Text

Initial Examination Report, No. 50-166/OL-10-01, University of Maryland
	ML102230464
Person / Time
Site:	University of Maryland
Issue date:	08/31/2010
From:	Johnny H. Eads; Research and Test Reactors Branch B
To:	Al-Sheikhly M; Univ of Maryland - College Park
	Schoenebeck G, NRR/DPR, 415-6345
References
	50-166/OL-10-01
	Download: ML102230464 (52)
	v • d • e

ENCLOSURE 1 August 31, 2010 Dr. Mohamad Al-Sheikhly, Director Radiation Facilities and Nuclear Reactor Department of Materials Science and Engineering 2309D Chemical and Nuclear Engineering Building Building 090, Stadium Drive The University of Maryland College Park, MD 20742-2115

Dear Dr. Al-Sheikhly:

During the week of July 19, 2010, the NRC administered an operator licensing examination at the Maryland University Training 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 (PARS) component of NRC's 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 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 Patrick Isaac at 301-415-1019 or via internet e-mail Patrick.Isaac@nrc.gov.

Sincerely,

/RA/ Johnny H. Eads, Jr., Chief Research and Test Reactors Oversight Branch Division of Policy and Rulemaking Office of Nuclear Reactor Regulation

Docket No. 50-166

Enclosures:

1. Initial Examination Report No. 50-166/OL-10-01

2. Facility Comments with NRC Resolution

3. Written examination with facility comments incorporated

cc without enclosures: See next page

August 31, 2010 Dr. Mohamad Al-Sheikhly, Director Radiation Facilities and Nuclear Reactor Department of Materials Science and Engineering 2309D Chemical and Nuclear Engineering Building Building 090, Stadium Drive The University of Maryland College Park, MD 20742-2115

Dear Dr. Al-Sheikhly:

During the week of July 19, 2010, the NRC administered an operator licensing examination at the Maryland University Training 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 (PARS) component of NRC's 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 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 Patrick Isaac at 301-415-1019 or via internet e-mail Patrick.Isaac@nrc.gov.

Sincerely,

/RA/ Johnny H. Eads, Jr., Chief Research and Test Reactors Oversight Branch Division of Policy and Rulemaking Office of Nuclear Reactor Regulation

Docket No. 50-166

Enclosures:

1. Initial Examination Report No. 50-166/OL-10-01 2. Facility Comments with NRC Resolution

3. Written examination with facility comments incorporated cc without enclosures: See next page

DISTRIBUTION w/ encls.: PUBLIC PROB r/f RidsNRRDPRPRLB RidsNRRDPRPROB Facility File (CRevelle) O7 G13 ADAMS ACCESSION #: ML102230464 TEMPLATE #:NRR-074 OFFICE PROB:CE IOLB:LA E PROB:SC NAME PIsaac CRevelle JEads DATE 8/25/2010 8/26/2010 8/31/2010 OFFICIAL RECORD COPY

University of Maryland Docket No. 50-166 cc: Director, Dept. of Natural Resources Power Plant Siting Program Energy & Coastal Zone Administration Tawes State Office Building Annapolis, MD 21401 Mr. Roland Fletcher, Director Center for Radiological Health Maryland Department of Environment 201 West Preston Street 7 th Floor Mail Room Baltimore, MD 21201 Mr. Vincent G. Adams Facility Coordinator Chemical and Nuclear Engineering Building 090 University of Maryland College Park, MD 20742

Maureen M. Kotlas, Director Department of Environmental Safety 3115 Chesapeake Building 338 University of Maryland College Park, MD 20742

Test, Research, and Training Reactor Newsletter University of Florida 202 Nuclear Sciences Center University of Florida Gainesville, FL 32611 ENCLOSURE 1 U. S. NUCLEAR REGULATORY COMMISSION OPERATOR LICENSING INITIAL EXAMINATION REPORT

REPORT NO.: 50-166/OL-10-01

FACILITY DOCKET NO.: 50-166

FACILITY LICENSE NO.: R-70

FACILITY: University of Maryland

EXAMINATION DATES: July 22-23, 2010

SUBMITTED BY: ___________/RA/ ______ __8/25/10_

Patrick Isaac, Chief Examiner Date

SUMMARY

During the week of July 19, 2010, the NRC administered operator licensing examinations to three Reactor Operator candidates at the Maryland University Training Reactor. One candidate passed the license examination and has been issued, a license. Two candidates, failed Section A of the written examination.

REPORT DETAILS

1. Examiners:

Gregory Schoenebeck, NRC, Examiner (In Training) Patrick Isaac, NRC, Chief Examiner

2. Results:

RO PASS/FAILSRO PASS/FAILTOTAL PASS/FAIL Written 1/2 N/

A1/2 Operating Tests3/0 N/

A3/0 Overall 1/2 N/

A1/2 3. Exit Meeting:

Gregory Schoenebeck, NRC, Examiner (In Training) Patrick Isaac, NRC, Chief Examiner Vincent G. Adams, Facility Coordinator The NRC examiner thanked the facility staff for their prompt submission of written examination comments (enclosure 2).

ENCLOSURE 2 FACILITY COMMENTS ON THE WRITTEN EXAM WITH NRC RESOLUTION Question B.4 Comment: Answer key was incorrect; correct answer was b. NRC Resolution: Comment accepted; answer changed to b.

Question B.20 Comment: The facility noted that during operations the numbers vary between the range of 1 kW to 10 kW for an operator to note the Fuel Doppler Effect.

Justification: SP-204, Step 3.2

NRC Resolution: The NRC examiner accepted both b and c (1kW and 10kW respectively) as it would be an appropriate range which the Fuel Doppler Effect would become evident.

