Text

Initial Examination Report No. 50-123/OL-09-01, Missouri University of Science and Technology
	ML083390531
Person / Time
Site:	University of Missouri-Rolla
Issue date:	12/19/2008
From:	Johnny Eads; Research and Test Reactors Branch B
To:	Frimpong S; Missouri Univ of Science & Technology
	Young P, NRC/NRR/ADRA/DPR, 415-4094
References
	50-123/OL-09-01
	Download: ML083390531 (22)
	v • d • e

December 19, 2008 Dr. Samuel Frimpong, Chair Mining and Nuclear Engineering 226 McNutt Hall Missouri University of Science and Technology Rolla, MO 65409-0450

SUBJECT:

INITIAL EXAMINATION REPORT NO. 50-123/OL-09-01, MISSOURI UNIVERSITY of SCIENCE and TECHNOLOGY

Dear Dr. Frimpong:

During the week of November 17, 2008, the NRC administered an operator licensing examination at your Missouri University of Science and Technology 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 Mr. Phillip T. Young at 301-415-4094 or via internet e-mail pty@nrc.gov.

Sincerely,

/RA/

Johnny H. Eads, Jr., Chief Research and Test Reactors Branch B Division of Policy and Rulemaking Office of Nuclear Reactor Regulation Docket No. 50-123

Enclosures:

1. Initial Examination Report No. 50-123/OL-09-01

2. Written examination with facility comments incorporated cc without enclosures:

Please see next page

December 19, 2008 Dr. Samuel Frimpong, Chair Mining and Nuclear Engineering 226 McNutt Hall Missouri University of Science and Technology Rolla, MO 65409-0450

SUBJECT:

INITIAL EXAMINATION REPORT NO. 50-123/OL-09-01, MISSOURI UNIVERSITY of SCIENCE and TECHNOLOGY

Dear Dr. Frimpong:

During the week of November 17, 2008, the NRC administered an operator licensing examination at your Missouri University of Science and Technology 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 Mr. Phillip T. Young at 301-415-4094 or via internet e-mail pty@nrc.gov.

Sincerely,

/RA/

Johnny H. Eads, Jr., Chief Research and Test Reactors Branch B Division of Policy and Rulemaking Office of Nuclear Reactor Regulation Docket No. 50-123

Enclosures:

1. Initial Examination Report No. 50-123/OL-09-01

2. Written examination with facility comments incorporated cc without enclosures:

Please see next page DISTRIBUTION w/ encls.:

PUBLIC PRTB r/f RidsNRRDPRPRTA RidsNRRDPRPRTB Facility File (CRevelle) O-13 D-07 ADAMS ACCESSION #: ML083390531 TEMPLATE #:NRR-074 OFFICE PRTB:CE IOLB:LA E

PRTB:SC NAME PYoung pty CRevelle car JEads jhe DATE 12/05/08 12/15/08 12/19/08 OFFICIAL RECORD COPY

University of Missouri - Rolla Docket No. 50-123 cc:

Bill Bonzer University of Missouri-Rolla Missouri University of Science and Technology Nuclear Reactor Facility 1870 Miner Circle Rolla, MO 65409-0630 Homeland Security Coordinator Missouri Office of Homeland Security P.O. Box 749 Jefferson City, MO 65102 Planner, Dept of Health and Senior Services Section for Environmental Public Health 930 Wildwood Drive, P.O. Box 570 Jefferson City, MO 65102-0570 Deputy Director for Policy Department of Natural Resources 1101 Riverside Drive Fourth Floor East Jefferson City, MO 65101 A-95 Coordinator Division of Planning Office of Administration P.O. Box 809 State Capitol Building Jefferson City, MO 65101 Test, Research, and Training Reactor Newsletter University of Florida 202 Nuclear Sciences Center Gainesville, FL 32611

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

50-123/OL-09-01 FACILITY DOCKET NO.:

50-123 FACILITY LICENSE NO.:

R-79 FACILITY:

Missouri University of Science and Technology EXAMINATION DATES:

November 17 & 18, 2008 SUBMITTED BY:

_____/RA/_________________

__12/5/08____

Phillip T. Young, Chief Examiner Date

SUMMARY

During the week of November 17, 2008 the NRC administered operator licensing examinations to one Senior Operator - Instant and two Senior Operator - Upgrade applicants. All applicants passed all portions of the examinations.

REPORT DETAILS

1.

Examiners:

Phillip T. Young, Chief Examiner, NRC John Nguyen, Examiner Trainee, NRC

2.

