ML25216A181

Examination Report Letter No. 50-252/OL-26-01, University of New Mexico

ML25216A181
Person / Time
Site:	University of New Mexico (R-102)
Issue date:	03/12/2026
From:	Tony Brown NRC/NRR/DANU/UNPO
To:	Willis C Univ of New Mexico
Shared Package
50-252/OL-26	List: ML25216A181
References
50-252/26-01, 20260311-40009 50-252/OL-26
Download: ML25216A181 (0)

Text

Mr. 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-26-01, UNIVERSITY OF NEW MEXICO

Dear Mr. Willis:

During the week of January 19, 2026, the U.S. Nuclear Regulatory Commission (NRC) administered an operator licensing examination at your University of New Mexico research reactor. The examination was 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 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 Margaret Goodwin at (301) 415-1177, or via email at Margaret.Goodwin@nrc.gov.

Sincerely, Tony Brown, 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-26-01

2. Written examination cc: w/ enclosures to GovDelivery Subscribers March 12, 2026 Signed by Brown, Tony on 03/12/26

C. Willis 2

SUBJECT:

EXAMINATION REPORT NO. 50-252/OL-26-01, UNIVERSITY OF NEW MEXICO DATED: MARCH 12, 2026 DISTRIBUTION:

PUBLIC MReisi-Fard, NRR TBrown, NRR JRady, NRR EHelvenston, NRR AFarahmandfar, NRR MGoodwin, NRR AWaugh, NRR NJones, NRR RAlexander, RGN-IV ADAMS Accession Numbers:

Pkg: ML25216A158 Report: ML25216A181 e-Concurrence case: 20260311-40009 NRR-079 U. S. NUCLEAR REGULATORY COMMISSION OPERATOR LICENSING INITIAL EXAMINATION REPORT REPORT NO.:

OL-XX-XX FACILITY DOCKET NO.:

50-252 FACILITY LICENSE NO.:

R-102 FACILITY:

University of New Mexico EXAMINATION DATE(S):

Week of January 19, 2026 SUBMITTED BY:

SUMMARY

During the week of January 19, 2026, the NRC administered operator licensing examinations to four Reactor Operator (RO) candidates. One RO candidate failed Categories A and B and was an overall written examination failure but passed the operating test. One RO candidate failed Category C of the written examination but passed the operating test. All remaining RO candidates passed all applicable portions of the examinations and tests.

REPORT DETAILS 1.

Examiner:

Margaret N. Goodwin, Chief Examiner, NRC 2.

Results:

RO PASS/FAIL SRO PASS/FAIL TOTAL PASS/FAIL Written 2/2 N/A 2/2 Operating Tests 4/0 N/A 4/0 Overall 2/2 N/A 2/2 3.

Exit Meeting:

Carl Willis, Chief Reactor Supervisor, University of New Mexico Rowdy Davis, Reactor Administrator, University of New Mexico Margaret N. Goodwin, 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. The NRC examiner discussed some apparent weaknesses among the expected level of knowledge for RO candidates. Examiner observations include: weakness in Administrative Topics, including federal radiation dose limits and Technical Margaret N. Goodwin November 5, 2023 Margaret N. Goodwin, Chief Examiner Date

2 Specification Safety Limit and Limiting Safety System Settings. The NRC examiner also noted weakness regarding facility temperature detectors and the neutron source. Additionally, the NRC examiner provided feedback to facility regarding an apparent gap in candidate training on personal dosimetry. 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 19, 2026

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

University of New Mexico REACTOR TYPE:

AGN DATE ADMINISTERED:

01/22/2026 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 and a 70% overall are required to pass the examination. Examinations will be picked up three (3) hours after the examination starts.

CATEGORY VALUE

% OF TOTAL CANDIDATE'S SCORE

% OF CATEGORY VALUE CATEGORY 20.00 33.0 A. REACTOR THEORY, THERMODYNAMICS, AND FACILITY OPERATING CHARACTERISTICS 20.00 33.0 B. NORMAL AND EMERGENCY OPERATING PROCEDURES AND RADIOLOGICAL CONTROLS 20.00 33.0 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

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 and a 70 percent or greater overall.