Question C.10 Comment: This question is technically incorrect. The purpose of the drying stones is to remove moisture in order to prevent corrosion of the electrical wiring for the nuclear instruments.

NRC Resolution: Question deleted.

Question C.19 Comment: During a loss of electricity to the MUTR, power would be provided to both the emergency lighting and security monitor system via a battery backup source.

NRC Resolution: The NRC Examiner accepted both b and c (emergency lighting and security monitoring systems respectively) as correct answers

University of Maryland NRC License Examination Written Examination with Answer Key 7/22/2010

ENCLOSURE 3 U. S. NUCLEAR REGULATORY COMMISSION NON-POWER REACTOR INITIAL LICENSE EXAMINATION FACILITY: UNIVERSITY OF MARYLAND

REACTOR TYPE: POOL TYPE, MODIFIED TRIGA DATE ADMINISTERED: 7/22/2010 CANDIDATE: ___________________________________

INSTRUCTIONS TO CANDIDATE:

Answers are to be written on the answer sheet provided. Attach the answer sheets to the examination. Points for each question are indicated in parentheses for each question. A 70% overall is 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 33.3 _______ _______

A. REACTOR THEORY, THERMODYNAMICS, AND FACILITY OPERATING CHARACTISTICS 20.00 33.3 _______ _______

B. NORMAL AND EMERGENCY OPERATING PROCEDURES AND RADIOLOGICAL CONTROLS 20.00 19.00 33.3 _______ _______

C. FACILITY AND RADIATION MONITORING SYSTEMS 60.00 59.00 ___________ FINAL GRADE TOTALS ALL THE WORK DONE ON THIS EXAMINATION IS MY OWN. I HAVE NEITHER GIVEN NOR RECEIVED AID.

__________________________

CANDIDATE'S SIGNATURE

Section A: ReactorTheory, 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.

MULTIPLE CHOICE 001 a b c d _

002 a b c d _ 003 a b c d _ 004 a b c d _ 005 a b c d _ 006 a b c d _ 007 a b c d _

008 a b c d _ 009 a b c d _ 010 a b c d _ 011 a b c d _

012 a b c d _ 013 a b c d _ 014 a b c d _ 015 a b c d _ 016 a b c d _ 017 a b c d _

018 a b c d _ 019 a b c d _ 020 a b c d _

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

Section B Normal, Emergency and Radiological Control Procedures 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.

MULTIPLE CHOICE 001 a b c d _

002 a b c d _ 003 a b c d _ 004 a b c d _ 005 a b c d _ 006 a b c d _ 007 a b c d _

008 a b c d _ 009 a b c d _ 010 a b c d _ 011 a b c d _

012 a b c d _ 013 a b c d _ 014 a b c d _ 015 a b c d _ 016 a b c d _ 017 a b c d _

018 a b c d _ 019 a b c d _ 020 a b c d _

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

Section 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.

MULTIPLE CHOICE 001 a b c d _

002 a b c d _ 003 a b c d _ 004 a b c d _ 005 a b c d _ 006 a b c d _ 007 a b c d _

008 a b c d _ 009 a b c d _ 010 a b c d _ 011 a b c d _

012 a b c d _ 013 a b c d _ 014 a b c d _ 015 a b c d _ 016 a b c d _ 017 a b c d _

018 a b c d _ 019 a b c d _ 020 a b c d _

(********** 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 not received or 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. 6. Fill in the date on the cover sheet of the examination (if necessary).

7. Print your name in the upper right-hand corner of the first page of each section of your answer sheets. 8. The point value for each question is indicated in parentheses after the question.

9. Partial credit will NOT be given.

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

11. When you are done and have turned in your examination, leave the examination area as defined by the examiner.

EQUATION SHEET

DR - Rem/hr, Ci - curies, E - Mev, R - feet

1 Curie = 3.7 x 10 10 dis/sec 1 kg = 2.21 lbm 1 Horsepower = 2.54 x 10 3 BTU/hr 1 Mw = 3.41 x 10 6 BTU/hr 1 BTU = 778 ft-lbf °F = 9/5 °C + 32 1 gal (H 2O) 8 lbm °C = 5/9 (°F - 32) c P = 1.0 BTU/hr/lbm/°F c p = 1 cal/sec/gm/°C

()()2 2 max=P T UA H m T c m Q P===1 sec 1.0=eff()()2 1 1 1 2 1 eff eff K CR K CR=+=eff SUR 06.26=t e P P 0 sec 10 1 4*x= eff K S S SCR=1()()2 2 1 1=CR CR ()0 1 P P=)(0 10 t SUR P P=1 2 1 1 CR CR K M eff==2 1 1 1 eff eff K K M==* eff eff K K SDM=1693.0 2 1=T++= eff*2 1 1 2 eff eff eff eff K K K K=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=

List of Figures Figure 1-Question A.2 Figure 2-Question A.6

List of Figures Figure 3-Question A.9

Figure 4-Question A.12

List of Figures Figure 5-Question A.15

List of Figures Figure 6-Question A.18

List of Figures Figure 7-Question B.9

List of Figures Figure 8-Question C.15 Section A: Reactor Theory, Thermodynamics, and Fac. Operating Characteristics

QUESTION A.1 [1.0 point]

Which ONE of the following isotopes has the largest microscopic cross-section for absorption for thermal neutrons?

a. Sm 149 b. U235 c. Xe 135 d. B10 QUESTION A.2 [1.0 point] The graph depicted in Figure-1 for U-235 depicts--

a. neutron energy distribution in the moderator b. axial flux distribution in the core

c. radial flux distribution in the core

d. fission product yield distribution

QUESTION A.3 [1.0 point]