Results:

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

3.

Exit Meeting:

Phillip T. Young, NRC, Examiner Bill Bonzer, Reactor Supervisor, Missouri University of Science and Technology The examiner thanked the facility for their cooperation during the examination. No generic issues were identified.

ENCLOSURE 1

License Operator Written Examination With ANSWER KEY OL-09-01 MISSOURI UNIVERSITY of SCIENCE and TECHNOLOGY November 17, 2008

Section A:

Theory, Thermodynamics, and Facility Operating Characteristics Page 6 of 22 Question A.001

[1.0 point]

(1.0)

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 Answer:

A.001 d.

Reference:

Glasstone, S., Nuclear Reactor Engineering, Kreiger Publishing, Malabar:

Florida, 1991. 3rd Edition. pg. 13 Question A.002

[1.0 point]

(2.0)

Suppose the temperature coefficient of a core is -2.5 x 10-4 K/K/C and the average control rod worth of the regulating control rod is 5.895 x 10-3 K/K/inch. If the temperature INCREASES by 50C what will the automatic control command the regulating rod to do? Select the answer that is closest to the calculated value.

a. 5.6 inches in

b. 2.1 inches out

c. 0.5 inches in

d. 4.3 inches out Answer:

A.002 b.

Reference:

The temperature increase will result in a change in reactivity of: -2.5 x 10-4 K/K/C x 50C = -1.25 x 10-2 K/K. Since the temperature rise results in a negative reactivity insertion, the control rod will need to drive out to add positive reactivity. D = (1.25 x 10-2 K/K)

÷ (5.895 x 10-3 K/K/inch) = 2.12 inches

Section A:

Theory, Thermodynamics, and Facility Operating Characteristics Page 7 of 22 Question A.003

[1.0 point]

(3.0)

Given the following data, which ONE of the following is the closest to the half life of the material?

TIME ACTIVITY 0

2400 cps 10 min.

1757 cps 20 min.

1286 cps 30 min.

941 cps 60 min.

369 cps

a. 11 minutes

b. 22 minutes

c. 44 minutes

d. 51 minutes Answer A.003 b.

Reference:

Question A.004

[1.0 point]

(4.0)

During a fuel loading of the core, as the reactor approaches criticality, the value of 1/M:

a. Increases toward one

b. Decreases toward one

c. Increases toward infinity

d. Decreases toward zero Answer:

A.004 d.

Reference:

Glasstone, S., Nuclear Reactor Engineering, Kreiger Publishing, Malabar:

Florida, 1991. 3rd Edition. pg. 191

Section A:

Theory, Thermodynamics, and Facility Operating Characteristics Page 8 of 22 Question A.005

[1.0 point]

(5.0)

Which one of the following is the definition of the FAST FISSION FACTOR?

a. The ratio of the number of neutrons produced by fast fission to the number produced by thermal fission

b. The ratio of the number of neutrons produced by thermal fission to the number produced by fast fission

c. The ratio of the number of neutrons produced by fast and thermal fission to the number produced by thermal fission

d. The ratio of the number of neutrons produced by fast fission to the number produced by fast and thermal fission Answer:

A.005 c.

Reference:

[1.0 point]

(6.0)

The number of neutrons passing through a one square centimeter of target material per second is the definition of which one of the following?

a. Neutron Population (np)

b. Neutron Impact Potential (nip)

c. Neutron Flux (nv)

d. Neutron Density (nd)

Answer:

A.006 c.

Reference:

[1.0 point]

(70)

Which ONE of the following atoms will cause a neutron to lose the most energy in an elastic collision?

a. Uranium238

b. Carbon12

c. Hydrogen2

d. Hydrogen1 Answer:

A.007 d.

Reference:

Lamarsh, J.R., Introduction to Nuclear Engineering, 1983. § Appendix II Table II.2, p. 643.

Section A:

Theory, Thermodynamics, and Facility Operating Characteristics Page 9 of 22 Question A.008

[1.0 point]

(8.0)

Two different neutron sources were used during two reactor startups. The source used in the first startup emits ten times as many neutrons as the source used in the second startup.

Assume all other factors are the same for the second startup. Which ONE of the following states the expected result at criticality?

a. Neutron flux will be higher for the first startup.

b. Neutron flux will be higher for the second startup.

c. The first startup will result in a higher rod position (rods further out of the core).

d. The second startup will result in a higher rod position (rods further out of the core).

