of authorization or approved needed to depart from a license condition or technical specification?

a.

Licensed Senior Reactor Operator b.

Reactor Administrator c.

Chief Reactor Supervisor d.

Reactor Safety Advisory Committee QUESTION B.02

[1.0 point]

Per the UNM Emergency Plan, how frequently are licensed operators required to receive emergency training and drills?

a. Annually

b. Semi-Annually c.

Quarterly

d. Monthly QUESTION B.03

[1.0 point]

During a reactor operation, a small fire occurs in the control room console. Which ONE of the following classes of extinguisher would most likely be used with this type of fire?

a.

Class A: Fires in ordinary combustibles, such as wood, paper, plastic, etc b.

Class B: Fires in flammable or combustible liquids, flammable gases, greases

c. Class C: Fires in live electrical equipment d.

Class D: Fires involving combustible metals such as magnesium

Category B: Normal/Emergency Operating Procedures and Radiological Controls QUESTION B.04

[1.0 point]

A radiation survey of an area reveals a general radiation reading of 1 mRem/hr. However, an irradiated experiment sample (point source) is brought into the area that reads 10 mRem/hr at 1 meter. Which ONE of the following is the required posting for the area, in accordance with 10 CFR Part 20?

a. CAUTION - RADIATION AREA

b. CAUTION - HIGH RADIATION AREA c.

GRAVE DANGER - VERY HIGH RADIATION AREA

d. CAUTION - AIRBORNE RADIOACTIVITY AREA QUESTION B.05

[1.0 point, 0.25 each]

Match type of radiation (Column A) with the minimum shielding material needed (Column B)

Column A Column B

a. Gamma

1. Best shielded by 20 cm of lead

b. Beta

2. Stopped by 1 cm of aluminum or plastic and lead cladding

c. Alpha

3. Water, wax, or hydrogenous plastic

d. Neutron

4. Stopped by thin sheet of paper QUESTION B.06

[1.0 point]

In accordance with 10 CFR 20, what is the definition of Deep Dose Equivalent?

a.

The portion of the dose equivalent received from radiation sources outside the body b.

The portion of the dose equivalent received from radiative material taken into the body c.

The dose equivalent at a tissue depth of 100 cm d.

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 mrem

Category B: Normal/Emergency Operating Procedures and Radiological Controls QUESTION B.07 [1.0 point]

Which ONE of the following statements best states the MINIMUM staffing requirements when the reactor is NOT secured?

a.

1 RO and 1 SRO in the control room

b. 1 RO in the control room and 1 SRO licensee at the facility

c. 1 RO and a designated person capable of performing a reactor shutdown in the control room; 1 SRO on call; 1 HP on call

d. 1 SRO and a designated person capable of performing a reactor shutdown in the control room; 1 SRO on call; 1 HP on call.

QUESTION B.08

[1.0 point]

To prevent damage to the reactor or excessive release of radioactive materials in the event of an experiment failure, experiments containing corrosive materials shall:

a.

not be inserted into the reactor or stored at the facility b.

have a TEDE to any person occupying an unrestricted area in excess of 0.1 rem c.

be doubly encapsulated d.

be limited to less than 10 grams QUESTION B.09

[1.0 point]

All applicants for a RO or SRO license must submit NRC Form 396 and 398 to the U.S. NRC before taking the examinations. This requirement is specified in 10 Code of Federal Requirements (CFR):

a.

Part 19 b.

Part 20 c.

Part 55

d. Part 73

Category B: Normal/Emergency Operating Procedures and Radiological Controls QUESTION B.10

[2.0 points, 0.50 each]

Match the annual dose limit values (Column A) to the type of exposure (Column B). Answer in Column B can be used once, more than once, or not at all.

Type of Exposure Column A Annual Dose Limit Value Column B a.

Lens of the Eye 1.

0.1 rem b.

Extremities 2.

5.0 rem c.

Occupational Total Effective 3.

15 rem Dose Equivalent (TEDE) d.

TEDE to a member of 4.

50 rem the public QUESTION B.11

[1.0 point]

The dose rate from a mixed beta-gamma point source is 100 mrem/hour at a distance of 1 foot and is 0.1 mrem/hour at a distance of 10 feet. What percentage of the source consists of beta radiation?

a.

30%

b.

50%

c.

70%

d.

90%

QUESTION B.12

[1.0 point]

At UNM, who is the individual that shall supervise all reactor maintenance or modification that could affect the reactivity of the reactor?

a.

Reactor Operator b.

Reactor Supervisors c.

Reactor Administrator d.

Reactor Safety Advisory Committee

Category B: Normal/Emergency Operating Procedures and Radiological Controls QUESTION B.13

[1.0 point]

The safety rods and coarse control rod shall be interlocked such that at any operating power below __________, none of the rods can be moved to a more reactive position.

a.

5 watts b.

1 watt c.

50 x 10-5 watts d.

50 x 10-6 watts QUESTION B.14

[1.0 point]

During an emergency, who is responsible for supervising decontamination actions including the decontamination and/or preparation of contaminated injured personnel?

a.