Which factors of the six factor formula are affected by an INCREASE in core temperature and how are they affected?

a. Lf , p, f

b. , Lf , L t , p

c. , Lf , L t , p , , f

d. , Lf , L t , p , , f

Section A: Reactor Theory, Thermodynamics, and Fac. Operating Characteristics

QUESTION A.4 [1.0 point] You are conducting a reactor startup after installing 2 new fuel assemblies in the core. Given the following rod withdrawal data, estimate the rod position when criticality would occur. The initial count rate on the nuclear instrumentation prior to rod withdrawal is 55 cps.

a. 11 in

b. 12 in c. 13 in

d. 15 in QUESTION A.5 [1.0 point]

What is eff? a. The time required for the reactor power to change by a factor of e

b. The fraction of all fission neutrons that are born as delayed neutrons

c. The fraction of all delayed neutrons which reach thermal energy

d. The fractional change in neutron population per generation

QUESTION A.6 [1.0 point]

Given Figure-2, which answer best describes neutron behavior within Region II.

a. The neutron cross section is inversely proportional to the neutron velocity (1/V)

b. The neutron cross section decreases steadily with increasing neutron energy (1/E).

c. Neutrons of specific energy levels (e.g., 50 ev, 100 kev) are less likely to be readily absorbed than neutrons at other energy levels.

d. Neutrons of specific energy levels (e.g., 50 ev, 100 kev) are more likely to be readily absorbed than neutrons at other energy levels.

Rod Withdrawal (Inches) Count Rate (cps) 0 55 2 63 4 71 6 85 8 103 10 300 Section A: Reactor Theory, Thermodynamics, and Fac. Operating Characteristics QUESTION A.7 [1.0 point] Which of the following types of neutrons has a mean neutron generation lifetime of 12.7 seconds?

a. Prompt

b. Delayed

c. Fast

d. Thermal QUESTION A.8 [1.0 point] Which of the following statements is the predominant factor for the change in Xenon concentration following a reactor scram?

a. The concentration of Xe 135 will increase due to reduced nuclear flux

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

c. The concentration of Xe 135 will decrease by natural decay into I 135 d. The concentration of Xe 135 will remain constant until it is removed via neutron burnout during the subsequent reactor startup.

QUESTION A.9 [1.0 point]

Figure-3 depicts a plot of reactor period as a function of time. What best describes the behavior of REACTOR POWER between points A and B:

a. Constant

b. Decreasing then increasing

c. Continually increasing

d. Continually decreasing

Section A: Reactor Theory, Thermodynamics, and Fac. Operating Characteristics QUESTION A.10 [1.0 point] A reactor that has a reactivity of -$2.39 has a count rate of 50 cps on nuclear instrumentation. Calculate what the neutron level (i.e., count rate) should be after a reactivity insertion of $1.21 from the withdrawal of the control rods. Assume =0.0070 a. 25 cps

b. 50 cps

c. 100 cps

d. 200 cps QUESTION A.11 [1.0 point] During the time following a reactor scram, reactor power decreases on an 80 second period, which of the following corresponds to the half-life of the longest-lived delayed neutron precursors?

a. 80 seconds

b. 55 seconds

c. 40 seconds

d. 20 seconds

QUESTION A.12 [1.0 point] The reactor is operating in the automatic mode at 200 kW, with the regulating rod at 60% withdrawn. A malfunction of equipment in the secondary cooling system has caused primary temperature to decrease by 8 C. Disregarding any other automated system design features, find the new position of the regulating rod using the following and Figure-4:

Temperature Coefficient= -4.9 x 10

-4 K/C =0.0070 a. 44% Withdrawn

b. 50% Withdrawn

c. 66% Withdrawn

d. 80% Withdrawn

Section A: Reactor Theory, Thermodynamics, and Fac. Operating Characteristics QUESTION A.13 [1.0 point] Which ONE of the following is a correct statement of why delayed neutrons enhance the ability to control reactor power?

a. There are more delayed neutrons than prompt neutrons

b. Delayed neutrons are born at higher energy levels than prompt neutrons

c. Delayed neutrons increase the average neutron lifetime

d. Delayed neutrons readily fission in U-238 QUESTION A.14 [1.0 point] Reactor power is at 100 W and increasing on a 10 second period. Neglecting any temperature or reactivity feedback effects, how long will the reactor be at 200 kW?

a. 6.9 seconds

b. 76 seconds

c. 200 seconds

d. 362 seconds

QUESTION A.15 [1.0 point]

Using the applicable portion from the chart of the nuclides (Figure-5), what isotope will Mn-56 decay into? a. Mn-55 b. Co-60

c. Fe-56 d. Fe-58 Section A: Reactor Theory, Thermodynamics, and Fac. Operating Characteristics QUESTION A.16 [1.0 point] What is the condition of the reactor when =1 1 k? a. subcritical

b. critical

c. prompt critical

d. prompt supercritical

QUESTION A.17 [1.0 point] Inelastic scattering can be described as a process whereby a neutron collides with a nucleus and:

a. recoils with a lower kinetic energy, with the nucleus emitting a gamma ray.

b. recoils with the same kinetic energy it had prior to the collision.

c. is absorbed by the nucleus, with the nucleus emitting a gamma ray.

d. recoils with a higher kinetic energy, with the nucleus absorbing a gamma ray.