12.

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

Candidate Name: ___________________________

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

If you change your answer, write your selection on the line. Answers written on the line will be taken as the final answer.

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 *****)

Candidate Name: ___________________________

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

If you change your answer, write your selection on the line. Answers written on the line will be taken as the final answer.

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 ___

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 ___

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 ___

B20 a b c d ___

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

Candidate Name: ___________________________

Category C: Plant and Radiation Monitoring Systems A N S W E R S H E E T Multiple Choice (Circle your choice, or write on the line)

If you change your answer, write your selection on the line. Answers written on the line will be taken as the final answer.

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 ___

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 ___

C20 a b c d ___

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

(********** END OF 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

T UA H

m T

c m

Q P

sec 10 1

4

2 1

1 1

2 1

eff eff K

CR K

CR

eff SUR 06 26

te P

P 0

eff K

S S

SCR

1

2 2

1 1

CR CR

0 1

P P

1 2

1 1

CR CR K

M eff

)

(

0 10 t

SUR P

P 2

1 1

1 eff eff K

K M

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

2 2

2 2

1 1

d DR d

DR

t e

DR DR

0

1 2

1 2

2 2

Peak Peak

2 6

R n

E Ci DR

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

[1.00 point] No Correct Answer With respect to subcritical multiplication, which ONE of the following statements is TRUE?

a. Criticality is achieved when the value of M reaches zero (0).

b. It can be used to calculate the neutron population in a critical reactor.

c.

It can be used to calculate the neutron count following reactivity additions independently of the initial Keff.

d. The initial neutron source count can be calculated using the original Keff and the new Keff only.

QUESTION A.02

[1.00 point]

Which ONE of the following statements best describes reactivity?

a. The change in Keff resulting from changing a core parameter.

b. The maximum power that can be achieved by inserting all control and safety rods.

c.

The difference between the initial and current effective multiplication factor.

d. The measurement of a reactors departure from criticality.

QUESTION A.03

[1.00 point]

Which ONE of the following statements best describes a fissile isotope?

a. An isotope that ordinarily generates a greater than average number of neutrons per fission.

b.

An isotope that can generate other similarly fissile isotopes.

c.

An isotope that requires a high energy neutron to fission.

d.

An isotope that can fission with a zero-energy neutron.

QUESTION A.04

[1.00 point]

If it takes 38 seconds for reactor power to increase from 60 mW to 4.8 W, what is the reactor period?

a.

0.1s b.

3.3s c.

8.7s d.

12.2s

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

[1.00 point]

Which ONE of the following delayed neutron precursors results in the greatest negative period following a reactor scram?

a.

Bromine-87 (T1/2 = 55.5s) b.

Iodine-137 (T1/2 = 22.7s) c.

Rubidium-93 (T1/2 =5.8s) d.

Xenon-143 (T1/2 = 0.5s)

QUESTION A.06

[1.00 point]

Which ONE of the following statements best describes INELASTIC SCATTERING?

a.

A neutron is captured by a nucleus and the nucleus emits all forms of radiation to reach ground state.

b.

A neutron enters a nucleus, imparts kinetic energy and leaves the nucleus in ground state.

c.

A neutron enters a nucleus, imparts kinetic energy and the nucleus decays via gamma emission to return to the ground state.

d.

A neutron is absorbed by a nucleus leaving it in an excited state.

QUESTION A.07

[1.00 point]

Which ONE of the following factors in the Six Factor Formula is the number of fast fission neutrons produced per thermal neutron absorbed by fuel?

a.

Thermal Utilization Factor b.

Reproduction Factor c.

Fast Fission Factor d.

Resonance Escape Probability QUESTION A.08

[1.00 point]

Which ONE of the following isotopes is MOST likely to undergo a fission interaction with a THERMAL NEUTRON?

a.

Uranium-233 ( = 527 barns) b.

Uranium-235 ( = 577 barns) c.

Plutonium-239 ( = 742 barns) d.

Plutonium-241 ( = 1025 barns

Category A: Reactor Theory, Thermodynamics, and Facility Operating Characteristics QUESTION A.09

[1.00 point]

In a fresh POISON control rod in a core with a normal flux distribution, where is differential reactivity worth GREATEST?

a.

