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Examination Report No. 50-027/OL-13-01, Washington State University
	ML12347A183
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Site:	Washington State University
Issue date:	12/12/2012
From:	Gregory Bowman; Division of Policy and Rulemaking
To:	Wall D; Washington State Univ
	Nguyen J
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December 12, 2012 Dr. Donald Wall, Director Nuclear Radiation Center Roundtop Drive Washington State University Pullman, WA 99164-1300

SUBJECT:

EXAMINATION REPORT NO. 50-027/OL-13-01, WASHINGTON STATE UNIVERSITY

Dear Dr. Wall:

During the week of December 3, 2012, the U.S. Nuclear Regulatory Commission (NRC) administered operator licensing examinations at your Washington State University TRIGA 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 at the conclusion of the examination with those members of your staff identified in the enclosed report.

In accordance with Title 10, Section 2.390 of the Code of Federal Regulations, 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 Public Electronic Reading Room). The NRC is forwarding the individual grades to you in a separate letter which will not be released publicly. If you have any questions concerning this examination, please contact Mr. John T. Nguyen at (301) 415-4007 or via internet e-mail John.Nguyen@nrc.gov.

Sincerely,

/RA/

Gregory T. Bowman, Chief Research and Test Reactors Oversight Branch Division of Policy and Rulemaking Office of Nuclear Reactor Regulation Docket No.50-027

Enclosures:

1. Examination Report No. 50-027/OL-13-01

2. Written Exam with facility comments incorporated cc: Corey Hines, Reactor Supervisor, Washington State University cc: w/o enclosures: See next page

ML12347A183 OFFICE PROB:CE IOLB:LA E PROB:BC NAME JNguyen CRevelle GBowman DATE 12/11 /2012 12/12/2012 12/12 /2012 Washington State University Docket No.50-027 cc:

Director Division of Radiation Protection Department of Health 7171 Cleanwater Lane, Bldg #5 P.O. Box 47827 Olympia, WA 98504-7827 Mr. David Clark Director, Radiation Safety Office Washington State University P.O. Box 641302 Pullman, WA 99164-1302 Dr. Ken Nash Chair, Reactor Safeguards Committee Nuclear Radiation Center Washington State University P.O. Box 641300 Pullman, WA 99164-1300 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.: 50-27/OL-13-01 FACILITY DOCKET NO.: 50-27 FACILITY LICENSE NO.: R-76 FACILITY: Washington State University TRIGA Reactor EXAMINATION DATES: December 4, 2012 SUBMITTED BY: _______/RA/ _______________ __12/11/12_

John T. Nguyen, Chief Examiner Date

SUMMARY

During the week of December 3, 2012, the NRC administered operator licensing examination to one Reactor Operator (RO) license candidate. The license candidate passed all applicable portions of the examinations.

REPORT DETAILS

1. Examiners: John T. Nguyen, Chief Examiner, NRC

2. Results:

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

3. Exit Meeting:

John T. Nguyen, Chief Examiner, NRC Paulette Torres, Project Manager, NRC Corey Hines, Reactor Supervisor, Washington State University At the conclusion of the site visit, the examiner met with representative of the facility staff to discuss the results of the examinations. The facility licensee had no comments on the written examination except recommendation of changing the answer key on Question B.17, Question C.4, and Question C.12.

ENCLOSURE 1

U. S. NUCLEAR REGULATORY COMMISSION NON-POWER REACTOR LICENSE EXAMINATION FACILITY: Washington State University REACTOR TYPE: TRIGA DATE ADMINISTERED: 12/4/2012 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 20.00 33.3 B. NORMAL AND EMERGENCY OPERATING PROCEDURES AND RADIOLOGICAL CONTROLS 20.00 33.3 C. FACILITY AND RADIATION MONITORING SYSTEMS 60.00 % TOTALS FINAL GRADE All work done on this examination is my own. I have neither given nor received aid.