Answer:

A. 008 a.

Reference:

Burn, Introduction to Nuclear Reactor Operations, Pages 5-14 thru 5-19.

Question A.009

[1.0 point]

(9.0)

When performing rod calibrations, many facilities pull the rod out a given increment, then measure the time for reactor power to double (doubling time), then calculate the reactor period.

If the doubling time is 42 seconds, what is the reactor period?

a. 29 sec

b. 42 sec

c. 61 sec

d. 84 sec Answer:

A.009 c.

Reference:

ln (2) = -time/ = time/(ln(2)) = 60.59 61 seconds Question A.010

[1.0 point]

(10.0)

Which ONE of the following statements concerning reactor poisons is NOT true?

a. Following shutdown, Xenon concentration will initially increase to some value then decrease exponentially.

b. Following shutdown, Samarium concentration will increase to some value then stabilize.

c. During reactor operation, Samarium concentration is independent of reactor power level.

d. During reactor operation, Xenon concentration is dependent on reactor power level.

Answer:

A.010 c.

Reference:

Primary Reference, Volume 2, Module 3, Reactor Theory (Nuclear Parameters), Enabling Objectives 4.1 through 4.15.

Section A:

Theory, Thermodynamics, and Facility Operating Characteristics Page 10 of 22 Question A.011

[1.0 point]

(11.0)

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

a.

35Br87 33As83

b.

35Br87 35Br87

c.

35Br87 34Se86

d.

35Br87 36Kr87 Answer:

A.011 a.

Reference:

[1.0 point]

(12.0)

About two minutes following a reactor scram, period has stabilized, and is decreasing at a CONSTANT rate. If reactor power is 10-5% full power what will the power be in three minutes.

a. 5 x 10-6 % full power

b. 2 x 10-6 % full power

c. 10-6 % full power

d. 5 x 10-7 % full power Answer:

A.012 c.

Reference:

P = P0 e-T/ = 10-5 x e(-180sec/80sec) = 10-5 x e-2.25 = 0.1054 x 10-5 = 1.054 x 10-6 Question A.013

[1.0 point]

(13.0)

For the same constant reactor period, which ONE of the following transients requires the SHORTEST time to occur? A power increase of:

a. 5% of rated power going from 1% to 6% of rated power.

b. 10% of rated power going from 10% to 20% of rated power.

c. 15% of rated power going from 20% to 35% of rated power.

d. 20% of rated power going from 40% to 60% of rated power.

Answer:

A. 013 d.

Reference:

Burn, Introduction to Nuclear Reactor Operations, Page 4-4.

Section A:

Theory, Thermodynamics, and Facility Operating Characteristics Page 11 of 22 Question A. 014

[1.0 point]

(14.0)

Which ONE of the following describes the term prompt jump?

a. The instantaneous change in power level due to withdrawing a control rod.

b. A reactor which has attained criticality on prompt neutrons alone.

c. A reactor which is critical using both prompt and delayed neutrons.

d. A negative reactivity insertion which is less than âeff.

Answer:

A.014 a.

Reference:

Burn, Introduction to Nuclear Reactor Operations, Page 4-21.

Question A.015

[1.0 point]

(15.0)

Which ONE of the following describes the difference between a moderator and reflector?

a. A reflector increases the fast non-leakage factor and a moderator increases the thermal utilization factor.

b. A reflector increases the neutron production factor and a moderator increases the fast fission factor.

c. A reflector decreases the thermal utilization factor and a moderator increases the fast fission factor.

d. A reflector decreases the neutron production factor and a moderator decreases the fast nonleakage factor.

Answer:

A.015 a.

Reference:

Burn, Introduction to Nuclear Reactor Operations, Page 3-16.

Section A:

Theory, Thermodynamics, and Facility Operating Characteristics Page 12 of 22 Question B.001

[1.0 point]

(1.0)

Which ONE of the following is the definition of Emergency Action Level?

a. a condition that calls for immediate action, beyond the scope of normal operating procedures, to avoid an accident or to mitigate the consequences of one.

b. Specific instrument readings, or observations; radiation dose or dose rates; or specific contamination levels of airborne, waterborne, or surface-deposited radioactive materials that may be used as thresholds for establishing emergency classes and initiating appropriate emergency methods.

c. classes of accidents grouped by severity level for which predetermined emergency measures should be taken or considered.

d. a document that provides the basis for actions to cope with an emergency. It outlines the objectives to be met by the emergency procedures and defines the authority and responsibilities to achieve such objectives.

