ML16014A410

Examination Report No. 50-182/OL-16-01, Purdue University Training Reactor

ML16014A410
Person / Time
Site:	Purdue University
Issue date:	01/20/2016
From:	Anthony Mendiola Research and Test Reactors Branch B
To:	Bean R Purdue University Research Reactor
Michele DeSouza 301-415-1169
Shared Package
ML15286A024	List: ML16014A410 ML16015A022
References
50-182/OL-16-001
Download: ML16014A410 (34)

Text

January 20, 2016 Robert S. Bean, Ph.D.

Director of Radiation Laboratories Purdue University School of Nuclear Engineering 400 Central Drive West Lafayette, IN 47904-2017

SUBJECT:

EXAMINATION REPORT NO. 50-182/OL-16-01, PURDUE UNIVERSITY TRAINING REACTOR

Dear Dr. Bean:

During the week of January 4, 2016, the U.S. Nuclear Regulatory Commission (NRC) administered operator licensing examinations at your Purdue University 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 you at the conclusion of the examinations.

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. 50-182

Enclosures:

1. Examination Report No. 50-182/OL-16-01

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

Robert S. Bean, Ph.D. January 20, 2016 Director of Radiation Laboratories Purdue University School of Nuclear Engineering 400 Central Drive West Lafayette, IN 47904-2017

SUBJECT:

EXAMINATION REPORT NO. 50-182/OL-16-01, PURDUE UNIVERSITY TRAINING REACTOR

Dear Dr. Bean:

During the week of January 4, 2016, the U.S. Nuclear Regulatory Commission (NRC) administered operator licensing examinations at your Purdue University 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 you at the conclusion of the examinations.

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. 50-182

Enclosures:

1. Examination Report No. 50-182/OL-16-01

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

PUBLIC RidsNRRDPRPRTA RidsNRRDPRPRTB ADAMS ACCESSION No.: ML16014A410 TEMPLATE #:NRR-079 OFFICE DPR/PROB/CE DPR/PROB/OLA DPR/PROB/BC NAME MDeSouza CRevelle AMendiola DATE 01/15/2016 01/15 /2016 01/20/2016 OFFICIAL RECORD COPY

Purdue University Training Reactor Docket No. 50-182 cc:

Leah Jamieson, Dean of Engineering Purdue University School of Nuclear Engineering 400 Central Drive West Lafayette, IN 47907 Mayor City of West Lafayette 609 W. Navajo West Lafayette, IN 47906 John H. Ruyack, Manager Epidemiology Res Center/Indoor & Radiological Health Indiana Department of Health 2525 N. Shadeland Ave., E3 Indianapolis, IN 46219 Howard W. Cundiff, P.E., Director Consumer Protection Indiana State Department of Health 2 North Meridian Street, 5D Indianapolis, IN 46204 Clive Townsend, Reactor Supervisor Purdue University School of Nuclear Engineering 400 Central Drive West Lafayette, IN 47907 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.: 50-182/OL-16-01 FACILITY DOCKET NO.: 50-182 FACILITY LICENSE NO.: R-87 FACILITY: Purdue University Training Reactor EXAMINATION DATES: January 6-7, 2016 SUBMITTED BY: ____________/RA/ ___________ ___01/15/2016_

Michele DeSouza, Chief Examiner Date

SUMMARY

During the week of January 4, 2016, the NRC administered operator licensing examinations to two Senior Reactor Operator Instant (SRO-I) candidates. All Senior Reactor Operator candidates passed all applicable portions of the examinations.

