Text

Examination Report No 50-083/OL-16-001, University of Florida Training Reactor
	ML15345A404
Person / Time
Site:	05000083
Issue date:	12/17/2015
From:	Anthony Mendiola; Research and Test Reactors Branch B
To:	Jordan K; Univ of Florida
	Michele DeSouza - 301-415-1169
Shared Package
ML15217A040	List: ML15217A046; ML15286A211; ML15345A404;
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	50-083/OL-16-001
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December 17, 2015 Dr. Kelly Jordan, Director University of Florida Training Reactor Nuclear and Radiological Engineering Department University of Florida P. O. Box 118300 Gainesville, FL 32611

SUBJECT:

EXAMINATION REPORT NO. 50-083/OL-16-01, UNIVERSITY OF FLORIDA TRAINING REACTOR

Dear Dr. Jordan:

During the week of November 16, 2015, the U.S. Nuclear Regulatory Commission (NRC) administered an operator licensing examination at your University of Florida training nuclear reactor. The examinations were conducted according to NUREG-1478, "Operator Licensing Examiner Standards for Research and Test Reactors," Revision 2. Examination questions and preliminary findings were discussed with those members of your staff identified in the enclosed report at the conclusion of the examination.

In accordance with Title 10 of the Code of Federal Regulations, Section 2.390, a copy of this letter and the enclosures will be available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records (PARS) component of NRC's Agencywide Documents Access and Management System (ADAMS). ADAMS is accessible from the NRC 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 Ms. Michele DeSouza at (301) 415-1169 or via e-mail Michele.DeSouza@nrc.gov.

Sincerely,

/RA/

Anthony J. Mendiola, Chief Research and Test Reactors Oversight Branch Division of Policy and Rulemaking Office of Nuclear Reactor Regulation Docket No.50-083

Enclosures:

1. Examination Report No. 50-083/OL-16-01

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

Dr. Kelly Jordan December 17, 2015 Director of the University of Florida Training Reactor Nuclear and Radiological Engineering Department University of Florida P. O. Box 118300 Gainesville, FL 32611

SUBJECT:

EXAMINATION REPORT NO. 50-083/OL-16-01, UNIVERSITY OF FLORIDA TRAINING REACTOR

Dear Dr. Jordan:

During the week of November 16, 2015, the U.S. Nuclear Regulatory Commission (NRC) administered an operator licensing examination at your Pennsylvania State University Breazeale nuclear reactor. The examinations were conducted according to NUREG-1478, "Operator Licensing Examiner Standards for Research and Test Reactors," Revision 2.

Examination questions and preliminary findings were discussed with those members of your staff identified in the enclosed report at the conclusion of the examination.

In accordance with Title 10 of the Code of Federal Regulations, Section 2.390, a copy of this letter and the enclosures will be available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records (PARS) component of NRC's Agencywide Documents Access and Management System (ADAMS). ADAMS is accessible from the NRC 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 Ms. Michele DeSouza at (301) 415-1169 or via e-mail Michele.DeSouza@nrc.gov.

Sincerely,

/RA/

Anthony J. Mendiola, Chief Research and Test Reactors Oversight Branch Division of Policy and Rulemaking Office of Nuclear Reactor Regulation Docket No.50-083

Enclosures:

1. Examination Report No. 50-083/OL-16-01

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

PUBLIC RidsNRRDPRPRTA RidsNRRDPRPRTB ADAMS ACCESSION #: ML15345A404 TEMPLATE #:NRR-079 OFFICE PROB:CE IOLB:LA E PROB:BC NAME MDeSouza CRevelle AMendiola DATE 12/02/2015 12/11/2015 12/17 /2015 OFFICIAL RECORD COPY

University of Florida Training Reactor Docket No.50-083 cc:

Administrator Department of Environmental Regulation Power Plant of Siting Section State of Florida 2600 Blair Stone Road Tallahassee, FL 32301 State Planning and Development Clearinghouse Office of Planning and Budgeting Executive Office of the Governor The Capitol Building Tallahassee, FL 32301 Chief, Bureau of Radiation Control Department of Health 4052 Bald Cypress Way Tallahassee, FL 32399-1741 Test, Research and Training Reactor Newsletter P.O. Box 118300 University of Florida Gainesville, FL 32611-8300 Brian Shea, Reactor Manager University of Florida 340 Weil Hall P.O. Box 116134 Gainesville, FL 32611 Dean Cammy Abernathy University of Florida College of Engineering PO Box 116550 Gainesville, FL 32611

U. S. NUCLEAR REGULATORY COMMISSION OPERATOR LICENSING INITIAL EXAMINATION REPORT REPORT NO.: 50-083/OL-16-01 FACILITY DOCKET NO.: 50-083 FACILITY LICENSE NO.: R-56 FACILITY: University of Florida Training Reactor EXAMINATION DATES: November 17-19, 2015 SUBMITTED BY: _____________/RA/__________ ____12/15/2015__

Michele DeSouza, Chief Examiner Date

SUMMARY

During the week of November 16, 2015, the NRC administered operator licensing examinations to three Senior Reactor Operator candidates. All Senior Reactor Operator candidates passed all applicable portions of the examinations.