At the top and bottom of the rod.

b.

The differential rod worth is uniform across the control rod.

c.

In the middle of the control rod.

d.

The location of greatest reactivity worth is dependent on its location within the core.

QUESTION A.10

[1.00 point]

If Keff is 0.972 with a count rate of 456 cps, what count rate would result in a Keff of 0.998 a.

2689 b.

3144 c.

4571 d.

6384 QUESTION A.11

[1.00 point]

Which ONE of the following would require the WITHDRAWAL of POISON control rods to maintain a steady reactor power?

a.

Xe-135 burn up while operating.

b.

Replacing the water filled core positions with graphite reflector elements.

c.

Decreasing the temperature of the fuel.

d.

Uranium-235 burn up in the fuel.

QUESTION A.12

[1.00 point]

All of the following will impact the probability of a neutron interacting with a nucleus EXCEPT:

a.

The source of the neutron.

b.

The energy of the neutron.

c.

The type of interaction occurring.

d.

The size and type of the nucleus.

Category A: Reactor Theory, Thermodynamics, and Facility Operating Characteristics QUESTION A.13

[1.00 point]

Which ONE of the following types of neutrons has a core lifetime of approximately 5 x10-5s?

a.

Delayed neutrons b.

Prompt neutrons c.

Thermal neutrons d.

Resonance neutrons QUESTION A.14

[1.00 point]

What reactivity addition is required to increase Keff from 0.861 to 0.942?

a.

0.079 b.

0.088 c.

0.099 d.

1.003 QUESTION A.15

[1.00 point]

Which ONE of the following is an example of alpha decay?

a.

94Pu239 92U235 b.

94Pu239 93Np239 c.

94Pu239 94Pu238 d.

94Pu239 95Am239 QUESTION A.16

[1.00 point]

Which ONE of the following is the phenomenon where the resonance peaks of the neutron absorption cross section increase in width due to thermal motion of the nuclei?

a.

Moderator Negative Temperature Coefficient b.

Mass Defect c.

Doppler Broadening d.

Spectrum Hardening

Category A: Reactor Theory, Thermodynamics, and Facility Operating Characteristics QUESTION A.17

[1.00 point]

Xenon-135 in a core generally ____________ immediately after shutdown due to decay of a.

Increases; Iodine-135 b.

Increases; Cesium-135 c.

Decreases; Xenon-135 d.

Decreases; Tellurium-135 QUESTION A.18

[1.00 point]

The amount of negative reactivity added to a reactor operating with a critical, cold, clean core by inserting the control rods is referred to as the:

a.

Prompt jump b.

Shutdown Margin c.

Core Excess d.

Peak Pulse Power QUESTION A.19

[1.00 point]

What would reactor power be if a reactivity of 0.0078 were added while the reactor was operating at 50 W with a eff of 0.0083?

a.

432 W b.

529 W c.

786 W d.

824 W QUESTION A.20

[1.00 point]

All of the following are characteristics of an effective neutron moderator EXCEPT:

a.

Large neutron energy loss per collision.

b.

Low neutron absorption cross section.

c.

Large neutron scattering cross section.

d.

Low atomic density.

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

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

[1.00 point]

Which ONE of the following scenarios would result in a radiation dose exceeding the 10 CFR 20 limits for occupational workers?

a.

Handling a freshly irradiated experiment emitting an extremity dose rate of 400 rem/hr for 6 minutes.

b.

Accidentally dropping a radioactive powder that gives a radiation dose of 10 rem to the lens of the eye.

c.

Inhaling fission product gases during a release resulting in a radiation dose of 55 rem to the lungs.

d.

Performing work in a radiation area that takes approximately 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> to complete.

QUESTION B.02

[1.00 point]

In accordance with the University of New Mexico AGN Emergency Plan, which ONE of the following would require a facility evacuation?

a.

Notification of an incoming tornado to the facility.

b.

A civil disturbance outside of the facility.

c.

Effluent concentrations within the operations boundary that would result in a Committed Effective Dose of 10 mrem within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

d.