Candidate's Signature ENCLOSURE 1

A. RX THEORY, THERMO & FAC OP CHARS 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 ___

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 *****)

B. NORMAL/EMERG PROCEDURES & RAD CON 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 ___ (0.25 each)

B07 a b c d ___

B08 a b c d ___

B09 a b c d ___

B10 a b c d ___

B11 a b c d ___

B12 a b c d ___

B13 a b c d ___

B14 a b c d ___

B15 a b c d ___

B16 a b c d ___

B17 a b c d ___

B18 a b c d ___

B19 a b c d ___

B20 a b c d ___

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

C. PLANT AND RAD 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 ___ (0.25 each) e ___ f ___ g ___ h ___

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 ___ (0.25 each)

C13 a b c d ___

C14 a b c d ___

C15 a b c d ___

C16 a b c d ___

C17 a b c d ___

C18 a b c d ___

C19 a b c d ___

(***** 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 et 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 lbm 1 Horsepower = 2.54 x 103 BTU/hr 1 Mw = 3.41 x 106 BTU/hr 1 BTU = 778 ft-lbf °F = 9/5 °C + 32 1 gal (H2O) 8 lbm °C = 5/9 (°F - 32) cP = 1.0 BTU/hr/lbm/°F cp = 1 cal/sec/gm/°C

WASHINGTON STATE UNIVERSITY TRIGA REACTOR Operator Licensing Examination Week of December 3, 2012 ENCLOSURE 2

Section A - Reactor Theory, Thermohydraulics & Fac. Operating Characteristics Page 1 QUESTION A.1 [1.0 points]

Reactor is at a power level of 5 watts. The operator immediately inserts an experiment worth of

$0.75 into the core. This insertion will cause:

Given:

T: reactor period, *: Prompt neutron lifetime; : reactivity insertion; : beta fraction

a. A delayed reactor period to be equal to NEGATIVE (-) 80 seconds

b. A number of prompt neutrons equals to a number of delayed neutrons

c. The immediate reactor period to be a function of the prompt neutron lifetime (T=*/)

d. A sudden change of power that equals to the initial power multiplied by (1- )/ ( -)

QUESTION A.2 [1.0 point]

Xenon-135 (Xe135) is produced in the reactor by two methods. One is directly from fission; the other is indirectly from the decay of :

a. Xe136

b. Sm136

c. Cs135

d. I135 QUESTION A.3 [1.0 point]

A reactor with Keff = 0.8 contributes 1000 neutrons in the first generation. Changing from the first generation to the THIRD generation, how many TOTAL neutrons are there after the third generation?

a. 1800

b. 2440

c. 3240

d. 6400

Section A - Reactor Theory, Thermohydraulics & Fac. Operating Characteristics Page 2 QUESTION A.4 [1.0 point]

Which ONE of the following will be the resulting stable reactor period when a $0.35 reactivity insertion is made into an exactly critical reactor core? Neglect any effects from prompt. Given

=0.0070 and =0.1

a. 19 seconds

b. 22 seconds

c. 27 seconds

d. 31 seconds QUESTION A.5 [1.0 point]

A nuclear reactor startup is being performed by adding EQUAL amounts of positive reactivity and waiting for neutron population to stabilize. As the reactor approaches criticality, the Neutron Multiplication, Keff, will __________ after each reactivity addition; and the TIME required for the neutron population to STABILIZE will ___________ after each reactivity addition.

a. decrease; decrease

b. increase; increase

c. increase; decrease

d. remains the same; increase

Section A - Reactor Theory, Thermohydraulics & Fac. Operating Characteristics Page 3 QUESTION A.6 [1.0 point]

Given the following Core Reactivity Data during startup:

Control Rod Total Rod Worth Rod Worth removed

($) at 5 watts critical ($)

Blade #1 3.00 2.00 Blade #2 1.50 0.50 Blade #3 2.50 1.00 TRANS Rod 4.00 3.20 Assume the all blades are scrammable, the Shutdown Margin defined by the WSU TECHNICAL SPECIFICATIONS for this core is:

a. $2.7

b. $3.7

c. $4.3

d. $6.7

Section A - Reactor Theory, Thermohydraulics & Fac. Operating Characteristics Page 4 QUESTION A.7 [1.0 point]

Attached is the applicable portion from the chart of the nuclides, what will Mn-57 decay into?

a. Fe-57

b. Mn-58

c. Cr-57

d. V-53

Section A - Reactor Theory, Thermohydraulics & Fac. Operating Characteristics Page 5 QUESTION A.8 [1.0 point, 0.25 each]

Fill out the blank with INCREASE or DECREASE due to effects of moderator temperature increase.

a. Slowing down length _____________.

b. Thermal non leakage _____________.

c. Fast non leakage _____________.

d. Rod worth _____________.