REPORT DETAILS

1. Examiner: Michele DeSouza, Chief Examiner, NRC

2. Results:

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

3. Exit Meeting:

Michele C. DeSouza, Chief Examiner, NRC Brian Shea, Associate Director Upon completion of the examinations, the NRC examiner met with facility staff representative to discuss the results. At the conclusion of the meeting, the NRC examiner thanked the facility for their support in the administration of the examinations.

ENCLOSURE 1

U. S. NUCLEAR REGULATORY COMMISSION NON-POWER REACTOR LICENSE EXAMINATION FACILITY: University of Florida Training Reactor REACTOR TYPE: Argonaut DATE ADMINISTERED: 11/18/2015 CANDIDATE: _______________________

INSTRUCTIONS TO CANDIDATE:

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

% OF CATEGORY % OF CANDIDATE'S CATEGORY VALUE TOTAL SCORE VALUE CATEGORY 19.00 33.3 A. REACTOR THEORY, THERMODYNAMICS AND FACILITY OPERATING CHARACTERISTICS 20.00 33.3 B. NORMAL AND EMERGENCY OPERATING PROCEDURES AND RADIOLOGICAL CONTROLS 20.00 33.3 C. FACILITY AND RADIATION MONITORING SYSTEMS 59.00 % TOTALS FINAL GRADE All work done on this examination is my own. I have neither given nor received aid.

Candidate's Signature ENCLOSURE 2

Category A: Reactor Theory, Thermodynamics, & Facility Operating Characteristics ANSWER SHEET Multiple Choice (Circle or X your choice)

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

A01 a b c d ___

A02 a b c d ___

A03 a ___ b ___ c ___ d ___ (0.25 each)

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 ___

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

Category B: Normal/Emergency Operating Procedures and Radiological Controls ANSWER SHEET Multiple Choice (Circle or X your choice)

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

B01 a b c d ___

B02 a b c d ___

B03 a b c d ___

B04 a b c d ___

B05 a b c d ___

B06 a b c d ___

B07 a b c d ___

B08 a b c d ___

B09 a ___ b ___ c ___ (0.33 each)

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 ___ (0.25 each)

B18 a b c d ___

B19 a b c d ___

B20 a b c d ___

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

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

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

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 ___ (0.5 each)

C19 a b c d ___

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

EQUATION SHEET

( )2 eff = 0.1sec 1 Q = m cP T = m H =UAT Pmax =

(2 )

t P = P0 e S S SCR = * =1x104 sec 1 K eff eff +

SUR = 26 .06

( ) (

CR1 1 K eff1 = CR2 1 K eff 2 ) CR1 ( 1 ) = CR2 ( 2 )

(1 ) M=

1

= 2 CR P = P0 10SUR(t )

P= P0 1 K eff CR1 1 K eff1 1 K eff

M= SDM = =

1 K eff 2 K eff

0.693 K eff 2 K eff1

+ T1 =

eff + 2 K eff1 K eff 2 K eff 1

= DR = DR0 e t 2 DR1 d1 = DR2 d 2 2

K eff 6 Ci E (n) ( 2 )2 = (1 )2 DR =

R2 Peak2 Peak1 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

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

c. , Lf, Lt, p, , f

d. , Lf, Lt, p, , f QUESTION A.02 [1.0 point]

Which ONE of the following is the major source of energy (heat) generated after SHUTDOWN?

a. Prompt gamma ray

b. Fission product decay

c. Delayed neutrons

d. Hydrogen gas QUESTION A.03 [1.0 point, 0.25 each]

Match the following Neutron Interactions in Column A with the appropriate definition in Column B (each used only once)

Column A Column B

a. Fission 1. Neutron enters nucleus, forms a compound nucleus, then decays by gamma emission

b. Radiative capture 2. Particle enters nucleus, forms a compound nucleus and is excited enough to eject a new particle with incident neutron remaining in nucleus

c. Scattering 3. Nucleus absorbs neutron and splits into two similarly sized parts

d. Particle ejection 4. Nucleus is struck by a neutron and emits a single neutron

Category A: Reactor Theory, Thermodynamics, and Facility Operating Characteristics QUESTION A.04 [1.0 point]

Reactor is critical. What would be the corresponding keff when removing 0.05 k/k from its criticality?

a. 0.9951

b. 0.9524

c. 0.9750

d. 1.0526 QUESTION A.05 [1.0 point]

Which ONE of the following is the reason for an installed neutron source within the reactor core? A startup without an installed neutron source _______.