Answer:

B.001 b.

Reference:

Emergency Plan, § 2.0 Definitions, p. 2-1.

Question B.002

[1.0 points]

(2.0)

Which ONE of the following correctly defines a Safety Limit?

a. Limits on important process variables which are found to be necessary to reasonably protect the integrity of certain physical barriers which guard against the uncontrolled release of radioactivity.

b. The Lowest functional capability of performance levels of equipment required for safe operation of the facility.

c. Settings for automatic protective devices related to those variables having significant safety functions.

d. a measuring or protective channel in the reactor safety system.

Answer:

B.002 a.

Reference:

Technical Specifications § 1, Definitions

Section B - Normal & Emergency Operating Procedures & Radiological Controls Page 13 of 22 Question B.003

[2.0 points, 2/5 each]

(4.0)

Match the Control Channel in column A with its respective rundown setpoint in column B.

Control Channel Setpoint

a. Linear power (%)

1. 15

b. Reactor period (seconds)

2. 20

c. Low CIC voltage (%)

3. 80

d. Radiation Monitors (mR/hr)

4. 120

e. Log power Answer:

B.003 a. = 4;

b. = 1; c.= 3;

d. = 2;

e. = 4

Reference:

Technical Specification Table 3.1 Question B.004

[1.0 point]

(5.0)

For the purposes of a reactor startup, the reactor is considered clean if it hasnt been operated if within the past 52 hours6.018519e-4 days 0.0144 hours 8.597884e-5 weeks 1.9786e-5 months , it hasnt exceeded

a. 2 kW-hr.

b. 10 kW-hr.

c. 20 kW-hr.

d. 100 kW-hr.

Answer:

B.004 c.

Reference:

SOP 103 Startup to Low Power, § B.2.

Question B.005

[1.0 point]

(6.0)

An experimenter wishes to irradiate three specimens with reactivity worths of 0.5% k/k, 0.13% k/k and 0.27% k/k. Can these specimens be placed in the reactor as UNSECURED experiments and why (why not).

a. Yes, the sum of the three specimens is less than 1.2% k/k.

b. No, the sum of the three specimens is greater than 0.8% k/k.

c. Yes, each specimen is less than 0.6% k/k.

d. No, one of the specimens is greater than 0.4% k/k.

Answer:

B.005 d.

Reference:

Technical Specifications 3.7.1

Section A:

Theory, Thermodynamics, and Facility Operating Characteristics Page 14 of 22 Question B.006

[1.0 point]

(7.0)

SOP 501 Emergency Procedures for Reactor Building Evacuation lists the actions for you (the RO) and the SRO on duty to take during this type of an emergency. The lowest level of management authorized to instruct you to proceed differently from the items listed in your checklist is

a. SRO on Duty

b. Reactor Manager

c. Reactor Director

d. NRC Project Manager, the SRO on Duty may instruct the operator to proceed differently from the items listed in the checklist.

Answer:

B.006 a.

Reference:

SOP 501 Emergency Procedures for Reactor Building Evacuation § C.I.6 Question B.007

[1.0 point]

(8.0)

Your Reactor Operator license expires after _____ years.

a. 2

b. 4

c. 6

d. 8 Answer:

B.007 c.

Reference:

10CFR55.55(a)

Question B.008

[1.0 point]

(9.0)

Which ONE of the following conditions does NOT require a rod drop time measurement?

a. Rod moved to new location within core.

b. Magnet assembly removed and reinstalled.

c. the core configuration is changed.

d. Rod inspection Answer:

B.008 c.

Reference:

T.S. §§ 4.2.1 Specification (1)

Section B - Normal & Emergency Operating Procedures & Radiological Controls Page 15 of 22 Question B.009

[1.0 point]

(10.0)

Technical Specification 5.4.1 requires the neutron multiplication factor of the fully loaded storage pit shall not exceed ____ under any conditions.

a. 0.80

b. 0.85

c. 0.90

d. 0.95 Answer:

B.009 c.

Reference:

Technical Specification 5.4.1 Question B.010

[1.0 point]

(11.0)

According to Technical Specification 3.7.1 Experiments worth more than _____ delta k/k shall be inserted or removed with the reactor shutdown.

a. 0.05

b. 0.4

c. 1.2

d. 1.5 Answer:

B.010 b.