QUESTION A.9 [1.0 point]

You are the reactor operator performing two pulsing operations. The first pulse has a reactivity worth of $1.20 which results in a peak power of 200 MW. If the second pulse has a peak power of 5000 MW, the corresponding reactivity worth is:

Given:

=0.0070

a. $1.50

b. $1.75

c. $2.00

d. $2.50 QUESTION A.10 [1.0 point]

Which ONE of the following physical characteristics of the TRIGA fuel is the MAIN contributor for the prompt negative temperature coefficient?

a. As the fuel heats up, a rapid increase in moderator temperature occurs through conduction and convection heat transfer mechanisms which adds negative reactivity

b. As the fuel heats up, the oscillating hydrogen in the Zr-H lattice imparts energy to a thermal neutron, thereby increasing its mean free path and probability of escape

c. As the fuel heats up, the resonance absorption peaks broaden and increases the likelihood of absorption in U-238 and/or Pu-240

d. As the fuel heats up, fission product poisons (e.g., Xe) increase in concentration within the fuel matrix and add negative reactivity via neutron absorption

Section A - Reactor Theory, Thermohydraulics & Fac. Operating Characteristics Page 6 QUESTION A.11 [1.0 point]

Which of the following is the definition for reactivity ()?

a. The measure of a reactors departure from criticality

b. The time required for power to change by a factor of e

c. The fraction of a number of delayed neutrons and a number of prompt neutrons

d. The faction of a number of neutrons of current generation and a number of neutrons of the previous generation QUESTION A.12 [1.0 point]

Which ONE of the following isotopes has the HIGHEST thermal neutron cross section?

a. Cd-112

b. Sm-149

c. Xe-135

d. U-238 QUESTION A.13 [1.0 point]

A reactor is critical. Reactor operator accidentally inserts an experiment in the core and Keff changes to 1.010. What is the period of the reactor? A prompt neutron lifetime (*) is 1 x 10 -4 seconds.

a. 0.001 sec

b. 0.01 sec

c. 0.10 sec

d. 1.0 sec

Section A - Reactor Theory, Thermohydraulics & Fac. Operating Characteristics Page 7 QUESTION A.14 [1.0 point]

In a subcritical reactor with Keff of 0.931, a reactivity worth of 0.017 k/k is inserted into the reactor core. Which ONE of the following is the NEW Keff ?

a. 0.925

b. 0.933

c. 0.946

d. 1.001 QUESTION A.15 [1.0 point]

Use Figure 3.3 attached. Calculate the effective delayed neutron fraction (-effective). At birth energies, there are 65 delayed neutrons and 9935 prompt neutrons. In the process of slowing down, there are only 56 delayed neutrons and 7352 prompt neutrons at the thermal range. The resultant -effective of Figure 3.3 is:

a. 0.00654

b. 0.00756

c. 0.00762

d. 0.00348

Section A - Reactor Theory, Thermohydraulics & Fac. Operating Characteristics Page 8 QUESTION A.16 [1.0 point]

A reactor is operating at 100 KW. The reactor operator withdraws the control rod allowing power to increase. The operator then inserts the same rod to its original position, decreasing power. In comparison to the rod withdrawal, the rod insertion will result in:

a. a slower period due to long lived delayed neutron precursors

b. a faster period due to long lived delayed neutron precursors

c. the same period due to equal amounts of reactivity being added

d. the same period due to equal reactivity rates from the rod QUESTION A.17 [1.0 point]

Reactor power is increasing by a factor of 10 every minute. The reactor period is:

a. 65 seconds

b. 37 seconds

c. 26 seconds

d. 13 seconds QUESTION A.18 [1.0 point]

Which ONE of the following conditions will INCREASE the core excess of a reactor?

a. Higher moderator temperature (assume negative temperature coefficient)

b. Insertion of a negative reactivity worth experiment

c. Burnout of a burnable poison

d. Fuel depletion

Section A - Reactor Theory, Thermohydraulics & Fac. Operating Characteristics Page 9 QUESTION A.19 [1.0 point]

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

a. 5%, from 95% to 100%

b. 10%, from 80% to 90%

c. 15%, from 15% to 30%

d. 20%, from 60% to 80%

QUESTION A.20 [1.0 point]

Which ONE of the following statements correctly describes thermal neutrons?

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

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

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

d. A neutron at resonant epithermal energy levels that causes fissions to occur in U-238.