a. Is impossible as no neutrons would be available to start up the reactor

b. Can be compensated for by adjusting the compensating voltage on the source range detector

c. Could result in a very short period due to the reactor going critical before the neutron population is built up high enough to be read on nuclear instrumentation

d. Would be very slow due to the long time to build up the neutron population from such a low level QUESTION A.06 [1.0 point]

A reactor is slightly supercritical with the following values for each of the factors in the six-factor formula:

Fast fission factor 1.05 Fast non-leakage probability 0.80 Resonance escape probability 0.90 Thermal non-leakage probability 0.92 Thermal utilization factor 0.80 Reproduction factor 1.86 A control rod is inserted to bring the reactor back to critical. Assuming all other factors remain unchanged, the new value for the thermal utilization factor is:

a. 0.698

b. 0.702

c. 0.743

d. 0.773

Category A: Reactor Theory, Thermodynamics, and Facility Operating Characteristics QUESTION A.07 [1.0 point]

What is the condition of the reactor when k = ? (Note: not eff)

a. Subcritical

b. Critical

c. Super critical

d. Prompt critical QUESTION A.08 [1.0 point]

Given a source strength of 150 neutrons per second (N/sec) and a multiplication factor of 0.7, which ONE of the following is the expected stable neutron count rate?

a. 150 N/sec

b. 250 N/sec

c. 400 N/sec

d. 500 N/sec QUESTION A.09 [1.0 point]

Which ONE of the following isotopes will readily absorb neutrons when it interacts with neutrons?

a. Hydrogen-1

b. Oxygen-16

c. Boron-10

d. Uranium-235 QUESTION A.10 [1.0 point]

Which ONE of the following is the stable reactor period which will result in a power rise from 1%

to 100% power in 120 seconds?

a. 10 seconds

b. 13 seconds

c. 26 seconds

d. 80 seconds

Category A: Reactor Theory, Thermodynamics, and Facility Operating Characteristics QUESTION A.11 [1.0 point]

The following shows part of a decay chain for the radioactive element Pa-234:

234 91Pa 92U234 This decay chain is an example of _______ decay.

a. Alpha

b. Beta

c. Gamma

d. Neutron QUESTION A.12 [1.0 point]

The reactor is on a CONSTANT positive period. Which ONE of the following power changes will take the SHORTEST time to complete?

a. From 100 kW to 150 kW

b. From 10 kW to 20 kW

c. From 10 W to 30 W

d. From 1 W to 5 W QUESTION A.13 [1.0 point]

Inelastic scattering can be described as a process whereby a neutron collides with a nucleus and leaves the nucleus in an excited state. The nucleus later:

a. emits a gamma ray and a neutron with lower energy

b. emits a gamma ray and a neutron with higher energy

c. emits a beta particle and a neutron with lower energy

d. emits an alpha particle ONLY QUESTION A.14 [1.0 point]

A subcritical reactor, keff is increased from 0.914 to 0.965. Which ONE of the following is the amount of reactivity that was added to the core?

a. 3.64%k/k

b. 4.38%k/k

c. 5.78%k/k

d. 6.57%k/k

Category A: Reactor Theory, Thermodynamics, and Facility Operating Characteristics QUESTION A.15 [1.0 point]

Which ONE of the following statements correctly describes thermal neutrons?

a. A neutron that experiences an increase in energy levels after collisions with larger atoms of the moderator

b. A neutron that experiences a linear decrease in energy as the temperature of the moderator increases

c. A neutron that experiences no net change in energy after several collisions with atoms of the moderator

d. A neutron at resonant epithermal energy levels that causes fissions to occur in U-238 QUESTION A.16 [1.0 point]

Which ONE of the following types of neutrons has a mean neutron generation lifetime of 12.5 seconds?

a. Prompt

b. Delayed

c. Fast

d. Thermal QUESTION A.17 [1.0 point]

Which ONE of the following conditions would INCREASE the shutdown margin of a reactor?

a. Inserting an experiment adding positive reactivity

b. Depletion of Uranium fuel

c. Depletion of a burnable poison

d. Lowering moderator temperature if the moderator temperature coefficient is negative QUESTION A.18 [1.0 point]

Two common FISSION PRODUCTS that have especially large neutron cross sections and play a significant role in reactor physics are Xe-135 and _________.

a. Nitrogen-16

b. Argon-41

c. Iodine-131

d. Samarium-149

Category A: Reactor Theory, Thermodynamics, and Facility Operating Characteristics QUESTION A.19 [1.0 point]

Which ONE of the following parameter changes will require control rod INSERTION to maintain constant power level following the change?

a. Buildup of samarium in the core

b. Coolant water temperature increase

c. Insertion of a void into the core

d. Removal of an experiment containing cadmium

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

Category B: Normal/Emergency Operating Procedures and Radiological Controls QUESTION B.01 [1.0 point]

Which ONE of the following conditions is a violation of UFTR Technical Specifications, reactor primary coolant water?