Reference:

Technical Specification 3.7.1 (3)

Question B. 011

[1.0 point]

(12.0)

In accordance with Technical Specifications, which ONE of the following conditions is NOT permissible when the reactor is operating?

a. Primary coolant resistivity = 0.5 mega-ohm-cm.

b. Depth of water in pool = 16 feet.

c. A secured experiment worth 1.2% delta k/k in reactor.

d. Minimum shutdown margin = 1.5% delta k/k.

Answer:

B.011 b.

Reference:

University of Missouri-Rolla Technical Specifications, Section 3.3.

Section A:

Theory, Thermodynamics, and Facility Operating Characteristics Page 16 of 22 Question B. 012

[1.0 point]

(13.0)

In accordance with SOP 101, who is the only person authorized to use an interlock bypass key?

a. The licensed reactor operator at the console.

b. The Senior Operator on duty.

c. Reactor Manager.

d. Reactor Director.

Answer:

B.012 b.

Reference:

SOP 101, General Operational Procedures.

Question B. 013

[1.0 point]

(14.0)

"A channel test of each of the reactor safety system channels shall be performed before each day's operation or before each operation expected to extend more than one day, except for the bridge motion monitor which shall be done weekly." This is an example of a"

a. safety limit.

b. limiting safety system setting.

c. limiting condition for operation.

d. surveillance requirement.

Answer:

B.013 d.

Reference:

University of Missouri-Rolla Technical Specifications, Section 4.2.2.

Question B.014

[1.0 point]

(15.0)

The Quality Factor is used to convert

a. dose in rads to dose equivalent in rems.

b. dose in rems to dose equivalent in rads.

c. contamination in rads to contamination equivalent in rems

d. contamination in rems to contamination equivalent in rads Answer:

B.014 a.

Reference:

10CFR20.1004.

Section C - Facility and Radiation Monitoring Systems Page 17 of 22 Question C.001

[1.0 point, 1/4 each]

(1.0)

Match each of the radiation monitors in column A with its associated actions in Column B.

a. Demineralizer RAM

1. Indication Only

b. Experiment Room RAM

2. Indication and Runback Only

c. Reactor Bridge RAM

3. Indication, Runback and Evacuation.

d. CAM Answer:

C.001 a. = 2;

b. = 2;

c. = 3;

d. = 1

Reference:

Technical Specifications Table 3.3, and SAR § 3.6.2, pp., 3 3-38.

Question C.002

[1.0 point]

(2.0)

Core inlet temperature is measured using two thermocouples. A thermocouple is

a. a precision wound resistor which changes resistance proportional to the change in temperature.

b. a bi-metallic junction which changes voltage proportional to the change in temperature.

c. a sphere containing a liquid which changes volume with temperature. Expansion and contraction cause an arm in an inductor to move changing inductance proportional to the change in temperature.

d. a mercury filled balloon inside an inductor, the expansion and contraction of the mercury causes a variation in the circuit inductance proportional to the change in temperature.

Answer:

C.002 b.

Reference:

SAR § 3.5.3 Question C.003

[1.0 point]

(3.0)

How is heat removed from the core at 100% power?

a. Forced flow due to the diffuser pumps.

b. Natural convection of the water within the core.

c. Forced flow due to flow through the demineralizer system.

d. Nucleate boiling of the water within the core.

Answer:

C.003 b.

Reference:

Standard NRC Question

Section A:

Theory, Thermodynamics, and Facility Operating Characteristics Page 18 of 22 Question C.004

[1.0 point]

(4.0)

The gas used to move pneumatic tube rabbit samples into and out of the reactor is

a. H2

b. Air

c. CO2

d. N2 Answer:

C.004 d.

Reference:

SAR § 4.3, p. 4-5.

Question C.005

[1.0 point]

(5.0)

The heat capacity of the reactor pool is sufficient to cool the reactor for ______, with the reactor operating at full power (200 Kilowatts. Assumption: Starting bulk temperature = 20C. Note 135F = 57.2C.

a. about 10 Minutes

b. about an Hour

c. about a Day (24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months )

d. about a Week (168 hours0.00194 days 0.0467 hours 2.777778e-4 weeks 6.3924e-5 months )

Answer:

C.005 c.

Reference:

SAR, § 3.4.7, p. 3-28.

Question C.006

[1.0 point]

(6.0)

Each shim/safety rods consists of a grooved,

a. hafnium rod.

b. boron-carbide rod.

c. boral (boron and aluminum alloy) rod.

d. boron steel rod.

Answer:

C.006 d.