- - - - End of Section A ********************************

Section B - Normal/Emergency Procedures and Radiological Controls Page 10 QUESTION B.1 [1.0 point]

Which ONE of the following is the MAIN reason why the limitation on the total radioactive inventory of iodine isotopes is less than 1.5 Ci in the fueled experiment? If the total radioactive inventory of iodine isotopes is greater than 1.5 Ci :

a. it would exceed a boiling point of 60 °C

b. the reactivity worth would exceed a secured limit of $2.0

c. the reactivity worth would exceed an unsecured limit of $1.0

d. it would exceed in an air effluent release limit specified in 10 CFR 20 QUESTION B.2 [1.0 point]

You use a survey instrument with a window probe to measure the beta-gamma dose rate from an irradiated experiment. The dose rate is 200 mrem/hour with the window opened and 140 mrem/hour with the window closed. The gamma dose rate is:

a. 60 mrem/hour

b. 140 mrem/hour

c. 200 mrem/hour

d. 340 mrem/hour QUESTION B.3 [1.0 point]

Per WSU Technical Specifications, what is the MINIMUM level of management who shall be present at the facility during all control rod relocations within the reactor core?

a. Reactor Operator

b. Senior Reactor Operator

c. Reactor Facility Director

d. The Reactor Operations Committee

Section B - Normal/Emergency Procedures and Radiological Controls Page 11 QUESTION B.4 [1.0 point]

Provide the correct class of emergency if a fire or explosion in a reactor-related area that cannot be immediately extinguished and which has the potential of adversely affecting the reactor.

a. Safety Event

b. Unusual Event

c. Alert

d. Site Area Emergency QUESTION B.5 [1.0 point]

Before entering to the experimental facility, you see a sign at the door CAUTION, RADIATION AREA. You would expect that radiation level in the facility could result in an individual receiving a dose equivalent of:

a. 2 mRem/hr at 30 cm from the source

b. 5 mRem/hr at 30 cm from the source

c. 100 mRem/hr at 30 cm from the source

d. 500 mRem/hr at 30 m from the source QUESTION B.6 [1.0 point, 0.25 each]

Per WSU Technical Specifications, match each event listed in column A with its associated time required for a written report to the U.S. NRC listed in column B. (Items in column B is used only once)

Column A Column B

a. A violation of a safety limit 1. 10 days

b. Total radioactivity liquid waste discharged 2. 30 days

c. Indicate a substantial variation from prior analysis 3. 60 days after an amendment of power upgrade

d. Permanent changes in Level 1of the facility 4. Annually organization

Section B - Normal/Emergency Procedures and Radiological Controls Page 12 QUESTION B.07 [1.0 point]

Per WSU Technical Specifications, the MINIMUM exhaust flow rate of the ventilation system in the normal mode, from the reactor pool room, shall be _______.

a. 3000 cubic foot per minute (cfm)

b. 4000 cubic foot per minute (cfm)

c. 3000 cubic meter per minute (cmm)

d. 4000 cubic meter per minute (cmm)

QUESTION B.8 [1.0 point]

A Senior Reactor Operator who is "on call" shall be capable of getting to the reactor facility in less than _______ and shall remain within a _______ radius of the facility.

a. 15 minutes, 30 mile

b. 30 minutes, 15 mile

c. 15 minutes, 25 mile

d. 30 minutes, 30 mile QUESTION B.9 [1.0 point]

Operability of the BNC facility access door shall be checked and documented before operation of the experiment commences each day that the BNC facility is used to carry out a BNC experiment. This is an example of:

a. a Safety Limit (SL)

b. a Surveillance Requirement (SR)

c. a Limiting Safety System Setting (LSSS)

d. a Limiting Conditions for Operation (LCO)

Section B - Normal/Emergency Procedures and Radiological Controls Page 13 QUESTION B.10 [1.0 point]

A radioactive source reads 50 Rem/hr on contact. Five hours later, the same source reads 5.0 Rem/hr. How long is the time for the source to decay from a reading of 50 Rem/hr to 50 mRem/hr?

a. 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months

b. 15 hours1.736111e-4 days 0.00417 hours 2.480159e-5 weeks 5.7075e-6 months

c. 20 hours2.314815e-4 days 0.00556 hours 3.306878e-5 weeks 7.61e-6 months

d. 25 hours2.893519e-4 days 0.00694 hours 4.133598e-5 weeks 9.5125e-6 months QUESTION B.11 [1.0 point]

Which ONE of the following conditions requires the NRC APPROVAL for changes?

a. Revise the startup checklist b Revise the requalification operator licensing examination c Major changes in the Special Nuclear Material Accountability Plan d Reduce the minimum number of the Reactor Safeguards Committee members from five to three QUESTION B.12 [1.0 point]

The radiation from an unshielded source is 1 rem/hr. When a lead sheet of 60-mm thickness is inserted; the radiation level reduces to 125 mrem/hr. What is the half-value-layer (HVL) of lead?