REPORT DETAILS

1. Examiners: Michele DeSouza, Chief Examiner, NRC

2. Results:

RO PASS/FAIL SRO PASS/FAIL TOTAL PASS/FAIL Written 0/0 2/0 2/0 Operating Tests 0/0 20 2/0 Overall 0/0 2/0 2/0

3. Exit Meeting:

Michele C. DeSouza, Chief Examiner, NRC Robert S. Bean, Ph.D., Facility Director Upon completion of the examinations, the NRC Examiners met with facility staff representatives to discuss the results. At the conclusion of the meeting, the NRC examiners 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: Purdue University Training Reactor REACTOR TYPE: Lockheed DATE ADMINISTERED: 01/06/2016 CANDIDATE: _______________________

INSTRUCTIONS TO CANDIDATE:

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

% OF CATEGORY % OF CANDIDATE'S CATEGORY VALUE TOTAL SCORE VALUE CATEGORY 20.00 33.3 A. REACTOR THEORY, THERMODYNAMICS AND FACILITY OPERATING CHARACTERISTICS 19.00 33.3 B. NORMAL AND EMERGENCY OPERATING PROCEDURES AND RADIOLOGICAL CONTROLS 19.00 33.3 C. FACILITY AND RADIATION MONITORING SYSTEMS 58.00  % 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 ___

A20 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 ____ d ____ (0.25 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 ___ (0.25 each)

B17 a b c d ___

B18 a b c d ___

B19 a b c d ___

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

Category C - Facility and Radiation Monitoring Systems 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 ___ (0.25 each)

C10 a b c d ___

C11 a ___ b ___ c ___ (0.33 each)

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)

(***** 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 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.02 [1.0 point]

During the time following a reactor scram, reactor power decreases on an 80 second period, which corresponds to the half-life of the longest-lived delayed neutron precursors, which is approximately _________.

a. 20 seconds

b. 40 seconds

c. 55 seconds

d. 80 seconds 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]

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.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]

Given a source strength of 250 neutrons per second (N/sec) and a multiplication factor of 0.5, 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.07 [1.0 point]

Which ONE of the following parameters is MOST significant in determining the differential rod worth of a control rod?

a. Fuel temperature

b. Flux shape

c. Reactor power

d. Rod speed

Category A: Reactor Theory, Thermodynamics, and Facility Operating Characteristics QUESTION A.08 [1.0 point]

How high will the reactor power get given the lowest of the reactor high power scrams set point is 120%, the scram delay time is 0.5 seconds, the reactor is operating at 100% power prior to the scram, and the reactor period is positive 20 second?

a. 113%

b. 119%

c. 123%

d. 125%

QUESTION A.09 [1.0 point]

Which factors of the six factor formula are affected by an INCREASE in core temperature and how are they affected? Lf - Fast non-leakage probability Lt - Thermal non-leakage probability

- Fast fission factor p - Resonance escape probability - Thermal fission factor f - Thermal utilization factor

a. Lf, p, f

b. , Lf, Lt, p

c. , Lf, Lt, p, , f

d. , Lf, Lt, p, , f QUESTION A.10 [1.0 point]

Which ONE of the following is the MAJOR source of energy released during fission?

a. Fission fragments

b. Fission product decay

c. Prompt gamma rays

d. Fission neutrons (kinetic energy)

QUESTION A.11 [1.0 point]

A subcritical reactor, keff is increased from 0.917 to 0.966. Which ONE of the following is the amount of reactivity that was added to the core?

a. 3.64%k/k

b. 4.35%k/k

c. 5.53%k/k

d. 6.53%k/k

Category A: Reactor Theory, Thermodynamics, and Facility Operating Characteristics 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]

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.14 [1.0 point]

Which ONE of the following best describes the difference between reflectors and moderators?

a. Reflectors decrease thermal leakage while moderators decrease fast leakage

b. Reflectors thermalize neutrons while moderators decrease core leakage

c. Reflectors decrease core leakage while moderators thermalize neutrons

d. Reflectors shield against neutrons while moderators decrease core leakage QUESTION A.15 [1.0 point]

Two common FISSION PRODUCTS that have especially large neutron cross sections and play a significant role in reactor physics are Samarium-149 and _________.