A radiation dose rate at the console in excess of 100 mR/hr.

QUESTION B.03

[1.00 point]

Which ONE of the following experiments would be permissible?

a.

An experiment with a reactivity worth of 0.42%K/K.

b.

An experiment containing explosive material that is doubly encapsulated.

c.

An experiment containing radioactive effluents that upon release would result in a radiation dose of 50 mrem to personnel.

d.

An experiment containing Uranium-235 suspended in a liquid that is singly encapsulated.

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

[1.00 point] 2 correct answers Which ONE of the following MUST be performed prior to every reactor startup?

a.

A channel check of Nuclear Safety Channels #2 and #3.

b.

A visual inspection of the shield tank.

c.

Verification of the operability of the manual scram function.

d.

Verification of the reactor access control.

QUESTION B.05

[1.00 point]

A sample of radioactive Argon-41 is removed from the reactor with a half-life of 1.83 hours9.606481e-4 days <br />0.0231 hours <br />1.372354e-4 weeks <br />3.15815e-5 months <br />.

What is the decay constant?

a.

0.38 h-1 b.

0.56 h-1 c.

0.76 h-1 d.

0.92 h-1 QUESTION B.06

[1.00 point]

In accordance with the Reactor Operating and Training Manual, all of the following may be performed by a Reactor Assistant EXCEPT:

a.

Assist in the withdrawal and insertion of the fine control rod.

b.

Removal of the Cadmium Rod prior to Reactor Startup.

c.

Initiate a manual reactor scram.

d.

Help maintain a record of reactor operations in the operational log.

QUESTION B.07

[1.00 point]

In accordance with the Reactor Operating and Training Manual, all of the following are considered ROUTINE OPERATIONS EXCEPT:

a.

Reactor operations following repair of the coarse control rod.

b.

Approved operations for the Reactor Laboratory Class.

c.

Operations where criticality is achieved by adding experiments containing Uranium-235.

d.

Operations where an unapproved experiment is performed.

Category B: Normal/Emergency Operating Procedures and Radiological Controls QUESTION B.08

[1.00 point]

If an experiment is emitting a dose rate of 5mrem/hr at a distance of 75 cm, what is the dose rate measured at 15 cm?

a.

25 mrem/hr b.

75 mrem/hr c.

100 mrem/hr d.

125 mrem/hr QUESTION B.09

[1.00 point]

In accordance with the UNM Emergency Plan, which ONE of the following actions must be taken for personnel who are potentially contaminated?

a.

They should immediately evacuate to the decontamination area in room 081.

b.

Personnel are checked for contamination while evacuating and no further action is needed.

c.

Potentially contaminated personnel are to remain separated at the Hold Station.

d.

All personnel are presumed contaminated while evacuating and undergo cursory decontamination.

QUESTION B.10

[1.00 point]

In accordance with the UNM Technical Specifications, which ONE of the following is a CHANNEL CALIBRATION?

a.

Verifying that the Nuclear Safety Channel #3 scrams at a power of 6 Watts.

b.

Adjusting the safety rod scram time so it falls in 0.5s instead of 1.2s.

c.

Introducing a radioactive source to the fission chamber to verify operability.

d.

Changing the radioactive source used to verify the operability of the Remote Area Monitors.

Category B: Normal/Emergency Operating Procedures and Radiological Controls QUESTION B.11

[1.00 points total; 0.25 points each]

In accordance with the UNM Technical Specifications, identify each of the following as either a Safety Limit (SL), and Limiting Safety System Setting (LSSS), or a Limiting Condition of Operation (LCO).

a.

The polystyrene core fuse shall melt at 120oC.

b.

The maximum core temperature shall not exceed 200oC.

c.

The excess reactivity with no experiments in the core and with all safety rods, coarse control rod, and fine control rod fully inserted shall not exceed 0.25%K/K.

d.

The safety channels shall initiate a reactor scram at a power of 6 watts.

QUESTION B.12

[1.00 point]

In accordance with the UNM Shut-down Procedure, which ONE of the following is ONLY performed for an Unintentional Shut-down?

a.