(HVL: thickness of lead required so that the original intensity will be reduced by half)?

a. 10 mm

b. 20 mm

c. 30 mm

d. 40 mm

Section B - Normal/Emergency Procedures and Radiological Controls Page 14 QUESTION B.13 [1.0 point, 0.25 each]

A small radioactive source is to be stored in the reactor building. The source is estimated to contain 4 curies and emit 100% of 1170-Kev gamma. Assuming no shielding used, how far is a distant that reads 5 mrem/hr?

a. 28 feet

b. 32 feet

c. 75 feet

d. 87 feet QUESTION B.14 [1.0 point]

Per WSU Technical Specifications of the Pulse Mode Operation, the maximum safe allowable reactivity insertion shall be calculated _________ for an existing core and prior to pulsing a new or modified core arrangement.

a. Semiannually

b. Annually

c. Biennially

c. Triennially QUESTION B.15 [1.0 point]

The operator licensing candidate requires submitting the NRC Form 396, Certification of Medical Examination by Facility Licensee, to the NRC Chief Examiner before start date of the examination. This requirement can be found in:

Section B - Normal/Emergency Procedures and Radiological Controls Page 15 QUESTION B.16 [1.0 point]

During an emergency with expected airborne radio nuclides in the pool room, which ONE of the following correctly describes the procedure to identify airborne radio nuclides? (Identify exact nuclides presented in the pool room)

a. The reactor bridge radiation monitor will identify the exact nuclides in the pool room

b. You enter the pool room and use portable meter for identification of the nuclides

c. Use a high volume air sampler to collect particulates on a filter paper, and then count it on a multichannel analyzer

d. Read a peak energy reading on exhaust gas monitor, and then compare it with the maximum allowable concentration as specified in Appendix B, Table II of 10 CFR 20 for identification QUESTION B.17 [1.0 point]

Per WSU Technical Specifications, which ONE of the following would most likely be considered a Special Report (the Facility shall report to the NRC no later than the following working day)?

a. You receive a fire alarm during reactor operation

b. You did not pay attention while raising the control rods to power, which causes reactor scram

c. You observe an abnormal loss of core coolant at a rate that exceeds the normal makeup capacity.

d. You load an unknown sample to the core, which causes an unexplained change in a $1.20 worth of reactivity.

QUESTION B.18 [1.0 point]

The WSU TRIGA reactor has been shutdown due to a fuel element leak. Which ONE of the following radioactive GASES is possibly released from the leaking fuel element?

a. Ar-41

b. I-131

c. Cs-137

d. N-16

Section B - Normal/Emergency Procedures and Radiological Controls Page 16 QUESTION B.19 [1.0 point, 0.25 each]

Per WSU Technical Specifications, all fuel elements shall be stored in a geometrical array where the k-effective is _______ for all conditions of moderation.

a. < 0.5

b. < 0.6

c. < 0.8

d. < 0.9 QUESTION B.20 [1.0 point]

Which ONE of the following is the 10CFR20 definition for Annual Limit on Intake (ALI)?

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

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

c. 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 millirem for noble gases

d. 10CFR20 derived limit, based on a Committed Effective Dose Equivalent of 5 Rems 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

- - - - End of Section B ********************************

Section C: Plant and Rad Monitoring Systems Page 17 QUESTION C.1 [1.0 point]

Which ONE of the following correctly describes the characteristic of the STARDARD fuel rod used at the WSU reactor?

a. The maximum uranium content is 30% by weight uranium, enriched to less than 20% U-235; and the erbium content is homogeneously distributed with a nominal 0.90% by weight

b. The maximum uranium content is 9% by weight uranium, enriched to less than 20% U-235, and NO erbium content.

c. The maximum uranium content is 20% by weight uranium, enriched to less than 30% U-235; and the erbium content is homogeneously distributed with a nominal 0.90% by weight

d. The maximum uranium content is 30% by weight uranium, enriched to less than 20% U-235; and the erbium content is homogeneously distributed with a nominal 0.50% by weight QUESTION C.2 [1.0 point]