a. Nitrogen-16

b. Argon-41

c. Iodine-131

d. Xenon-135

Category A: Reactor Theory, Thermodynamics, and Facility Operating Characteristics QUESTION A.16 [1.0 point]

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

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

a. Alpha

b. Beta

c. Gamma

d. Neutron QUESTION A.17 [1.0 point]

What is ?

a. The fractional change in neutron population per generation

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

c. The time required for the reactor to change by power by a factor of e

d. The fraction of all delayed neutrons that reach thermal energy QUESTION A.18 [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.19 [1.0 point]

Which ONE of the following is a correct statement of how delayed neutrons enhance the ability to control reactor power?

a. Prompt neutrons can cause fissions in both U-235 and U-238 and delayed neutrons can only cause fissions in U-235

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

c. The average number of delayed neutrons produced per fission is higher than the average number of prompt neutrons

d. Delayed neutrons increase the average neutron lifetime that allows a reactor to be controlled

Category A: Reactor Theory, Thermodynamics, and Facility Operating Characteristics QUESTION A.20 [1.0 point]

Reactor is critical. What would be the corresponding keff when removing 0.06 k/k from its criticality?

a. 0.9244

b. 0.9433

c. 0.9753

d. 1.0526

(***** 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 Purdue Technical Specifications, reactor primary coolant?

a. Primary coolant conductivity shall be 5 micromhos/cm

b. Primary coolant resistivity shall be maintained at greater than 330K ohms-cm

c. Primary coolant shall be maintained at least 13 feet above the core

d. Primary coolant pH shall be maintained at 4.5-6.5 QUESTION B.02 [1.0 point]

In accordance with Purdue emergency plan, a fire that may affect any reactor safety systems is an example of what type of classification?

a. General emergency

b. Site emergency

c. Alert

d. Unusual event QUESTION B.03 [1.0 point]

Which ONE of the following is the 10CFR20 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. The 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. The projected Committed Effective Dose Equivalent commitment to individuals that warrants protective action following a release of radioactive material QUESTION B.04 [1.0 point]

In accordance with Purdue E-plan, which individual is responsible for authorizing continued operation of the reactor?

a. SRO

b. Reactor Supervisor

c. Facility Director

d. Emergency Director

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

Per Purdue Technical Specifications, what is the MINIMUM shutdown margin with the most reactive shim rod and regulating rod fully withdrawn?

a. 0.01 k/k

b. 0.03 k/k

c. 0.003 k/k

d. 0.006 k/k QUESTION B.06 [1.0 point]

Purdue emergency plan states the ________ boundary will be the limits of the ________ while the ________ boundary will be the ________.

a. Operations, nuclear engineering laboratories, site, reactor room

b. Operations, reactor room, site, nuclear engineering laboratories

c. Emergency planning zone, nuclear engineering laboratories, site, reactor room

d. Emergency planning zone, electrical engineering building, site, nuclear engineering laboratories QUESTION B.07 [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.08 [1.0 point]

In accordance with Purdue procedure 05-1, what is the lowest level of permission necessary to continue any order-of-magnitude up-scaling of mass work that may impact the Reg Rod worth curve?

a. RO

b. SRO

c. Reactor Supervisor

d. Committee on Reactor Operations

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]

10 CFR 20 limits the annual occupational exposure to the SKIN of an individual to:

a. 5 rem

b. 15 rem

c. 50 rem

d. 100 rem QUESTION B.11 [1.0 point]

The measured value of the power level scram shall be no higher than 1.2 kW. This is an example of:

a. Safety Limit

b. Limiting Safety System Setting

c. Limiting Conditions for Operation

d. Safety Operational Limit

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

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

a. 205 mrem

b. 250 mrem

c. 255 mrem

d. 305 mrem QUESTION B.13 [1.0 point]

A radiation field is 330 mR/hr at 3 feet. What is your dose rate at 2 feet away from the source?

a. 294 mR/hr

b. 366 mR/hr

c. 495 mR/hr

d. 742 mR/hr QUESTION B.14 [1.0 point]

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

a. 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> per quarter

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

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

d. 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> per year QUESTION B.15 [1.0 point]

What emergency classification is identified if an individual is contaminated and injured?

a. General emergency

b. Site emergency

c. Unusual event

d. Non-reactor safety event

Category B: Normal/Emergency Operating Procedures and Radiological Controls QUESTION B.16 [1.0 point, 0.25 each]

Match the appropriate 10CFR part in Column A with the requirements in Column B.