Director of Emergency Operations (DEO) b.

Emergency Preparedness Coordinator (EPC) c.

Reactor Safety and Recovery Operations Coordinator (ROC) d.

Radiation Safety and Dose Assessment Coordinator (DAC)

QUESTION B.15

[1.0 point]

Which of ONE of the following would violate the Limiting Safety System Setting for the UNM?

a.

The shutdown margin is less than $1.00

b. Nuclear Safety Channel #2 exceeds 115% of licensed power c.

The average reactivity addition rate for each control rod exceeds 0.065%k/k per second d.

The polystyrene core thermal fuse melts when heated to a temperature of about 120oC resulting in core separation and a reactivity loss greater than 5%k/k QUESTION B.16

[1.0 point]

A two-curie radioactive source emitting 80% of 100 keV gamma is to be stored in the reactor building. How far from the source will it read 100 mrem/hr?

a.

3 feet b.

10 feet c.

13 feet d.

100 feet

Category B: Normal/Emergency Operating Procedures and Radiological Controls QUESTION B.17

[1.0 point]

In accordance with UNM Technical Specifications, temporary procedure changes which do NOT change the intent of the original procedure or involve a 10 CFR 50.59 review may be approved as a MINIMUM by the:

a.

Senior Reactor Operator b.

Chief Reactor Supervisor c.

Reactor Administrator and Reactor Safety Advisor Committee

d. Nuclear Regulatory Commission QUESTION B.18

[1.0 point]

Which ONE of the following is NOT considered a reportable event?

a.

During the reactor operation, a student inserted an experiment to cause a high-power scram.

b.

During the reactor operation, the operator found two rods can be inserted at the same time.

c.

During the reactor operation, the operator found a disagreement between expected and actual critical rod positions of 0.4% k/k.

d.

During the reactor training, a student allows the power drift up to the 6 watt limit, where a reactor scram occurs.

QUESTION B.19 [1.0 point]

According to the UNM Technical Specifications, which ONE of the following is the required interval for control rod scram times?

a.

Quarterly b.

Semi-annually c.

Annually d.

Biennially

(***** END OF CATEGORY B *****)

Category C: Facility and Radiation Monitoring Systems QUESTION C.01

[1.0 point]

Which power channel detector high voltage is automatically removed when a pre-selected power level is reached?

a. #1

b. #2

c. #3

d. Auxiliary QUESTION C.02

[1.0 point]

In accordance with UNM Technical Specifications, what is the minimum required worth of the cadmium rod?

a.

$3 b.

$5 c.

$7 d.

$10 QUESTION C.03

[1.0 point]

In accordance with UNM Technical Specifications, which ONE of the following statements is considered a Design Feature?

a. Shutdown Margin shall be at least $1.00

b. Control rod drop scram times shall be measured annually c.

Maximum core temperature shall not exceed 200oC during operation

d. Core, reflector and lead shielding are enclosed in and supported by a fluid tight steel reactor tank QUESTION C.04

[1.0 point]

At what water level drop does the shield water tank level trip?

a.

8 cm b.

12 cm c.

15 cm d.

18 cm

Category C: Facility and Radiation Monitoring Systems QUESTION C.05

[1.0 point]

Which of ONE of the following is the MAIN function of the high-density graphite surrounding the reactor core?

a.

to absorb fission product gases b.

to absorb thermal neutrons c.

to reduce neutron leakage d.

to reduce prompt gamma rays QUESTION C.06

[1.0 point]

The Low Power Interlock is controlled by power level indication from which channel?

a.

Auxiliary b.

Channel 1 c.

Channel 2 d.

Channel 3 QUESTION C.07

[1.0 point]

If the thermal fuse melts and the core separates, the reactor will shutdown due to a reactivity loss of greater than ___________.

a.

0.5 %k/k b.

1 %k/k c.

5 %k/k d.

10 %k/k QUESTION C.08

[1.0 point]

Which ONE of the following statements describes the design/operation of the control rod drive assemblies?

a.

fine control rod does not have a dashpot since it does not scram b.

dashpots consist of a foam cushion to reduce rod impact following a scram c.

coarse control rod dashpot uses magnetic force to slow the rod down before impact on a scram d.

dashpots are only associated with the safety rods since these rods have been raised against spring tension to assist in driving these rods down on a scram

Category C: Facility and Radiation Monitoring Systems QUESTION C.09

[1.0 point]

After the reactor Access Ports pass through the steel tank, what is the path?

a.

then the lead shield, the graphite reflector, the core, repeats in reserve and then back out b.

up to the graphite c.

then the lead shield and the graphite reflector

d. then the lead shield, the graphite reflector, repeats in reverse and then back out QUESTION C.10

[1.0 point]

What type of detectors are the remote area radiation monitors (general lab, reactor top, reactor console, checkpoint three)?

a.

Geiger-Mueller detectors b.

Ionization chambers c.

Scintillation detectors d.