Which ONE of the following correctly describes the Pool Level Alarm? When the pool level falls

______ inches below the normal operating level, it will initiate a signal alarm at__________.

a. 4, a monitored remote location ONLY

b. 8, the reactor control console ONLY

c. 4, the reactor control console and at a monitored remote location

d. 8, the reactor control console and at a monitored remote location QUESTION C.3 [1.0 point]

Which ONE of the statements below describes the operation of the three-way solenoid valve of the Transient rod air system?

a. When the solenoid valve is energized, the vent (exhaust) port is closed, the supply port is opened and the actual port (to the cylinder) is opened. Air from the accumulator is continuously supplied to the pneumatic cylinder of the Transient rod.

b. When the solenoid valve energized, the supply port is opened and the actual port is closed.

Air from the accumulator is vented through the vent port.

c. When the solenoid valve is de-energized, the vent (exhaust) port is closed, the supply port is opened and the actual port (to the cylinder) is opened. Air from the accumulator is continuously supplied to the pneumatic cylinder of the Transient rod.

d. When the solenoid valve de-energized; the vent port is closed. Air flows from pneumatic cylinder back to the accumulator.

Section C: Plant and Rad Monitoring Systems Page 18 Question C.4 [2.0 points, 0.25 each]

Match the inputs listed in column A with their responses listed in column B. (Items in column B may be used more than once or not at all). Assume the reactor is in operation.

Column A Column B

a. Log Power = 125 % full power 1. Indicate only

b. H.V. failure in Safety Channel #2 2. Interlocks

c. Pool water conductivity = 1 micomho/cm 3. Reactor automatically scrams

d. Withdrawal of blade #1 while in the Pulse mode

e. Seismic Switch relay actuates

f. Low pulse air pressure

g. Pool water temperature = 40 °C

h. Preset timer = 10 sec QUESTION C.5 [1.0 point]

After the performance of Thermal Power Calibration, the Linear Power Channel indicates only 90 % of full power calculated on the power calibration. To achieve 100% power level, the reactor operator needs to:

a. raise the Fission Chamber position to increase channel indication

b. lower the Fission Chamber position to increase channel indication

c. increase the H.V. CIC of the NMP 1000 to increase channel indication

d. lower the Compensated Ion Chamber (CIC) position of the NMP 1000 to increase channel indication

Section C: Plant and Rad Monitoring Systems Page 19 QUESTION C.6 [1.0 point]

The fuel temperature as measured by the Instrumented Fuel Rod shall not be more than 10 ° C above the pool temperature during the fuel movement. The main reason of this requirement is:

a. to maintain the integrity of the fuel element cladding

b. to ensure a lateral bending and an elongation of a fuel element are correctly measured

c. the ensure the fuel temperature increase will not cause any damage to the fuel measurement tool

d. to ensure the reactivity measurement to be made at low power without having to correct for negative temperature coefficient contributions QUESTION C.7 [1.0 point]

The Pulse Channel consists of:

a. Fission Chamber, Pre-AMP, and Safety #1 Monitor

b. Fission Chamber, Pre-AMP, and Wide Range Linear Monitor

c. Compensated Ion Chamber detector and a NMP 1000 channel

d. Uncompensated Ion Chamber detector and a NPP 1000 channel QUESTION C.8 [1.0 point]

During the startup, you perform a pulsing operation and collect the reading on the peak power (NV, in MW) and the total energy (NVT, in MW-sec). The peak power information comes from the _______ and the total energy information comes from the _________.

a. NPP 1000 channel, NMP 1000 channel

b. NPP 1000 channel, NPP 1000 channel

c. NPP 1000 channel, Wide Range Log Channel

d. NMP 1000 channel; NMP 1000 channel

Section C: Plant and Rad Monitoring Systems Page 20 QUESTION C.9 [1.0 point]

Which ONE of the following is the correct source to be used for the calibration of the Ar-41 monitor?

a. P-10

b. C-14

c. Cl-36

d. Sr-90 QUESTION C.10 [1.0 point]

You perform a fuel element inspection. In measuring the transverse bend, you find the bend of one fuel element exceeds the original length by 0.126 inches. For this measurement, you will:

a. continue the fuel inspection because this bend is within TS limit

b. continue the fuel inspection because the WSU Tech Spec requires the elongation measurement only

c. stop the fuel inspection; immediately report the result to the supervisor because it is considered a damaged fuel element d stop the fuel inspection, immediately report the result to the U.S. NRC since it is a reportable occurrence QUESTION C.11 [1.0 point]