Column A Column B

a. 10CFR19 1. Technical information including the proposed maximum power level

b. 10CFR20 2. Individual radiation exposure data

c. 10CFR50 3. Surveys evaluating the magnitude and extent of radiation levels

d. 10CFR55 4. Medical examination by a physician every two years QUESTION B.17 [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 fissionable material QUESTION B.18 [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

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

A two curie source emits a 2MeV gamma 100% of the time. The source will be placed in the reactor 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

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

Category C: Reactor Theory, Thermodynamics, and Facility Operating Characteristics QUESTION C.01 [1.0 point]

What instrumentation region is associated with the voltage is such that every primary ion produces an avalanche of secondary ions? This region also cannot differentiate between types of radiation.

a. Region I, Recombination

b. Region II, Ionization

c. Region III, Proportional

d. Region V, Geiger-Mueller QUESTION C.02 [1.0 point]

Which ONE of the following safety channels will initiate a reactor scram if the indicated power level exceeds 120% of the licensed power?

a. Safety channel #1

b. Safety channel #2

c. Safety channel #3

d. Safety channel #4 QUESTION C.03 [1.0 point]

Which ONE of the following is the Purdue neutron startup source?

a. Am-Li

b. Am-Be

c. Sb-Be

d. Pu-Be QUESTION C.04 [1.0 point]

When calibrating a Reactor Room RAM which points are used in accordance with PUR-1 Procedure M-5A?

a. 2mR/hr and 20mR/hr

b. 1mR/hr, 7.5mR/hr, and 15mR/hr

c. 2mR/hr, 7.5mR/hr, and 20mR/hr

d. 5mR/hr and 50mR/hr

Category C: Reactor Theory, Thermodynamics, and Facility Operating Characteristics QUESTION C.05 [1.0 point]

Purdue 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]

Which ONE of the following materials is the regulating rod fabricated from?

a. 6061 - Aluminum

b. Boron - Stainless Steel

c. Boron lined Aluminum

d. 304 - Stainless Steel QUESTION C.07 [1.0 point]

Which ONE of the following will initiate a reactor setback?

a. Log count rate < 2 cps

b. 7 second period

c. 12 second period

d. Pool RAM 50 mR/hr QUESTION C.08 [1.0 point]

When determining reactivity worth of the grid plate stainless steel guide tube if the regulating rod position is greater than 10cm what actions must be taken?

a. Continue operation and notify Senior Reactor Operator

b. Terminate experiment and notify Senior Reactor Operator

c. Terminate experiment and notify Reactor Supervisor

d. Terminate experiment and notify Committee On Reactor Operations

Category C: Reactor Theory, Thermodynamics, and Facility Operating Characteristics QUESTION C.09 [1.0 point, 0.25 each]

Match the monitor listed in Column A with the type of detector listed in Column B. (Answers may be used more than once or not at all)

Column A Column B

a. Log-N and Period Channel 1. Geiger-Mueller

b. Linear Channel 2. Uncompensated Ion Chamber

c. RAM 3. Compensated Ion Chamber

d. CAM 4. Scintillation QUESTION C.10 [1.0 point]

Purdue Technical Specification requires the total worth of all movable experiments not to exceed _________ and secured experiments not to exceed _________.