Determination of the reason for the shut-down.

b.

Depressing the manual scram button.

c.

Verification that all 4 control rods have been withdrawn.

d.

Removing the key from the key switch.

QUESTION B.13

[1.00 point]

Given the following, calculate the shutdown margin and determine if it is within the Technical Specification limit.

Control Rod Total Reactivity Worth Excess Reactivity Safety Rod #1

$3.02

$0.00 Safety Rod #2

$2.89

$0.00 Coarse Control Rod

$1.16

$1.05 Fine Control Rod

$0.74

$0.41 a.

$1.46; the Shutdown Margin is within the Technical Specification Limit b.

$1.46; the Shutdown Margin VIOLATES the Technical Specification Limit c.

$6.35; the Shutdown Margin is within the Technical Specification Limit d.

$6.35; the Shutdown Margin VIOLATES the Technical Specification Limit

Category B: Normal/Emergency Operating Procedures and Radiological Controls QUESTION B.14

[1.00 point]

In accordance with the UNM Reactor Operating and Training Manual, which ONE of the following statements best describes the power calibration?

a.

The change in power due to the insertion of the gold and cadmium foils is proportional to the operating power.

b.

The operational data of the UNM AGN reactor is sufficient to verify the proper calibration of the nuclear safety channels.

c.

The change in temperature and mass of the gold and cadmium foils is proportional to the reactor power.

d.

The activation of the gold and cadmium foils is proportional to reactor power.

QUESTION B.15

[1.00 point]

In accordance with the UNM Reactor Operating and Training Manual, all of the following locations require a radiation survey prior to startup EXCEPT:

a.

Reactor Top b.

Access Ports c.

Glory Hole d.

Reactor Console QUESTION B.16

[1.00 point]

In accordance with the UNM Emergency Plan, the Emergency Planning Zone (EPZ) is the:

a.

The area where the Director of Emergency Operations can initiate emergency activities.

b.

The area where organizing is done to assure prompt and effective actions are taken to protect the public in the event of an incident.

c.

The area where the Director of Emergency of Operations has complete and total authority over all activities.

d.

An area where access is limited to protect individuals from exposure to radiation or radioactive materials in the event of an emergency.

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

[1.00 point]

In accordance with the UNM Reactor Operating and Training Manual, all of the following must be reported to the Chief Reactor Supervisor EXCEPT:

a.

Higher than normal radiation near the Reactor Shield Access Doors.

b.

Water on the ground near access ports.

c.

Discovery that the safety trips were not reset from the previous reactor run.

d.

Discovery that the Man Hole Cover is unlocked.

QUESTION B.18

[1.00 point]

In accordance with the UNM Technical Specifications, the thermal column can be filled with any of the following EXCEPT:

a.

Air b.

Graphite c.

Water d.

Lead QUESTION B.19

[1.00 point]

In accordance with the UNM Technical Specifications, all of the following are required to be completed, at a minimum, annually EXCEPT:

a.

Determination of control rod reactivity worths.

b.

Verification that a loss of facility power initiates a scram.

c.

A radiation survey of the reactor room.

d.

Verification of the rod interlock operability.

Category B: Normal/Emergency Operating Procedures and Radiological Controls QUESTION B.20

[1.00 point]

In accordance with the Reactor Operating and Training Manual, which ONE of the following requires authorization from the Chief Reactor Supervisor and the Reactor Safety Advisory Committee:

a.

Permission to install a new experiment in one of the access ports.

b.

Permission for an Authorized Operator to manipulate the controls.

c.

Permission to obtain the console keys.

d.

Permission to perform a reactor start-up and shut-down.

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

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

[1.00 point]

In accordance with the UNM Technical Specifications, the reactor top must be locked to prevent:

a.

Unapproved access to nuclear material.

b.

Unapproved access to a High Radiation Area.

c.

Unapproved manual reactivity manipulations.

d.

Unapproved exposure to hazardous materials.

QUESTION C.02

[1.00 point]

All of the following statements regarding the control rods are TRUE EXCEPT:

a.

All four control rods must be withdrawn from the core before a reactor start-up can be performed.

b.

Only one safety rod can be inserted at a time.

c.