QUESTION A.18 [1.0 point] The graph (Figure-6) depicts fast and thermal fluxes in a reflected and non-reflected thermal reactor. Which of the following statements is true regarding a typical reflector?

a. A reflector has a high cross section for absorption which increases the peak power to average power ratio.

b. A reflector has a high cross section for scattering, which increases the peak to average power ratio c. Thermal neutrons tend to accumulate in the reflector until they leak back into the core, escape, or become absorbed, which reduces the peak to average power ratio.

e. Fast neutrons become absorbed in the reflector fuel, which raises the thermal flux and reduces the peak to average power ratio.

Section A: Reactor Theory, Thermodynamics, and Fac. Operating Characteristics QUESTION A.19 [1.0 point] A reactor is critical at 150 kW. Given the following data, calculate what the MINIMUM Shutdown Margin would be for this reactor under these conditions.

Total Rod Worth Safety Rod #1: $1.70 Safety Rod #2: $1.85 Regulating Rod: $1.50

a. $0.45 b. $2.30 c. $2.65 d. $3.20 QUESTION A.20 [1.0 point]

The ratio of the number of neutrons in one generation to the number of neutrons in the previous generation defines the:

a. effective multiplication factor.

b. fast fission factor.

c. neutron non-leakage factor.

d. neutron reproduction factor.

Control Rod Worth Remaining in Core:

Safety Blade #1: $1.00 Safety Blade #2: $1.00 Regulating Rod: $0.75

Section B: Normal/Emergency Procedures & Radiological Controls QUESTION B.1 [1.0 point] What is the Emergency Classification for a sustained fire at the reactor facility?

a. Personnel Emergency

b. Unusual Event (Class I)

c. Alert (Class 2)

d. None QUESTION B.2 [1.0 point] Which of the following is correct regarding NRC Form 3 "Notice to Employees"?

a. It provides guidance for filing a discrimination report

b. It provides guidance for how to report safety concerns

c. It informs you for how to get a record of your radiation exposure

d. All of the above

QUESTION B.3 [1.0 point] Which of the following conditions meets the Technical Specification definition for "Reactor Secured" at the MUTR?

a. An experiment with a reactivity of $2 is being installed in the reactor with all control rods fully inserted, Keyswitch is in OFF, and the console key is removed

b. All control rods are fully inserted and the Reactor Keyswitch in "OFF", console key is not removed

c. All control rods are fully inserted, the Reactor Keyswitch in "OFF", console key is removed, and fuel is being rearranged within the fuel storage racks.

d. Work is on the control rod drive mechanism is in progress with the drive coupled to the control rod. All control rods are fully inserted with the Reactor Keyswitch in "OFF" and console key is removed.

Section B: Normal/Emergency Procedures & Radiological Controls QUESTION B.4 [1.0 point] Which one of the following at MUTR DOES NOT require the presence of a Senior Reactor Operator (SRO)?

a. The relocation of an in-core experiment with worth equivalent to $1.00

b. The manipulation of reactor console controls by a student in training

c. Recovery from an unplanned shutdown due to loss of High Voltage power supply

d. The initial approach to power following the rearrangement of two fuel assemblies

QUESTION B.5 [1.0 point] The special unit for absorbed dose "Rem" is defined in 10 CFR Part 20 in terms of a dose equivalent. What does the term dose equivalent relate to?

a. It is derived by accounting for the amount of radioactive material taken into the body of an adult worker by inhalation or ingestion in one year

b. It is equal to the absorbed dose (rad) multiplied by the quality factor (Q) of the radiation

c. It is equal to the absorbed dose (rad) divided by the quality factor (Q) of the radiation

d. It is the equivalent dose one would receive during the 50-year period following intake

QUESTION B.6 [1.0 point] An example of Byproduct Material would be-.

a. Pu-239

b. U-233

c. U-235 d. Co-60

Section B: Normal/Emergency Procedures & Radiological Controls QUESTION B.7 [1.0 point] As an employee at the MUTR, if you worked continuously in an area of radiation which read 250 mrem/hr, how long could you stay before you exceeded your limit for exposure?

a. 24 minutes

b. 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months

c. 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months

d. 20 hours2.314815e-4 days 0.00556 hours 3.306878e-5 weeks 7.61e-6 months QUESTION B.8 [1.0 point] How many hours per calendar quarter must you perform the functions of an RO or SRO to maintain an active RO or SRO license?

a. 2 b. 4

c. 8 d. 12 QUESTION B.9 [1.0 point] You are performing a periodic contamination survey with a Geiger-Mueller type instrument. Using the graph (Figure-7), which region of the gas amplification curve does this type of meter belong to and which statement best describes this region?

a. Region V. The number of electrons produced through ionizations is independent of the applied detector voltage, therefore pulses cannot be differentiated to distinguish radiation of different energy types.

b. Region IV. The number of electrons produced through ionizations is dependent on the applied detector voltage, therefore pulses can be differentiated to distinguish radiation of different energy types.

c. Region III. Radiation interacts with a crystal center which causes electrons to be raised to an excited state. When crystal de-excites, the electron returns to ground state emitting a photon which is proportional to the intensity of the radiation.

d. Region II. The inner surface of the detector probe is covered with a thin coating of boron which aids with the detection of neutron radiation.