Proportional counters QUESTION C.11

[1.0 point]

Which ONE control rod listed below will NOT instantaneously eject from the core in the event of a scram?

a.

Safety #1 b.

Fine c.

Coarse d.

Safety #2 QUESTION C.12

[1.0 point]

Which ONE of the following materials will have a positive effect on reactivity when inserted into the Glory Hole?

a.

Gold b.

Polyethylene c.

Natural Uranium d.

Borated Polyethylene

Category C: Facility and Radiation Monitoring Systems QUESTION C.13

[1.0 point]

What is the MAIN purpose of the thermal fuse?

a.

measure the temperature of fuel core b.

measure any gases released from the fuel core c.

separate the reactor core to prevent exceeding the Safety Limit (SL) d.

send a scram signal to the Nuclear Safety #2 if Limiting Safety System Setting (LSSS) is exceeded QUESTION C.14

[2.0 points, 0.50 each]

Identify each of the following values as either a Safety Limit (SL), a Limited Safety System Setting (LSSS) or a Limiting Condition for Operation (LCO).

a.

shall not exceed 0.065%k/k b.

excess reactivity shall not exceed 0.65%k/k c.

the maximum core temperature shall not exceed 200oC d.

polystyrene core thermal fuse melts when heated to a temperature of about 120oC QUESTION C.15

[1.0 point]

The water within the shield tank is designed to provide shielding from:

a.

High energy b.

High energy c.

Thermal neutrons

d. Fast neutrons QUESTION C.16

[1.0 point]

Which ONE of the following does NOT automatically cause deactivation of rod magnet current?

a.

shield water level >18 cm below highest manhole opening b.

radiation level c.

shield tank temperature <18oC d.

earthquake switch

Category C: Facility and Radiation Monitoring Systems QUESTION C.17

[1.0 point]

Which ONE of the following is the reaction of the Pu(Be) source?

a. (,n)

b. (,n) c.

(+)

d. (,)

QUESTION C.18

[1.0 point]

Which ONE of the following does the shield tank water temperature interlock prevent?

a. during periods of high thermal stress

b. from a reactivity addition due to a temperature decrease

c. in the event of a high temperature condition

d. during a condition that will produce excess radiation levels QUESTION C.19

[1.0 point]

Where is the Hold Station or the area you should proceed to, during an emergency evacuation due to a fire?

a. North of the Nuclear Engineering Laboratory Building b.

Office of the Reactor Supervisor c.

Reactor Control Room d.

Counting Laboratory

(***** END OF CATEGORY C *****)

((*************** END OF EXAM ****************))

Category A: Reactor Theory, Thermodynamics, & Facility Operating Characteristics A.01 Answer:

d

Reference:

Reactivity added = 0.140 % k/k = 0.00140 k/k

= (-)/eff = 0.0070 - 0.00140 = 40 seconds (0.1) (0.00140)

= (Keff1 - Keff2) / (Keff1

Keff2)

= (1.0000-0.9750) / (0.9750

1.0000)

= 0.0250 / 0.9750 = 0.0256 k/k A.10 Answer:

b

Reference:

Lamarsh 3rd ed., Section 3.6, pg. 68-71 Basic Nuclear Engineering 4th ed., Slowing Down of Neutrons, pg. 226-227

Reference:

DOE Fundamentals Handbook, Volume 1, Module 1, pg. 61 A.19 Answer:

c

Reference:

Lamarsh 3rd, Table 3.6, pg. 88 A.20 Answer:

a

Reference:

Burns, Volume 4, Figure 8.1, pg. 8-6 Chart of the Nuclides

(***** END OF CATEGORY A *****)

Category B: Normal/Emergency Operating Procedures and Radiological Controls B.01 Answer:

a

Reference:

10 CFR 50.54(y)

UNM Technical Specifications 3.3 B.16 Answer:

a

Reference:

6CEN = R/hr @ 1 ft. -> 6 x 2 x 0.8 x 0.1 = 0.96 R/hr at 1ft.

I0D02 = I*D2 0.96 R/hr*(1 ft) 2 = 0.1 R/hr *D 2 D= sqrt(0.96/0.1) = 3 ft.

B.17 Answer:

b

Reference:

UNM Technical Specifications 6.6 B.18 Answer:

b or d accepted

Reference:

UNM Operations Manual, pg. 32 B.19 Answer:

c

Reference:

UNM Technical Specifications 4.1

(***** END OF CATEGORY B *****)

NRC Previous Examination

b

Reference:

UNM Technical Specifications, 3.2 C.19 Answer:

a

Reference:

UNM Operations Manual, pg. 51

(***** END OF CATEGORY C *****)

(********** END OF EXAMINATION **********)

Person / Time
ML23079A230
Site:	University of New Mexico (R-102)
Issue date:	03/21/2023
From:	Travis Tate NRC/NRR/DANU/UNPO
To:	Willis C Univ of New Mexico, Nuclear Engineering Department
References
50-252/23-01 50-252/OL-23
Download: ML23079A230 (2)
v • d • e

ML23079A230

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Dear Carl Willis:

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