Only the carrier positions of the fine and coarse control rod need to be displayed on the console.

d.

Both safety rods must be inserted before the coarse control rod can be moved into the core.

QUESTION C.03

[1.00 point]

In accordance with the UNM Technical Specifications, which ONE of the following scenarios would prevent a reactor start-up?

a.

A console power indication of 50 x 10-4 watts.

b.

A shield water temperature of 20oC.

c.

A loss of 20cm of water in the shield tank.

d.

An earthquake that results in no displacement.

Category C: Facility and Radiation Monitoring Systems QUESTION C.04

[1.00 point]

Which ONE of the following BEST describes the purpose of the polystyrene core fuse?

a.

It provides sufficient moderation through the use of low atomic number materials to maintain subcriticality.

b.

It melts at temperatures at or below 100oC to prevent the inadvertent violation of the safety limit.

c.

The polystyrene acts as a reflector to help slow down fast neutrons to maintain sufficient reactivity is available.

d.

It acts as a neutron shield to keep the dose rate in the reactor bay as low as reasonably achievable.

QUESTION C.05

[1.00 point]

Which ONE of the following core structures provides access to the core tank?

a.

The removable thermal column.

b.

The access ports.

c.

The reactor shield doors.

d.

The reactor shield tank manhole opening.

QUESTION C.06

[1.00 point]

In accordance with the UNM Technical Specifications, which ONE of the following statements best describes the purpose of the Safety Limit?

a.

To maintain the safety of the public and occupational workers.

b.

To prevent the overpower of the reactor by scramming the control rods.

c.

To prevent the violation of the facility Technical Specification limits.

d.

To maintain the integrity of the core and retain fission products.

Category C: Facility and Radiation Monitoring Systems QUESTION C.07

[1.00 point]

In accordance with the UNM Safety Analysis Report (SAR), all standard loadings are designed to fall within the limits on what reactor parameter?

a.

Reactivity Insertion Rate b.

Shutdown Margin c.

Total Core Reactivity d.

Core Excess QUESTION C.08

[1.00 point]

In accordance with the UNM SAR, during reactor operations, where are most fission products located?

a.

Within the polyethylene fuel disks.

b.

Within the core tank.

c.

Within the fuel particles.

d.

Within the concrete reactor shielding.

QUESTION C.09

[1.00 point]

During the maximum hypothetical accident, what is the peak temperature RISE the reactor will experience?

a.

75oC b.

100oC c.

150oC d.

200oC QUESTION C.10

[1.00 point]

During steady-state reactor operations at 4 watts, where is the radiation dose rate the highest?

a.

The north wall of the reactor b.

The side of the reactor tank shield c.

The glory hole access port d.

The reactor top

Category C: Facility and Radiation Monitoring Systems QUESTION C.11

[1.00 point]

Which ONE of the following statements best describes the purpose of the water in the reactor shield tank?

a.

It is designed to stop fast neutrons.

b.

It is designed to trap fission product gases.

c.

It is designed to maintain adequate core temperatures.

d.

It is designed to shield personnel from high energy betas.

QUESTION C.12

[1.00 point]

In accordance with the UNM Technical Specifications, when storing fuel, Keff must be kept below:

a.

0.80 b.

0.85 c.

0.90 d.

0.95 QUESTION C.13

[1.00 point]

Which ONE of the following materials is used to shield against gammas that are emitted from the core?

a.

Concrete b.

Lead c.

Water d.

Graphite QUESTION C.14

[1.00 point]

Which ONE of the following components is required for reactor operations?

a.

Auxiliary Power Channel b.

Fission Chamber c.

2 Ci Pu-Be Source d.

A portable radiation monitor

Category C: Facility and Radiation Monitoring Systems QUESTION C.15

[1.00 point]

Which ONE of the following statements BEST describes the fail-safe function of the control rods?

a.

The loss of any one control rod provides sufficient negative reactivity to put the reactor in a subcritical condition.

b.

The automatic scram function ensures no human intervention is necessary to place the reactor in a safe condition.

c.

The control rods excluding the fine control rod fall out due to gravity alone when magnet energy is lost for any reason.

d.