Section B: Normal/Emergency Procedures & Radiological Controls QUESTION B.10 [1.0 point] The tygon tubing for the pneumatic (rabbit) system is disconnected. An experiment is inserted into the core via the remaining tubing of the rabbit system. With the reactor running at 100% power which one of the following would most likely be a concern?

a. Radiation level increases due to Ar-41

b. Radiation level increases due to neutron streaming

c. Radiation level increases due to gamma streaming

d. Radiation level increases due to N-16 QUESTION B.11 [1.0 point] According to MUTR procedures and Technical Specifications, which of the following is NOT considered an UNSCHEDULED SHUTDOWN?

a. Loss of Power to the building removed the high voltage supply to the reactor console and caused all the safety rods to scram

b. During the annual surveillance check, a channel input signal of 320 kW caused all the safety rods to scram

c. The operator was not watching reactor period when it reached 4 seconds and caused all the safety rods to scram.

d. The operator inadvertently leaned on the scram bar with their elbow and caused all the safety rods to scram

Section B: Normal/Emergency Procedures & Radiological Controls QUESTION B.12 [1.0 point] The following statement, "The shutdown margin shall not be less than $0.50" provided in the MUTR Technical Specifications is an example of a (an)-.

a. Limiting safety system setting (LSS)

b. Safety limit

c. Limiting condition for operation (LCO)

d. Administrative Control QUESTION B.13 [1.0 point] During an event where reactor pool water is leaking significantly from cracks within the pool wall, which of the following is a TRUE statement regarding the need to maintain water inventory above 15 ft. per MUTR Tech Specs?

a. The loss of pool water will cause fuel temperature to exceed the limit for melting

b. Voiding effects will cause a significant positive reactivity addition and could cause overpower conditions

c. Due to the loss of coolant, the purification system will be unable to remove fission products from the pool water

d. The reduction in water inventory will reduce the effectiveness of the biological shielding

QUESTION B.14 [1.0 point] Which of the following is the limit on reactivity for a non-secured experiment at the MUTR?

a. < $0.50

b. < $1.00

c. < $1.50

d. < $3.00

Section B: Normal/Emergency Procedures & Radiological Controls QUESTION B.15 [1.0 point] The procedures to follow for a bomb threat can be found in the-..

a. 100 Series

b. 200 Series

c. 400 Series

d. 500 Series

QUESTION B.16 [1.0 point] What is the dose rate after shielding a Cs-137 source that emits 1 MeV photons if the unshielded dose rate is 100 mrem/hr and the source is shielded by 1/2 inch lead? Given:

Density: 11.35 g/cm 3 Mass Attenuation Coefficient: 0.0708 cm 2/g a. 13.3 mrem/hr

b. 36.2 mrem/hr

c. 50.0 mrem/hr

d. 91.4 mrem/hr

Section B: Normal/Emergency Procedures & Radiological Controls QUESTION B.17 [1.0 point] You are performing a periodic radiation survey when you find a streaming source of radiation which the detector display reads 50 mr/hr on contact from a cabinet that is not posted for radiological safety. How would this area be posted in accordance with the requirements of 10 CFR 20?

a. High Radiation Area @ 30 cm from the source

b. High Radiation Area on contact w/ the cabinet

c. Radiation Area @ 30 cm from the source

d. Radiation Area on contact w/ the cabinet QUESTION B.18 [1.0 point]

In the event of a suspected fuel leak from a 30/20 TRIGA element, which of the following nuclides would most likely be found in an Air Particulate Sample? a. Cs-138

b. Rn-226

c. Xe-133

d. Co-60 QUESTION B.19 [1.0 point] You are manually raising reactor power to 100 kW. When you reach the desired, stabilized power level you note that: Safety Channel I Reads 98 kW; Safety Channel II Reads 100 kW; and the Linear Power Chart Recorder (CIC Red pen) Reads 102 kW. Which of the following is considered the true reactor power level by procedure?

a. 102 kW

b. 100 kW

c. 98 kW d. None of the above. True power is determined from the Wide Range Log Power Channel

Section B: Normal/Emergency Procedures & Radiological Controls QUESTION B.20 [1.0 point] You are manually increasing power from 10 W to 250 kW on the regulating rod. By procedure at what power level will the Fuel Doppler Effect become evident?

a. 100 W b. 1 kW c. 10 kW d. 100 kW

Section C: Facility and Radiation Monitoring Systems QUESTION C.1 [1.0 point] How is the "Rod Down" limit indication cleared during control rod withdrawal?

a. The potentiometer sends an output signal based on the magnetic armature position being raised above the rod down limit position.

b. A microswitch is reversed when the foot on the pull rod drives upward due to the force of the compression spring, indicating the position of the control rod is above the rod down limit.

c. The magnetic draw tube engages the push rod and sends a signal to the console indicating the position of the control rod is above the rod down limit.

d. Sensors in the tubular barrel will send a signal indicating when the piston has cleared the rod down limit switch.

QUESTION C.2 [1.0 point] At the MUTR the reactor trip setpoint shall not exceed:

a. 275 kW

b. 300 kW

c. 350 kW

d. 425 kW

QUESTION C.3 [1.0 point] What is the basis for the safety limit "a standard TRIGA fuel element shall not exceed 1000°C under any condition of operation"?

a. This limit is set to prevent exceeding conditions for fuel melt

b. Prevents the formation of stress fractures which can form and cause fuel element failure during pulsing operations

c. Avoids "ballooning" effects and possible failure of the fuel element cladding from hydrogen gas during the dissociation of zirconium hydride

d. Precludes temperatures which are favorable for hydrogen embrittlement of the fuel cladding

Section C: Facility and Radiation Monitoring Systems QUESTION C.4 [1.0 point] The following reaction (10B + + ) can best be found in the ____________

a. Biological Shield

b. Thermal Column

c. Compensated Ion Chamber

d. Fission Chamber

QUESTION C.5 [1.0 point] Which of the following is a correct flowpath through the primary water system?

a. Top of reactor pool, flow orifice, primary pump, Heat Exchanger #1

b. Microfilter, primary pump, Heat Exchanger #2, flow orifice

c. Primary pump, flow orifice, Heat Exchanger #1, Heat Exchanger #2

d. Heat Exchanger #1, flow orifice, Heat Exchanger #2, reactor pool inlet

Section C: Facility and Radiation Monitoring Systems QUESTION C.6 [1.0 point] When radiation levels at the hot room Glove Box reach the alarm setpoint, which of the following occurs? a. An amber light will appear on the monitor

b. A red light will appear at the monitor and activate an audible alarm indication at the meter and the reactor console

c. A red light will appear at the monitor, an audible alarm indication will be available at the meter and the reactor console, and a reactor scram will occur

d. A red light will appear at the monitor, audible alarm indication will be available at the meter and the reactor console, a reactor scram will occur, and reactor external ventilation system will secure.