Reference:

SAR § 3.2.3, p. 3-11.

Section C - Facility and Radiation Monitoring Systems Page 19 of 22 Question C.007

[1.0 point]

(7.0)

Which ONE of the listed radioisotopes is best detected by the Continuous Air Monitor?

a. Rb88

b. N16

c. Ar41

d. Xe136 Answer:

C.007 a.

Reference:

SAR § 3.6.2, 7th ¶. (Designed to detect particulate NOT gaseous radioactivity.)

Question C.008

[1.0 point]

(8.0)

The Pneumatic Tube system consists of two rabbit tubes. One of these tubes is lined to prevent sample activation by thermal neutrons. This tube is lined with...

a. Boron

b. Cadmium

c. Carbon

d. Hafnium Answer:

C.008 b.

Reference:

SAR § 4.3 1st ¶.

Question C.009

[1.0 point]

(9.0)

The automatic controller will shift from automatic to manual, without operator action, anytime the difference between power level and demand exceeds the +/- % variation limit.

a. 1

b. 2

c. 3

d. 5 Answer:

C.009 b.

Reference:

SAR 3.5.5 page 3-36

Section A:

Theory, Thermodynamics, and Facility Operating Characteristics Page 20 of 22 Question:

C.010

[1.0 point]

(10.0)

Which ONE (1) of the following conditions would activate an interlock preventing Shim-Safety Rod withdrawal?

a. Radiation Area Monitor = 25 mr/hour.

b. Reactor period = 15 seconds.

c. Log power recorder is out of service.

d. Period amplifier not operable.

Answer:

C.010 c.

Reference:

SAR, Table IX, page 3-41.

Question C.011

[1.0 point]

(11.0)

Which ONE of the following types of detector is utilized in the continuous air monitoring system?

a. Geiger-Mueller tube.

b. Scintillation detector.

c. Ionization chamber.

d. Proportional counter.

Answer:

C.011 a.

Reference:

SAR, page 3-47.

Question C.012

[1.0 point]

(12.0)

Which ONE accident below is designated as the Maximum Hypothetical Accident for the UMRR?

a. Failure of a fueled experiment.

b. Fuel element handling accident.

c. Loss of coolant accident.

d. Failure of a movable experiment.

Answer:

C.012 a.

Reference:

SAR, page 9-19.

Section C - Facility and Radiation Monitoring Systems Page 21 of 22 Question C.013

[1.0 point]

(13.0)

Which ONE of the following is used when the reactor is operating to reduce the buildup of Ar41 in the reactor bay?

a. Operation of the ventilation system, which releases the Ar41 through the stack.

b. Diffuser pumps which decrease the release of Ar41 from the pool.

c. Purification system via the ion bed.

d. None required due to the relatively short half-life of Ar41 (seven seconds).

Answer:

C.013 a.

Reference:

SAR § Question C.014

[1.0 point]

(14.0)

On a scram which ONE of the following correctly describes the positions of the regulating rods and the shim/safety magnets. The regulating rod will

a. remain where it was for the scram and the shim/safety magnets will drive in.

b. drive in and the shim/safety magnets will drive in.

c. drive in and the shim/safety magnets will remain where they were for the scram.

d. remain where it was for the scram and the shim/safety magnets will remain where they were for the scram.

Answer:

C.014 d.

Reference:

SAR, § 3.4.7, p. 3-28.

Section A:

Theory, Thermodynamics, and Facility Operating Characteristics Page 22 of 22 Question C.015

[1.0 point]

(15.0)

Which ONE of the following methods is used to compensate for gamma radiation in a Fission Chamber?

a. Pulses smaller than a height (voltage) are stopped by a pulse-height discriminator circuit from entering the instrument channels amplifier.

b. The chamber contains concentric tubes one of which detects both neutrons and gammas the other only gammas, are wired electronically to subtract the gamma signal, leaving only the signal due to neutrons.

c. The signal travels through a Resistance-Capacitance (RC) circuit, converting the signal to a power change per time period effectively deleting the signal due to gammas.

d. A compensating voltage equal to a predetermined source gamma level is fed into the pre-amplifier electronically removing source gammas from the signal. Fission gammas are proportional to reactor power and therefore not compensated for.

Answer:

C.015 a.

Reference:

Standard NRC Question

ML083390531

Text

SUBJECT:

Dear Dr. Frimpong:

Enclosures:

SUBJECT:

Dear Dr. Frimpong:

Enclosures:

SUMMARY

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