a. 0.003 k/k and 0.005 k/k

b. 0.004 k/k and 0.006 k/k

c. 0.005 k/k and 0.007 k/k

d. 0.006 k/k and 0.008 k/k QUESTION C.11 [1.0 point, 0.33 each]

Match the following limitations in Column A with its specification in Column B Column A Column B

a. Safety Limit 1. Shutdown Margin $1.00

b. Limiting Safety System Setting 2. 530oC

c. Limiting Condition for Operation 3. 1.2 kW QUESTION C.12 [1.0 point]

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

a. Proportional

b. Limited proportional

c. Geiger-Mueller

d. Ion chamber

Category C: Reactor Theory, Thermodynamics, and Facility Operating Characteristics QUESTION C.13 [1.0 point]

The reactor water is analyzed for gross alpha, beta, gamma and ________.

a. H-3

b. N-16

c. Ar-41

d. I-131 QUESTION C.14 [1.0 point]

When using the positive period method which ONE of the following parameters is used?

a. Pool level vs. coolant level

b. Reactivity vs. rod height

c. Temperature vs. period

d. Count rate vs. k-effective QUESTION C.15 [1.0 point]

Fuel assemblies or fueled devices will not exceed what temperature?

a. 90oC

b. 95oC

c. 100oC

d. 110oC QUESTION C.16 [1.0 point]

Which ONE of the following will result in a rod withdrawal interlock?

a. Reactor period 7 seconds

b. High flux 105%

c. Log count rate 2 cps

d. Source range signal/noise ratio of 2

Category C: Reactor Theory, Thermodynamics, and Facility Operating Characteristics QUESTION C.17 [1.0 point]

Solid radioactive waste may be held for decay if the half-life is no more than _______.

a. 10 days

b. 20 days

c. 45 days

d. 60 days QUESTION C.18 [2.0 points, 0.5 each]

Label the JAM, SCRAM, 2/3 Up Limit, Upper Limit switches on the following control rod diagram:

Category C: Reactor Theory, Thermodynamics, and Facility Operating Characteristics

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

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

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

Reference:

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

Reference:

LaMarsh, Introduction to Nuclear Engineering, Page 88 Group 1 is longest lived neutron precursor for thermal fission in U-235 with a half-life of 55.72 seconds A.03 Answer: a3 b1 c4 d2

Reference:

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

Reference:

Burn, Introduction to Nuclear Reactor Operations, Section 2.5.1, Pages 2-38-43 A.05 Answer: c

Reference:

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

Reference:

CR=S/(1-k)150/(1-0.7) = 500 N/sec A.07 Answer: b

Reference:

Burn, Introduction to Nuclear Reactor Operations, Section 7.2 A.08 Answer: c

Reference:

P/Po = 120%, T = 20 seconds, t = 0.5, P/Po = 120 e^0.5/20 = 123%

A.09 Answer: a

Reference:

DOE Fundamentals Handbook Nuclear Physics and Reactor Theory, Volume 2, Module 1 A.10 Answer: a

Reference:

Burn, Introduction to Nuclear Reactor Operations, Table 3.2, Page 3-5b

=(k-1)/k-0.051=k-(-0.05k)=k(1+0.05)k=1/1.05 =0.9524

Category A: Reactor Theory, Thermodynamics, and Facility Operating Characteristics A.11 Answer: c

Reference:

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

=(keff2-keff1)/(keff1*keff2) = (0.966-0.917)/(0.966*0.917) = 0.0553k/k=5.53%k/k 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 A.13 Answer: b

Reference:

Burn, Introduction to Nuclear Reactor Operations, Section 6.2.3 A.14 Answer: c

Reference:

Burn, Introduction to Nuclear Reactor Operations, Section 5.4 A.15 Answer: d

Reference:

Burn, Introduction to Nuclear Reactor Operations, Section 8.1, Page 8-1 A.16 Answer: b

Reference:

Chart of the Nuclides A.17 Answer: b

Reference:

DOE Fundamentals Handbook Nuclear Physics and Reactor Theory, Volume 2, Module 4 A.18 Answer: d

Reference:

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

A.19 Answer: d

Reference:

Burn, Introduction to Nuclear Reactor Operations, Section 3.3.2, Page 3-7 A.20 Answer: b

Reference:

=(k-1)/k-0.061=k-(-0.06k)=k(1+0.06)k=1/1.06 =0.943

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

Reference:

Purdue TS 3.3(a)(b)(c)

B.2 Answer: d

Reference:

Purdue, EP 4, Table 1 B.3 Answer: c

Reference:

10CFR20.1003 B.4 Answer: d

Reference:

Purdue EP 3.1.1 and 8.6 B.5 Answer: a

Reference:

Purdue TS 3.1.a B.6 Answer: b

Reference:

Purdue EP 2.8, 2.16, and 2.26 B.7 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.8 Answer: c

Reference:

Purdue Procedure 05-01(9)

B.9 Answer: a (check), b (test), c (cal) , d (test)

Reference:

Purdue TS definitions 1.1, 1.2, and 1.3 B.10 Answer: c

Reference:

10 CFR 20.1201 B.11 Answer: b

Reference:

Purdue TS 2.2 B.12 Answer: d

Reference:

10mrad Alpha x 20 = 200mrem, 5mrad Gamma x 1 = 5mrem, 10mrad neutron x 10 = 100mrem 200mrem + 5mrem + 100mrem = 305mrem

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

Reference:

I1D12=I2D22 330mR/hr@(3ft)2=I2@(2ft)2 742mR/hr B.14 Answer: a

Reference:

10CFR55.59 B.15 Answer: d

Reference:

Purdue EP 4, Table 1 B.16 Answer: a (2), b(3), c(1), d(4)

Reference:

10CFR19.13(a), 10CFR20.1501(2)(i), 10CFR50.34(1)(ii)(A)

B.17 Answer: b

Reference:

Purdue TS 3.5.c B.18 Answer: d

Reference:

10CFR20.1301(a)(2)

B.19 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.

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

Reference:

NRC standard question C.02 Answer: b

Reference:

PUR-1 SAR, 1986 3.7.3 C.03 Answer: d

Reference:

PUR-1 Operating Principles and Core Characteristics Manual, 2015, Section 1.5.5, Page 13 of 24 C.04 Answer: c

Reference:

PUR-1 Procedure M-5A C.05 Answer: c

Reference:

Purdue TS 5.3 C.06 Answer: d

Reference:

PUR-1 Operating Principles and Core Characteristics Manual, 2015, Section 1.1, Page 5 of 24 C.07 Answer: c

Reference:

Purdue TS Table I & II C.08 Answer: c

Reference:

PUR-1 Procedure 99-SSG-1, Special Considerations step 5 C.09 Answer: a (3), b (2), c (4), d (1)

Reference:

PUR-1 SAR, 1986, PUR-1 Operating Principles and Core Characteristics Manual, 2015, Section 1.5 C.10 Answer: a

Reference:

Purdue TS 3.1f/g C.11 Answer: a(2), b(3), c(1)

Reference:

Purdue TS 2 & 3 C.12 Answer: d

Reference:

NRC standard question

Category C: Facility and Radiation Monitoring Systems C.13 Answer: a

Reference:

Purdue Reactor Water Sampling and Analysis SOP C.14 Answer: b

Reference:

PUR-1 Procedure 95-7RR/SS C.15 Answer: c

Reference:

Purdue TS 5.3.2 C.16 Answer: c

Reference:

Purdue TS Table I C.17 Answer: d

Reference:

Purdue SOP for Disposal of Solid Short Half-Life Radioactive Waste C.18 Answer: a (JAM) b (Upper Limit) c (2/3 Up Limit) d (SCRAM)

Reference:

Figure 1 Shim-Safety Control Rod Drive Schematic