QUESTION C.7 [1.0 point] If 120 gpm is the total flowrate for the primary coolant system, what is the flowrate through the coolant purification system?

a. 12 gpm

b. 18 gpm

c. 60 gpm

d. 120 gpm

Section C: Facility and Radiation Monitoring Systems QUESTION C.8 [1.0 point] Using the following diagram of an instrumented fuel element match the correct position locator (Column A) to the correct component (Column B).

Column A Column B I A. Zirconium Hydride-Uranium II B. Stainless steel III C. Erbium Burnable Poison IV D. Graphite Reflector E. Zirconium Rod F. Spacer G. Thermocouples

a. I.A, II.E, III.C, IV.G

b. I.D, II.G, III.A, IV.F

c. I.D, II.E, III.A, IV.G

d. I.C, II.A, III.B, IV.G

Section C: Facility and Radiation Monitoring Systems QUESTION C.9 [1.0 point] The total combined heat removal capacity for the #1 and #2 Heat Exchangers is --?

a. 240 kW

b. 250kW c. 275 kW

d. 350 kW

QUESTION C.10 [1.0 point]

What is the purpose of the drying stones in the continuous air monitor detector supply lines?

a. They act as a filter to remove dirt and debris which could restrict air flow in the supply line

b. They are used to trap I

-131 during a fuel element failure

c. They prevent water from entering the ventilation system through the stack

d. They remove water vapor from the air to prevent damage to the compressor

QUESTION C.11 [1.0 point] Which of the following would be the result from inadvertently advancing the REACTOR POWER RANGE SWITCH to zero when approaching the demand setpoint on the % DEMAND controller?

a. The limit of 15 seconds on the regulating rod will be removed

b. A reactor scram will occur due to loss of indication on the linear channel c The Regulating Rod will drive to the UP limit, thereby exceeding the desired power level

d. Rod control will go from automatic to manual operations

Section C: Facility and Radiation Monitoring Systems QUESTION C.12 [1.0 point] Which of the following is (are) considered the Engineered Safety Feature at the MUTR?

a. The reactor overpower trip

b. Heat Exchanger #1 and #2

c. The confinement around the reactor pool tank and associated laboratories

d. The emergency fill connection from the city water supply

QUESTION C.13 [1.0 point] The purpose of the primary diffuser pump is to--..

a. Provide assistance with natural circulation through the reactor core

b. Reduce radiation levels at the pool surface

c. Sweep away fission products in order to prevent them from reaching the pool surface

d. Take a suction on the primary pool and discharge it to the purification system to remove activated impurities

QUESTION C.14 [1.0 point] What is the composition of the regulating rod?

a. Hafnium (HF)

b. Boron Carbide (B 4 C) c. Silver-Gadolinium (Ag-Gd)

d. Silver-Indium-Cadmium (Ag-In-Cd)

Section C: Facility and Radiation Monitoring Systems QUESTION C.15 [1.0 point] Using the schematic of the MUTR core cross section (Figure-8) match the correct position locator (Column A) to the correct component (Column B).

Column A Column B I A. Fission Chamber II B. Compensated Ion Chamber III C. Regulating Rod IV D. Instrumented Fuel Element E. Pneumatic Tube F. Graphite Reflector G. Neutron Startup Source H. Uncompensated Ion Chamber I. Shim Rod #1

a. I.A, II.D, III.G, IV.E

b. I.B, II.C, III.F, IV.E

c. I.H, II.I, III.D, IV.F

d. I.B, II.A, III.F, IV.G QUESTION C.16 [1.0 point] If a reactor is operating at low power levels (e.g., 100 mW), what is a potential consequence for applying too much compensating voltage to the Multi-Range Linear Channel?

a. Actual core power may be higher than indicated power level

e. Actual core power may be lower than indicated power level

f. There will be no effect, as the neutron flux signal will dominate the gamma flux signal at this power level

e. There will be no effect, the Multi-Range Linear Channel detector is an uncompensated ion chamber.