Per WSU Technical Specifications, which ONE of the following can cause a control rod interlock when the PULSE mode is selected?

a. Standard rod drive DOWN and control rod DOWN

b. Power level at 2 kW and Pneumatic cylinder UP

c. Preset timer sets at 10 sec and Pneumatic cylinder UP

d. Pneumatic cylinder DOWN and Transient rod DOWN

Section C: Plant and Rad Monitoring Systems Page 21 Question C.12 [2.0 points, 0.5 each]

Match each instrument (channel) listed in column A with a specific purpose in column B. Items in column B is to be used only once.

Column A Column B

a. Log Power Channel 1. Provide a high power scram

b. Safety Power Channel 2. Provide rod scram after pulse

c. Preset Timer 3. Provide a low count rate interlock

d. Startup Channel 4. Provide period scram QUESTION C.13 [1.0 point]

During a reactor operation, you discover the Continuous Air Monitor (CAM) pump failure. Other monitors are operating. Which ONE of the following is the best action?

a. Continue to operate because the pump failure does NOT affect the operations of the CAM

b. Continue to operate because the Area Radiation and Exhaust Gas Radiation Monitors are still working

c. Shutdown the reactor; immediately report the result to the supervisor because the CAM is inoperable due to a pump failure; and the CAM failure considers a Tech Spec violation d Shutdown the reactor, immediately report the result to the U.S. NRC because it is a reportable occurrence

Section C: Plant and Rad Monitoring Systems Page 22 QUESTION C.14 [1.0 point]

Which ONE of the following best describes on how the Uncompensated Ion Chamber (UIC) and Compensated Ion Chamber (CIC) operate?

a. The CIC has two chambers, both can sense gamma rays but only one is coated with boron-10 for (n,) reaction; whereas the UIC has only one chamber coated with boron-10 for (n,) reaction.

b. The CIC has two chambers, one is coated with U-235 for fission reaction and the other is coated with boron-10 for (n,) reaction; whereas the UIC has only one chamber coated with U-235 for fission reaction.

c. The CIC has only one chamber coated with boron-10 for (n,) reaction; whereas the UIC has two chambers, one is coated with U-235 for fission reaction and the other is coated with boron-10 for (n,) reaction.

d. The CIC has only one chamber coated with U-235 for fission reaction, whereas the UIC has two chambers, both can sense gamma rays but only one is coated with boron-10 for (n,) reaction.

QUESTION C.15 [1.0 point]

Which ONE of the following is the main function performed by the DISCRIMINATOR in the LOG COUNT RATE of the Wide Range Log Channel?

a. To convert the signal from a fission counter to LINEAR output over a range of 10 -8 to 150 percent of full power.

b. To convert the signal logarithmic output of the metering circuit to a t (delta time) output for period metering purposes.

c. To filter out small pulses due to gamma interactions, passing only pulses due to neutron events within the LOG COUNT RATE.

d. To generate a current signal equal and of opposite polarity as the signal due to gamma generated within the LOG COUNT RATE.

Section C: Plant and Rad Monitoring Systems Page 23 QUESTION C.16 [1.0 point]

During reactor operation, a leak develops in the SECONDARY to PRIMARY heat exchanger.

Which ONE of the following conditions correctly indicates a leak in the heat exchanger?

a. Pool water conductivity will increase and Pool water level will increase

b. Pool water conductivity will decrease and Pool water level will decrease

c. Pool water conductivity will increase and Pool water level will decrease

d. Pool water conductivity will decrease and Pool water level will increase QUESTION C.17 [1.0 point]

The NPP-1000 in the STEADY STATE Mode provides the indications of:

a. Percent Power ONLY

b. Percent Power and 1 KW Interlock

c. Energy (Mw-sec) and Low Count Rate

d. Peak Power and Energy (Mw-sec)

Section C: Plant and Rad Monitoring Systems Page 24 QUESTION C.18 [1.0 point]

Use the following diagram of an instrumented fuel element. Which ONE of the following is the correct match for the position locator (Column A) to the correct component (Column B)?