a. Primary coolant dump valve is energized

b. Primary coolant resistivity is 0.6 M-cm

c. Primary coolant core level >2 inches above the fuel

d. Primary coolant water pH is 7.5 QUESTION B.02 [1.0 point]

In accordance with UFTR emergency plan, which one of following categories is defined as an accident that is predicted to have insufficient radiological consequence outside the operations boundary to warrant taking protective measures and no releases of radioactive material requiring off-site responses are expected is:

a. Class 0, events less severe than lowest category

b. Class I, unusual event

c. Class II, alert

d. Class III, site area emergency QUESTION B.03 [1.0 point]

A two curie source emits a 2MeV gamma 100% of the time. The source will be placed in the low level storage building. How far from the source should a high radiation area sign be posted?

a. Not required

b. 10.5 feet

c. 12.5 feet

d. 15.5 feet QUESTION B.04 [1.0 point]

Which ONE of the following materials shall NOT be irradiated in the reactor core?

a. Any corrosive material

b. Any explosive material

c. Any movable experiment

d. Any radioactive material

Category B: Normal/Emergency Operating Procedures and Radiological Controls QUESTION B.05 [1.0 point]

Based on the UFTR Requalification Plan, each operator must perform the functions of a licensed operator to maintain an active operators license a MINIMUM of ________.

a. 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months per year

b. 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months per quarter

c. 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months per month

d. 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months per quarter QUESTION B.06 [1.0 point]

Calculate an individuals total whole body dose given the individual received the following doses: 5 mrad of alpha, 10 mrad of gamma, and 10mrad of neutron (unknown energy)

a. 190 mrem

b. 200 mrem

c. 210 mrem

d. 220 mrem QUESTION B.07 [1.0 point]

Which ONE of the following is the radiation dose limit for the public in an unrestricted area?

a. No limit

b. 2 rem in a year

c. 2 rem in any one hour

d. 2 mrem in any one hour QUESTION B.08 [1.0 point]

What UFTR emergency classification is identified if any two area radiation monitors in the reactor cell read in excess of 500 mRad/hr?

a. Class 0, events less severe than lowest category

b. Class I, unusual event

c. Class II, alert

d. Class III, site area emergency

Category B: Normal/Emergency Operating Procedures and Radiological Controls QUESTION B.09 [1.0 point, 0.25 each]

Identify each of the following surveillances as a channel check (CHECK), a channel test (TEST),

or a channel calibration (CAL). Write the correct answer on your answer sheet next to the space given for each example listed below

a. During performance of the daily checklist, you compare the readings of radiation area monitor one and radiation monitor two

b. During performance of the daily checklist, you press the scram button to verify a scram on the safety system channel

c. Adjustment of the wide range monitor channel in accordance with recent data collected during a reactor power calibration

d. You expose a 2 mCi check source to the continuous air monitor detector to verify that its output is operable QUESTION B.10 [1.0 point]

You are standing three feet from a radiation field of 250 mR/hr. What is your dose rate at 9 feet away from the source?

a. 24 mR/hr

b. 28 mR/hr

c. 32 mR/hr

d. 36 mR/hr QUESTION B.11 [1.0 point]

Per UFTR Technical Specifications, the absolute reactivity worth of any single experiment shall be ________ and the total absolute reactivity worth of all experiments shall be __________.

a. 0.4% k/k and 1.6% k/k

b. 0.5% k/k and 1.5% k/k

c. 0.6% k/k and 1.4% k/k

d. 0.7% k/k and 1.3% k/k

Category B: Normal/Emergency Operating Procedures and Radiological Controls QUESTION B.12 [1.0 point]

Which ONE of the following individuals is NOT required during fuel transfer operations?

a. Supervisor in charge (SRO)

b. Control room operator (RO)

c. Radiation control person

d. Facility director QUESTION B.13 [1.0 point]

In the event of a UFTR-related emergency, the SECONDARY location for the emergency support center is:

a. Reactor building 557

b. Nuclear Science Center, building 634

c. Service drive behind Nuclear Science Center

d. Offsite QUESTION B.14 [1.0 point]

A power run above _________ kW will require a MINIMUM of ________minutes prior to entry into the equipment pit to allow for Nitrogen-16 activity to decay.

a. 1kW 10 minutes

b. 1kW 15 minutes

c. 10kW 10 minutes

d. 10kW 15 minutes QUESTION B. 15 [1.0 point]

Minor modifications to the original procedures may be made by ____________ but must be approved by ___________ within 14 days.

a. Facility Manager RSRS

b. Reactor Manager Facility Director

c. Senior Reactor Operator Reactor Manager

d. Reactor Operator Senior Reactor Operator

Category B: Normal/Emergency Operating Procedures and Radiological Controls QUESTION B.16 [1.0 point]

Which ONE of the following does NOT require the presence of a Senior Reactor Operator?

a. Relocation of an experiment worth $0.50

b. Initial startup and approach to power

c. Recovery from unscheduled shutdown

d. Control blade relocations within the reactor core QUESTION B.17 [1.0 point, 0.25 each]

Match the appropriate radiation unit in Column A with its definition in Column B.