Section C: Facility and Radiation Monitoring Systems QUESTION C.17 [1.0 point] The driving force for the pneumatic transfer system is-..?

a. Compressed air

b. Compressed Nitrogen

c. Compressed CO 2

d. Hydraulic pressure

QUESTION C.18 [1.0 point] If a rupture occurred in the pool water outlet pipe, what would prevent all the water from draining out of the pool?

a. A check valve

b. A pneumatic isolation valve

c. A siphon breaker

d. The minimal elevation difference between the pipe and top of the pool QUESTION C.19 [1.0 point] In the event of a loss of power at the MUTR, which of the following will be provided power from a battery backup source until the normal source of power is restored?

a. Primary pump

b. Emergency Lighting

c. Security monitoring system

d. Ventillation fan motors

Section C: Facility and Radiation Monitoring Systems QUESTION C.20 [1.0 point] Several hot days in the DC Metro area in conjunction with high power reactor operations for extended periods of time has caused significant pool evaporation. Make-up fill from the make-up water system will be required to be performed. It is determined that 3 inches of pool level is desired to fill to 100% capacity. With the primary coolant pump operating and secondary cooling off the makeup water system will add 2 inches of pool level per hour of operation. If you lined up the system to fill and walked away from the system and returned 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months later that day, what would be the final level of the reactor pool, given that the initial pool level is 6 inches.

a. 14 inches

b. 9 inches

c 8 inches

d. 6 inches Section A: Reactor Theory, Thermodynamics, and Facility Operating Characteristics A.1 Answer: c Sm 149 (41,000 b); U 235 (687 b); Xe 135 (2.65 x 10 6 b); B 10 (3840 b)

Reference:

Lamarsh, J. "Introduction to Nuclear Engineering" p. 738 A.2 Answer: d

Reference:

DOE Manual Vol. 1, pg. 57, NEEP 234 "Reactor Physics Part I", pg.2

A.3 Answer: a

Reference:

As reactor core temperature increases, the moderator to fuel ratio will decrease due to the decrease in density of the water. Therefore, due to this fact:

Lf (Fast Non-Leakage Factor): is the probability that neutrons will not leak out while still fast. Therefore, with less moderator in the core, the probability that they will not leak out decreases.

p(Resonance Escape Probability): is the probability that a neutron will be reduced to thermal energy levels without being absorbed by U-238. Due to the increase in temperature and Doppler Broadening effects, the probability of escape decreases.

f (Thermal Utilization Factor): is the ratio of absorption in fuel to the amount absorbed in the core (e.g., fuel, moderator, control rods, etc.). When the temperature rises, the water moderator expands, and a significant amount of it will be forced out of the reactor core. This means that

N m, the number of moderator atoms per cm 3, will be reduced, making it less likely for a neutron to be absorbed by a moderator atom. This reduction in N m results in an increase in thermal utilization as moderator temperature increases because a neutron now has a better chance of hitting a fuel atom.

DOE Manual Vol 2, Section 1.0

A.4 Answer: a

Reference:

2 1 CR CR=M 1, Where CR 1= reference count rate (i.e., 55 cps) and CR 2= current count rate.

DOE Handbook Vol. 2, NEEP 234

A.5 Answer: c Reference. Effective delayed neutron fraction is the fraction of all delayed neutrons which reach thermal energy. DOE Handbook, Vol 2, Section 2.0 A.6 Answer: d.

Reference:

Resonance Escape Region DOE Manual Vol 1, Section 2, and NEEP 234 "Reactor Physics III" pg. 2 A.7 Answer: b

Reference:

NEEP 234 "Reactor Physics II" pg. 2 A.8 Answer: b

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 and NEEP 234 "Reactor Physics I" pg. 9 0 0.2 0.4 0.6 0.8 1 1.202468101214 1/MRod Height (in)1/M Plot vs Rod Withdrawal A.9 Answer: d Ref: From point A to B, reactor period is negative, and since Pf=Poe T t, power will continue to decrease. DOE Manual Vol. 1, Section 2 A.10 Answer: c Ref: This question can be answered in two ways. One way is through the equations as shown below, or two, use a rule of thumb that if the reactor moves halfway from its subcritical state towards criticality, the count rate will double.

1 2 2 1 1 1 k k CR CR=--> 2 CR= 1 CR 2 1 1 1 k k=50 cps 992.0 1 984.0 1=100 Where, ($)=/

p 1=(0.0070)x(-$2.39)= -0.01673, p 2= (0.0070)x(1.21)= 0.00850= 821 pcm--> -0.00823 1 1 1 1 p k== 01673.0 1 1+= 0.984 2 2 1 1 p k== 00823.0 1 1+=0.9918 DOE Manual Vol. 2, Section 1

A.11 Answer: b

Reference:

Group 1 is the longest-lived delayed neutron precursor for thermal fission in U-235, with a half-life of 55.72 sec. Lamarsh, J. "Introduction to Nuclear Engineering" p. 88 A.12 Answer: a

Reference:

The decrease in temperature has added 0.392 % of reactivity which must be accounted for by the regulating rod to maintain 200 kW. Therefore, the reg rod must be inserted -0.392 % worth. Converting -0.392 % to $= ($)=/ 0.00392/0.0070= -56 cents Using the integral rod worth curve, with the reg rod initially at 60% (150 cents), the new rod height at 150 - 56=94 cents (44% withdrawn).

DOE Manual Vol. 2 Section 3, MUTR SAR p. 1-3 A.13 Answer: c

Reference:

DOE Manual, Section 3

A.14 Answer: b

Reference:

P=Po

exp(t/period) 200E3 W = (100 W)

exp(t/10sec) exp(t/10 sec) = 200E3/100 = 2E3 t/10 sec = ln(2E3) = 7.6 t = 76 seconds Lamarsh, J. 2001. Introduction to Nuclear Engineering 3 rd Ed.. P. 331, DOE Fundamentals Handbook.Vol.2 Section 4 A.15 Answer: c

Reference:

Mn-56 is beta decay, which is the conversion of a neutron into a proton and electron.