The total reactivity worth of all control rods is kept low enough to prevent the potential for violating the Safety Limit.

QUESTION C.16

[1.00 point]

Which ONE of the following would require the reactor operator to immediately scram the reactor?

a.

Loss of the Reactor Top Remote Area Monitor.

b.

Loss of the console Fine Control Rod position.

c.

Loss of the console shield water temperature display.

d.

Discovery that the coarse control rod reactivity insertion rate is 0.05%k/k/s QUESTION C.17

[1.00 point]

Which ONE of the following characteristics is uniform for ALL control rods used in the UNM AGN reactor?

a.

All control rods add positive reactivity to the core when inserted.

b.

All control rods can move at slow and fast speeds.

c.

All control rods scram at a speed of approximately 200 ms.

d.

All control rods contain the same amount of Uranium-235.

Category C: Facility and Radiation Monitoring Systems QUESTION C.18

[1.00 point]

Which ONE of the following best describes the purpose of the polyethylene used in the fuel disks?

a.

To act as a fast neutron shield.

b.

To act as a neutron moderator.

c.

To act as a neutron reflector.

d.

To act as a solid fuel support.

QUESTION C.19

[1.00 point]

Which ONE of the following colored light combinations would be illuminated if the two Safety Rods were fully inserted and the coarse and fine control rods were only partially inserted?

a.

Yellow-Green-Red b.

Red and Yellow Only c.

Green and Yellow Only d.

Green Only QUESTION C.20

[1.00 point]

Where is the location of the highest temperatures within the core?

a.

The topmost fuel disk.

b.

The glory hole and access ports.

c.

The thermal fuse.

d.

The coarse control rod.

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

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

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

b no correct answer

Reference:

DOE Fundamentals Handbook Nuclear Physics and Reactor Theory Vol. 2 Module 4 p.9 A.02 Answer:

d

Reference:

DOE Fundamentals Handbook Nuclear Physics and Reactor Theory Vol. 2 Module 3 p.18 A.03 Answer:

d

Reference:

R. R. Burn, Introduction to Nuclear Reactor Operations, Vol 2. p. 3-2 A.04 Answer:

c

Reference:

= 0

0 =

0 =

=

0

=

38 4800 60 = 8.6717 ~ 8.7 A.05 Answer:

a

Reference:

DOE Fundamentals Handbook Nuclear Physics and Reactor Theory Vol.

2 Module 4 p.32 A.06 Answer:

c

Reference:

R. R. Burn, Introduction to Nuclear Reactor Operations, Vol 1. p. 2-28 A.07 Answer:

b

Reference:

R. R. Burn, Introduction to Nuclear Reactor Operations, Vol 2. p. 3-16 A.08 Answer:

d

Reference:

R. R. Burn, Introduction to Nuclear Reactor Operations, Vol 1. p. 2-59 A.09 Answer:

c

Reference:

R. R. Burn, Introduction to Nuclear Reactor Operations, Vol 4. p. 7-4

Category A: Reactor Theory, Thermodynamics, and Facility Operating Characteristics A.10 Answer:

d

Reference:

1(1 1) = 2(1 2) 2 = 1 (1 1)

(1 2) 2 = 456 0.028 0.002

= 6384 A.11 Answer:

d

Reference:

R. R. Burn, Introduction to Nuclear Reactor Operations, Vol 2. p. 3-18 A.12 Answer:

a

Reference:

DOE Fundamentals Handbook Nuclear Physics and Reactor Theory Vol. 1 Module 2 p.7 A.13 Answer:

b

Reference:

DOE Fundamentals Handbook Nuclear Physics and Reactor Theory Vol. 1 Module 2 p.32 A.14 Answer:

c

Reference:

=

2 1 1 2

=

0.942 0.861 0.861 0.942 = 0.099 A.15 Answer:

a

Reference:

Chart of the Nuclides A.16 Answer:

c

Reference:

DOE Fundamentals Handbook Nuclear Physics and Reactor Theory Vol. 2 Module 3 p.4 A.17 Answer:

a

Reference:

DOE Fundamentals Handbook Nuclear Physics and Reactor Theory Vol. 2 Module 3 p.38 A.18 Answer:

b

Reference:

R. R. Burn, Introduction to Nuclear Reactor Operations, Vol 3. p. 6-4

Category A: Reactor Theory, Thermodynamics, and Facility Operating Characteristics A.19 Answer:

d

Reference:

=

(1 )

0

=

0.0083 (1 0.0078) 0.0083 0.0078 50 P = 824 W A.20 Answer:

d

Reference:

DOE Fundamentals Handbook Nuclear Physics and Reactor Theory Vol. 2 Module 3 p.24

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

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

c

Reference:

10 CFR 20 B.02 Answer:

d

Reference:

UNM Emergency Plan 7.3.2 B.03 Answer:

c

Reference:

UNM Technical Specifications 3.3 B.04 Answer:

a and b

Reference:

UNM Technical Specifications 4.3 B.05 Answer:

a

Reference:

=

ln (2) 1/2

=

ln (2) 1.83 = 0.379 = 0.38 h-1 B.06 Answer:

a

Reference:

UNM Reactor Operating and Training Manual p. 19 B.07 Answer:

d

Reference:

UNM Reactor Operating and Training Manual p. 23 B.08 Answer:

d

Reference:

1 2 1 = 22 2

2 =

1 2 1

2 2

2 = 5 752 152 = 125 mrem/hr B.09 Answer:

c

Reference:

UNM Emergency Plan 7.3.2 B.10 Answer:

b

Reference:

UNM Technical Specifications 1.1.2 B.11 Answer:

a: LSSS b: SL c: LSSS d: LCO

Reference:

UNM Technical Specifications 2.1, 2,2, and 3.1

Category B: Normal/Emergency Operating Procedures and Radiological Controls B.12 Answer:

a

Reference:

UNM Reactor Operating and Training Manual p. 33 B.13 Answer:

c

Reference:

SDM = TRW - ER SDM = (3.02+2.89+1.16+0.74) - (1.05+0.41)

SDM = $6.35 which is within the limit stated in TS 3.1 B.14 Answer:

d

Reference:

UNM Reactor Operating and Training Manual p. 34 B.15 Answer:

d

Reference:

UNM Reactor Operating and Training Manual p. 26 B.16 Answer:

b

Reference:

UNM Emergency Plan 2.4 B.17 Answer:

c

Reference:

UNM Reactor Operating and Training Manual pgs. 25-28 B.18 Answer:

d

Reference:

UNM Technical Specifications 3.4 B.19 Answer:

d

Reference:

UNM Technical Specifications 4.2 B.20 Answer:

a

Reference:

UNM Reactor Operating and Training Manual pgs. 21-22

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

C.01 Answer:

b

Reference:

UNM Technical Specifications 3.4 C.02 Answer:

a

Reference:

UNM Technical Specifications 3.2 C.03 Answer:

c

Reference:

UNM Technical Specifications 3.2 C.04 Answer:

b

Reference:

UNM SAR p.4 C.05 Answer:

a

Reference:

UNM SAR p.7 C.06 Answer:

d

Reference:

UNM Technical Specifications 2.1 C.07 Answer:

d

Reference:

UNM SAR p.8 C.08 Answer:

c

Reference:

UNM SAR p.34 C.09 Answer:

b

Reference:

UNM SAR p.43 C.10 Answer:

d

Reference:

UNM SAR Figure 19 C.11 Answer:

a

Reference:

UNM Technical Specifications 5.1 C.12 Answer:

c

Reference:

UNM Technical Specifications 5.2 C.13 Answer:

b

Reference:

UNM Technical Specifications 5.1

C.14 Answer:

d

Reference:

UNM Technical Specifications 3.4 C.15 Answer:

c

Reference:

UNM SAR p.12 C.16 Answer:

b

Reference:

UNM Technical Specifications 3.2 C.17 Answer:

a

Reference:

UNM SAR p.9 C.18 Answer:

b

Reference:

UNM SAR p.4 C.19 Answer:

b

Reference:

UNM SAR p.12 C.20 Answer:

c

Reference:

UNM SAR p.4

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

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