Column A Column B

a. Curie 1. Equal to absorbed dose of 100 ergs/gram

b. Roentgen 2. Amount of radioactive material decaying at a rate of 3.7x1010

c. RAD 3. Amount of x-ray or gamma ray leading to the absorption of 88 ergs/gram in air

d. Dose Equivalent 4. Equal to absorbed dose in RAD times quality factor QUESTION B.18 [1.0 point]

Which of the following parameters are used to evaluate the limiting safety system settings (LSSS)?

a. Reactor period, thermal power, primary coolant inlet temperature, and primary coolant outlet temperature

b. Thermal power, primary coolant inlet temperature, primary coolant outlet temperature, and primary pH

c. Reactor period, water tank level, primary coolant inlet temperature, and primary pH

d. Thermal power, reactor period, primary coolant outlet temperature, and primary pH

Category B: Normal/Emergency Operating Procedures and Radiological Controls QUESTION B.19 [1.0 point]

How long will it take a 50 Curie source, with a half-life of 5.26 years, to decay to 2 Curie?

a. 10.5 Years

b. 15.5 Years

c. 24.5 Years

d. 35.5 Years QUESTION B.20 [1.0 point]

Which ONE of the following is the definition for Annual Limit on Intake?

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

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

c. 10CFR20 derived limit, based on a Committed Effective Dose Equivalent of 5 rem whole body or 50 rems to any individual organ, for the amount of radioactive material inhaled or ingested in a year by an adult worker

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

(***** End of Category B *****)

Category C: Facility and Radiation Monitoring Systems QUESTION C.01 [1.0 point]

Prior to discharge into the sanitary sewer system the waste holding tanks must be sampled and analyzed. Which individuals signatures are required for approval of this release?

a. Reactor operator and radiation control technician

b. Senior reactor operator and radiation control officer

c. Radiation control officer and reactor manager

d. Reactor manager and facility director QUESTION C.02 [1.0 point]

Which ONE of the following WILL NOT result in a reactor trip WITH dump of primary water?

a. Period <3 seconds

b. AC power failure

c. Loss of primary coolant pump

d. HV >125% to safety channel #2 QUESTION C.03 [1.0 point]

Upon initiation of the evacuation siren which ONE of the following should automatically occur?

a. Differential pressure across the emergency exhaust air filter will increase

b. Dilution blower is energized and pushes air through the facility

c. Primary coolant pump increases flow rate

d. Stack vent and dilute fans are secured QUESTION C.04 [1.0 point]

Which ONE of the following materials is used at UFTR as the neutron absorbing material?

a. H2O

b. SbBe and PuBe sources

c. Cadmium tipped control blades

d. Thermal column

Category C: Facility and Radiation Monitoring Systems QUESTION C.05 [1.0 point]

UFTR Technical Specifications requires fuel elements be stored in a safe array where the MAXIMUM keff is _______.

a. 0.6

b. 0.7

c. 0.8

d. 0.9 QUESTION C.06 [1.0 point]

A heat exchanger leak can be determined by which ONE of the following methods?

a. Secondary pH decrease due to the transfer of the water to the primary

b. Primary flow rate increase

c. Secondary flow rate decrease

d. Resistivity decrease QUESTION C.07 [1.0 point]

Which ONE of the following is NOT a purpose of the shield tank?

a. Source of shielding

b. Provides access to high flux area for large experiments

c. Demineralizer water source for the primary system

d. Serves as a heat sink for experiments QUESTION C.08 [1.0 point]

Which primary coolant system feature eliminates the formation of vortices in the storage tank?

a. Heat exchanger

b. High pressure flow

c. Diffuser

d. Storage tank coolant vent line

Category C: Facility and Radiation Monitoring Systems QUESTION C.09 [1.0 point]

Which ONE of the following produces a signal proportional to the logarithm of neutron flux?

a. High voltage power supply

b. Pico ammeter

c. Linear amplifier

d. Log-n amplifier QUESTION C.10 [1.0 point]

In the event of a loss of power situation, DC and diesel electrical power systems will NOT provide power to which ONE of the following?

a. Dump valve

b. Physical protection systems

c. Emergency lighting

d. Radiation monitoring QUESTION C.11 [1.0 point]

Which device at UFTR protects the university water supply from contaminants?

a. Backflow preventer

b. Rupture disk

c. Aluminum baffle

d. Dump valve QUESTION C.12 [1.0 point]

UFTR exhaust system consists of which ONE of the following?

a. Activated charcoal and pressure monitoring filters

b. High Efficiency and conventional filters

c. Roughing and absolute filters

d. High efficiency and activated charcoal filters

Category C: Facility and Radiation Monitoring Systems QUESTION C.13 [1.0 point]