Baum, E., Knox, H., and Miller, T. 2002. Nuclides and Isotopes 16 th Ed. p. 28

A.16 Answer: c

Reference:

The multiplication factor (k) is proportional to the total number of neutrons, prompt and delayed, emitted per fission. However, since only the fraction (1-) of the fission neutrons are prompt, the fraction of prompt neutrons from with regards to the multiplication factor is (1-)k. Therefore, when (1-)k=1, the reactor is critical on prompt neutrons alone, and the reactor is said to be prompt critical. If you rearrange (1-)k=1 it will read =1 1 k. Lamarsh, J. 2001. Introduction to Nuclear Engineering 3 rd Ed.. pp.340-341 A.17 Answer: a

Reference:

DOE Handbook Vol I, pg. 45

A.18 Answer: c.

Reference:

The thermalized neutrons are not absorbed as quickly in the reflector as neutrons thermalized in the core since the reflector, being unfueled, has a much smaller absorption cross-section. The thermal neutrons tend to accumulate in the reflector until they leak back into the core, escape from the outer surface of the reflector, or are absorbed. Lamarsh, J. 2001. Introduction to Nuclear Engineering 3 rd Ed.. p. 305.

A.19 Answer: a

Reference:

Total Rod Worth Safety Rod #1: $1.70 Safety Rod #2: $1.85 Regulating Rod: $1.50

SDM= TRW+ Excess Reactivity =($1.70+$1.85+$1.50)-($1.00+$1.00+0.75)=$2.30 MIN SDM= $2.30-$1.85 (most reactive rod)=$0.45 DOE Manual Handbook Vol II, pg. 28 A.20 Answer:a

Reference:

MUTR ENNU 320 VOL.1, p. 7-1

Control Rod Worth Remaining in Core:

Safety Blade #1: $1.00 Safety Blade #2: $1.00 Regulating Rod: $0.75 Section B: Normal Emergency Procedures & Radiological Controls B.1 Answer: b

Reference:

MUTR Rev. 12, pg. 4-1 B.2 Answer: d

Reference:

NRC Form 3. http://www.nrc.gov/reading-rm/doc-collections/forms/form3_us.pdf

B.3 Answer: c

Reference:

MUTR TS 1.24.2.d B.4 Answer: b

Reference:

Under 10 CFR Part 55, The regulations in this part do not require a license for an individual who- "Under the direction and in the presence of a licensed operator or senior operator, manipulates the controls of a research or training reactor as part of the individual's training as a student" 10 CFR Part 55.13

B.5 Answer: b

Reference:

10 CFR Part 20.1003 B.6 Answer: d.

Reference:

Byproduct material is radioactive material made radioactive by the process of using special nuclear material 10 CFR Part 20.1003

B.7 Answer d.

Reference:

5000 mrem/250 mr/hr= 20 hours2.314815e-4 days 0.00556 hours 3.306878e-5 weeks 7.61e-6 months B.8 Answer: b

Reference:

10CFR55.53(e)

B.9 Answer: a

Reference:

DOE Fundamentals Handbook-1013/2-92, pg. 42

B.10 Answer: a

Reference:

MUTR SAR B.11 Answer: b

Reference:

MUTR AP-500 Section 3.8 and TS Section 1.140

B.12 Answer: c

Reference:

MUTR TS Section 3.1.1 B.13 Answer: d

Reference:

MUTR TS Section 3.3.1 B.14 Answer: b

Reference:

MUTR Tech Specs Section 3.7.1

B.15 Answer: c

Reference:

MUTR Procedure Index B.16 Answer: b

Reference:

and Solving for µ= x Radiation Protection Training Manual, Chapter 5 p. 42

B.17 Answer: c

Reference:

10 CFR 20.

B.18 Answer: a

Reference:

Emergency Preparedness Plan for the Maryland University Training Reactor, dated 12/99 p. 4-2 and MUTR SAR

B.19 Answer: a

Reference:

At power operations of greater than 2.5 kW, the most conservative power indication (i.e. highest reading) on either Safety I, Safety II, or the Linear Power Chart Recorder (CIC red pen) shall be used as the true power level whenever any two power level indicators listed above differs. MUTR OP 104, Section 3.6 B.20 Answer: b & c

Reference:

SP-204, Step 3.2

Section C: Facility and Radiation Monitoring Systems C.1 Answer: b

Reference:

ENNU 320 Vol.2, Section 3.2 C.2 Answer: b

Reference:

MUTR TS, p.11 C.3 Answer: c

Reference:

MUTR TS, March 2000, pg. 6

C.4 Answer: c

Reference:

ENNU 320 Vol.2, Section 3.3.5.2 C.5 Answer: c

Reference:

ENNU 320 Vol.2, Section 3.2 C.6 Answer: b

Reference:

MUTR SAR, pg. 7-29

C.7 Answer: a

Reference:

MUTR SAR, pg. 5-1 C.8 Answer: c

Reference:

ENNU 320 Vol.2, pg. 3-9

C.9 Answer: a

Reference:

ENNU 320 Vol.2, pg. 4-1 C.10 Deleted C.11 Answer: c

Reference:

Op104, Rev 12.

C.12 Answer: c

Reference:

MUTR SAR, p. 6-1 C.13 Answer: b

Reference:

ENNU 320 Vol.2, p.5-4

C.14 Answer: b

Reference:

ENNU 320 Vol.2, Appendix A-1 C.15 Answer: b

Reference:

ENNU 320 Vol.2, pg. 3-16 C.16 Answer: a

Reference:

DOE Fundamentals Handbook 1013, Section 2.4

C.17 Answer: c

Reference:

ENNU 320 Vol.2, pg. 5-2 C.18 Answer: d

Reference:

ENNU 320 Vol.2, pg. 4-2

C.19 Answer: b & c C.20 Answer: c

Reference:

MP305 Rev. 12

ML102230464

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Dear Dr. Al-Sheikhly:

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Dear Dr. Al-Sheikhly:

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