Which ONE of the following parameters is measured in the secondary coolant system?

a. Conductivity

b. Flow rate

c. Water storage level

d. pH QUESTION C.14 [1.0 point]

UFTR technical specifications requires area radiation monitoring systems low level alarm at

_______ and high level alarm at ________?

a. 2000 cps / 4000 cps

b. 4000 cps / 10000 cps

c. 2.5mR/hr / 10 mR/hr

d. 5 mR/hr / 25 mR/hr QUESTION C.15 [1.0 point]

Which region of the pulse size versus applied voltage characteristic curve does a fission chamber operate?

a. Proportional

b. Limited proportional

c. Geiger-Mueller

d. Ion chamber QUESTION C.16 [1.0 point]

UFTR pneumatic transfer system uses ______ to transfer capsules in and out of the reactor core.

a. Compressed air

b. Compressed nitrogen

c. Argon

d. Helium

Category C: Facility and Radiation Monitoring Systems QUESTION C.17 [1.0 point]

Which ONE of the following is NOT a function of the control blade drive inhibit system?

a. Reactor period 10 seconds or greater

b. Period greater than 30 seconds in automatic mode

c. Safety channels 1 and 2 calibrate switch in OPERATE position

d. Raising two or more blades simultaneously QUESTION C.18 [1.0 point]

Following a change in core configuration at UFTR, which method will be used for the initial startup?

a. Count rate versus k-effective

b. Blade position versus temperature

c. Positive period method

d. Inverse multiplication QUESTION C.19 [2.0 points, 0.5 each]

The following, figures 7-3 and 7-4 depict UFTR nuclear instrumentation schematics. Match the chambers (column B) supplying information to each of the nuclear instrumentation channels (column A).

Column A Column B

a. 1. Uncompensated Ion Chamber

b. 2. Fission Chamber

c. 3. B-10 Proportional Counter

d. 4. Compensated Ion Chamber

Category C: Facility and Radiation Monitoring Systems Category C: Facility and Radiation Monitoring Systems

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

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

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

Reference:

DOE Fundamentals Handbook Nuclear Physics and Reactor Theory, Volume 2, Module 1 A.02 Answer: b

Reference:

DOE Fundamentals Handbook Nuclear Physics and Reactor Theory, Volume 1, Module 1, Page 43-46 A.04 Answer: b

Reference:

=(k-1)/k-0.051=k-(-0.05k)=k(1+0.05)k=1/1.05 =0.9524 A.05 Answer: c

Reference:

Burn, Introduction to Nuclear Reactor Operations, Section 5.2.2, Pages 5 5-4 A.06 Answer: d

Reference:

K eff = 1.05*0.80*0.90*0.92*1.86*x X= 1/1.294 = 0.773 A.07 Answer: c

Reference:

LaMarsh, Introduction to Nuclear Engineering, Page 340-341 (1-B)k=1 manipulated reads k=1/(1-B)

A.08 Answer: d

Reference:

CR=S/(1-k)150/(1-0.7) = 500 N/sec A.09 Answer: c

Reference:

Burn, Introduction to Nuclear Reactor Operations, Section 2.5.1, Pages 2-38-43 A.10 Answer: c

Reference:

P = P0 et/T --> T= t/Ln(P/ P0 )

T= 120/Ln(100 ); T = 26 sec.

A.11 Answer: b

Reference:

Chart of the Nuclides A.12 Answer: a

Reference:

P=Poet/Tt=T*ln(P/Po) assume constant period=1 The smallest ratio of P/Po is the shortest time to complete

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

Reference:

Burn, Introduction to Nuclear Reactor Operations, Section 3.3.4, Page 3-20&21

=(keff2-keff1)/(keff1*keff2) = (0.965-0.914)/(0.965*0.914) = 0.0578k/k=5.78%k/k A.15 Answer: c

Reference:

DOE Fundamentals Handbook Nuclear Physics and Reactor Theory, Volume 1, Module 2 A.16 Answer: b

Reference:

DOE Handbook Vol. 1 Module 2, Section 3.0 A.17 Answer: b

Reference:

Burn, Introduction to Nuclear Reactor Operations, Section 6.2.3 A.18 Answer: d

Reference:

Burn, Introduction to Nuclear Reactor Operations, Section 8.1, Page 8-1 A.19 Answer: d

Reference:

NRC Standard question and Previous NRC Exam 2005, Insertion of a control rod inserts negative reactivity to balance the positive reactivity added when removing a neutron absorber A.20 Answer: a

Reference:

Burn, Introduction to Nuclear Reactor Operations, Section 4.2

Category B: Normal/Emergency Operating Procedures and Radiological Controls B.1 Answer: d

Reference:

UFTR TS 3.3 B.2 Answer: b

Reference:

UFTR E-plan section 4.0 - 4.4 B.3 Answer: d

Reference:

I=6CEn=R/hr@ft.2Ci x 2Mev x 100% = 24 R/hr@ (1ft)2 =

24 R/hr = 0.1 R/hr@ D2 = 240 R/hr = 15.5 ft.

B.4 Answer: b

Reference:

UFTR TS 3.6 B.5 Answer: d

Reference:

10CFR55.59 B.6 Answer: c

Reference:

5mrad Alpha x 20=100mrem, 10mrad Gamma x 1=10mrem, 10mrad neutron x 10 = 100mrem 100mrem+10mrem+100mrem= 210mrem B.7 Answer: d

Reference:

10CFR20.1301(a)(2)

B.8 Answer: c

Reference:

UFTR E-plan, Table 5.1 B.9 Answer: a (check), b (test), c (cal) , d (test)

Reference:

UFTR TS definitions B.10 Answer: b

Reference:

I1D12=I2D22 250mR/hr@(3ft)2=I2@(9ft)2 28mR/hr B.11 Answer: c

Reference:

UFTR TS 3.6(1) & 3.6(2)

B.12 Answer: d

Reference:

UFTR SOP-C.1, Page 5 B.13 Answer: c

Reference:

UFTR E-plan, section 8.1 and definitions

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

Reference:

UFTR SOP-A.1, 4.2.2 B.15 Answer: b

Reference:

UFTR TS 6.4 & UFTR Requalification and Recertification Training Manual, Page 60 B.16 Answer: a

Reference:

UFTR TS 6.1.3 B.17 Answer: a (2), b(3), c(1), d(4)

Reference:

10CFR20.1003, 1004, & 1005 B.18 Answer: a

Reference:

UFTR TS 2.2 B.19 Answer: c

Reference:

T A = A*e -t 2Ci = 50Ci* e -(t)

Ln(2/50) = -ln2/5.27 yr*(t) --> -3.2189/-0.1315 solve for t: 24.47 years B.20 Answer: c

Reference:

10CFR20.1003

Category C: Facility and Radiation Monitoring Systems C.01 Answer: c

Reference:

UFTR SOP D.7 C.02 Answer: c

Reference:

UFTR SAR 7.3.1 & 7.3.2 C.03 Answer: d

Reference:

UFTR Training Manual VI.C.1.b C.04 Answer: c

Reference:

UFTR Training Manual I.C.

C.05 Answer: c

Reference:

UFTR Training Manual VII.B.1 C.06 Answer: d

Reference:

UFTR SAR 5.1.2 C.07 Answer: c

Reference:

UFTR Training Manual III.B.

C.08 Answer: c

Reference:

UFTR SAR 5.1.1 C.09 Answer: d

Reference:

UFTR SAR 7.2.2.1.2 C.10 Answer: a

Reference:

UFTR SAR 8.4 & 8.5 C.11 Answer: a

Reference:

UFTR Training Manual VI.B.3.c.(3)

C.12 Answer: c

Reference:

UFTR SAR 3.3.1 C.13 Answer: b

Reference:

UFTR TS 3.3

Category C: Facility and Radiation Monitoring Systems C.14 Answer: d

Reference:

UFTR TS Table 3-3 C.15 Answer: a

Reference:

NRC standard question C.16 Answer: b

Reference:

UFTR SOP A.8 C.17 Answer: c

Reference:

UFTR SAR 7.2.3.2 C.18 Answer: d

Reference:

UFTR SOP A.9 C.19 Answer: a(3) b(2) c(4) d(1)

Reference:

UFTR SAR 7.2.2 Figure 7-3 & 7-4

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

Reference:

DOE Fundamentals Handbook Nuclear Physics and Reactor Theory, Volume 2, Module 1 A.02 Answer: b

Reference:

DOE Fundamentals Handbook Nuclear Physics and Reactor Theory, Volume 1, Module 1, Page 43-46 A.04 Answer: b

Reference:

=(k-1)/k-0.051=k-(-0.05k)=k(1+0.05)k=1/1.05 =0.9524 A.05 Answer: c

Reference:

Burn, Introduction to Nuclear Reactor Operations, Section 5.2.2, Pages 5 5-4 A.06 Answer: d

Reference:

K eff = 1.05*0.80*0.90*0.92*1.86*x X= 1/1.294 = 0.773 A.07 Answer: c

Reference:

LaMarsh, Introduction to Nuclear Engineering, Page 340-341 (1-B)k=1 manipulated reads k=1/(1-B)

A.08 Answer: d

Reference:

CR=S/(1-k)150/(1-0.7) = 500 N/sec A.09 Answer: c

Reference:

Burn, Introduction to Nuclear Reactor Operations, Section 2.5.1, Pages 2-38-43 A.10 Answer: c

Reference:

P = P0 et/T --> T= t/Ln(P/ P0 )

T= 120/Ln(100 ); T = 26 sec.

A.11 Answer: b

Reference:

Chart of the Nuclides A.12 Answer: a

Reference:

P=Poet/Tt=T*ln(P/Po) assume constant period=1 The smallest ratio of P/Po is the shortest time to complete

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

Reference:

Burn, Introduction to Nuclear Reactor Operations, Section 3.3.4, Page 3-20&21

=(keff2-keff1)/(keff1*keff2) = (0.965-0.914)/(0.965*0.914) = 0.0578k/k=5.78%k/k A.15 Answer: c

Reference:

DOE Fundamentals Handbook Nuclear Physics and Reactor Theory, Volume 1, Module 2 A.16 Answer: b

Reference:

DOE Handbook Vol. 1 Module 2, Section 3.0 A.17 Answer: b

Reference:

Burn, Introduction to Nuclear Reactor Operations, Section 6.2.3 A.18 Answer: d

Reference:

Burn, Introduction to Nuclear Reactor Operations, Section 8.1, Page 8-1 A.19 Answer: d

Reference:

NRC Standard question and Previous NRC Exam 2005, Insertion of a control rod inserts negative reactivity to balance the positive reactivity added when removing a neutron absorber A.20 Answer: a

Reference:

Burn, Introduction to Nuclear Reactor Operations, Section 4.2

Category B: Normal/Emergency Operating Procedures and Radiological Controls B.1 Answer: d

Reference:

UFTR TS 3.3 B.2 Answer: b

Reference:

UFTR E-plan section 4.0 - 4.4 B.3 Answer: d

Reference:

I=6CEn=R/hr@ft.2Ci x 2Mev x 100% = 24 R/hr@ (1ft)2 =

24 R/hr = 0.1 R/hr@ D2 = 240 R/hr = 15.5 ft.

B.4 Answer: b

Reference:

UFTR TS 3.6 B.5 Answer: d

Reference:

10CFR55.59 B.6 Answer: c

Reference:

5mrad Alpha x 20=100mrem, 10mrad Gamma x 1=10mrem, 10mrad neutron x 10 = 100mrem 100mrem+10mrem+100mrem= 210mrem B.7 Answer: d

Reference:

10CFR20.1301(a)(2)

B.8 Answer: c

Reference:

UFTR E-plan, Table 5.1 B.9 Answer: a (check), b (test), c (cal) , d (test)

Reference:

UFTR TS definitions B.10 Answer: b

Reference:

I1D12=I2D22 250mR/hr@(3ft)2=I2@(9ft)2 28mR/hr B.11 Answer: c

Reference:

UFTR TS 3.6(1) & 3.6(2)

B.12 Answer: d

Reference:

UFTR SOP-C.1, Page 5 B.13 Answer: c

Reference:

UFTR E-plan, section 8.1 and definitions

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

Reference:

UFTR SOP-A.1, 4.2.2 B.15 Answer: b

Reference:

UFTR TS 6.4 & UFTR Requalification and Recertification Training Manual, Page 60 B.16 Answer: a

Reference:

UFTR TS 6.1.3 B.17 Answer: a (2), b(3), c(1), d(4)

Reference:

10CFR20.1003, 1004, & 1005 B.18 Answer: a

Reference:

UFTR TS 2.2 B.19 Answer: c

Reference:

T A = A*e -t 2Ci = 50Ci* e -(t)

Ln(2/50) = -ln2/5.27 yr*(t) --> -3.2189/-0.1315 solve for t: 24.47 years B.20 Answer: c

Reference:

10CFR20.1003

Category C: Facility and Radiation Monitoring Systems C.01 Answer: d

Reference:

NRC standard question C.02 Answer: c

Reference:

UFTR SAR 7.3.1 & 7.3.2 C.03 Answer: d

Reference:

UFTR Training Manual VI.C.1.b C.04 Answer: c

Reference:

UFTR Training Manual I.C.

C.05 Answer: d

Reference:

UFTR TS 5.4 C.06 Answer: d

Reference:

UFTR SAR 5.1.2 C.07 Answer: c

Reference:

UFTR Training Manual III.B.

C.08 Answer: c

Reference:

UFTR SAR 5.1.1 C.09 Answer: d

Reference:

UFTR SAR 7.2.2.1.2 C.10 Answer: a

Reference:

UFTR SAR 8.4 & 8.5 C.11 Answer: a

Reference:

UFTR Training Manual VI.B.3.c.(3)

C.12 Answer: c

Reference:

UFTR SAR 3.3.1 C.13 Answer: b

Reference:

UFTR TS 3.3

Category C: Facility and Radiation Monitoring Systems C.14 Answer: d

Reference:

UFTR TS Table 3-3 C.15 Answer: a

Reference:

NRC standard question C.16 Answer: b

Reference:

UFTR SOP A.8 C.17 Answer: c

Reference:

UFTR SAR 7.2.3.2 C.18 Answer: d

Reference:

UFTR SOP A.9 C.19 Answer: a(3) b(2) c(4) d(1)

Reference:

UFTR SAR 7.2.2 Figure 7-3 & 7-4