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

a. I-C, II-F, III-A, IV-C

b. I-D, II-A, III-E, IV-C

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

d. I-C, II-B, III-E, IV-G

Section C: Plant and Rad Monitoring Systems Page 25 QUESTION C.19 [1.0 point]

Which ONE of the following would indicate a clog in the demineralizer tank?

a. High radiation level at pool surface

b. High flow rate through demineralizer

c. High temperature in demineralizer

d. High pressure upstream of demineralizer

- - - - End of Section C *****************************

- - - - End of the Exam ***************************

Section A L Theory, Thermo & Facility Operating Characteristics Page 26 A.1 Answer d

Reference:

§§ 8.1 8.4, pp. 8-3 8-14.

A.3 Answer: b

Reference:

=$* =$0.35*0.007 =0.00245 k T = (-)/

T = (0.0070 - 0.00245)/0.1 x 0.00245 = 18.57 seconds A.5 Answer b

Reference:

NRC Standard Question A.6 Answer: a

Reference:

Tech Spec SDM = total rod worth removed at critical - most reactivity control rod worth= $6.7 -$4.0 = $2.7 A.7 Answer: a

Reference:

- decay (np + -) Fe57 (N-1, Z+1)

Chart of the Nuclides A.8 Answer: a, Increase b, Decrease c, Decrease d, Increase

Reference:

Section A L Theory, Thermo & Facility Operating Characteristics Page 27 A.9 Answer: c 2

( 2 - )2 ( 1 - )

=

Peak 2 Peak 1

=($)*; 1=$1.20*0.007= 0.0084 k/k (Peak1 /Peak2)*(0.0084-.007)2 = (1- ) 2 0.000049=(1- ) 2 ;0.007= 1- or 1=0.007+0.007= 0.014 k/k or $2.0 Or Peak2 ($1-$1) 2 = Peak1*( $2-$1 /)2

($1-$1.0) 2 = (5000/200)*( $1.20-$1.0)2

$1-$1.0 = $1.0, $1 = $2.0 A.10 Answer: b

Reference:

TRIGA Fuel Design A.11 Answer: a

Reference:

DOE Fundamentals Handbook Nuclear Physics and Reactor Theory Vol. 2 A.12 Answer: c

Reference:

A.13 Answer: b

Reference:

Using equations provided in the equation sheet:

= (1.01-1)/1.01

( K eff - 1)

= = 0.01 K eff For prompt,

= 0.0001/0.01 = 0.01 sec

=

A.14 Answer: c

Reference:

= (Keff1-Keff2)/(Keff1*Keff2). 0.017 = (x-0.931)/(x*0.931); 0.017*0.931*x =x-0.931 0.01583x=x-0.931; 0.98417x =0.931; x=0.931/0.98417; x=0.946 A.15 Answer: b

Reference:

Section A L Theory, Thermo & Facility Operating Characteristics Page 28 A.16 Answer: a

Reference:

P=Poet/ J = 60 sec/ln(10) = 26 sec A.18 Answer c

Reference:

Standard NRC question A.19 Answer: c

Reference:

Time is related to ratio of final power to initial power. 2:1 is the largest ratio.

A.20 Answer: b

Reference:

NRC Standard Question

Section B Normal, Emergency and Radiological Control Procedures Page 29 B.1 Answer: d

Reference:

Technical Specification, Section 3.6 (Basis)

B.2 Answer: b

Reference:

Basic Radiation Instrumentation B.3 Answer: b

Reference:

Technical Specifications, Section 6.2.3 B.4 Answer: c

Reference:

Emergency Plan, Section 4.0 B.5 Answer: b

Reference:

10 CFR 20.1003 and 10CFR 20.1902 B.6 Answer: a(1) b(4) c(3) d(2)

Reference:

TS 6.10 B.7 Answer: b

Reference:

TS 3.4 B.8 Answer: b

Reference:

TS 6.2.1 B.9 Answer: b

Reference:

TS 4.8 B.10 Answer: b

Reference:

DR = DR*e -t 5.0 rem/hr =50 rem/hr* e -(5hr)

Ln(5.0/50) = -*5 --> =0.4605; solve for t: Ln(.05/50)=-0.4605 (t) t=15 hours or Reduce from 50 Rem to 5 Rem: 5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months From 5 Rem to 0.5 Rem: 5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months From 0.5 Rem to 0.05 Rem: 5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months Total: 15 hours1.736111e-4 days 0.00417 hours 2.480159e-5 weeks 5.7075e-6 months

Section B Normal, Emergency and Radiological Control Procedures Page 30 B.11 Answer: d

Reference:

TS 6.2.1 and 10 CFR 50.59 B.12 Answer: b

Reference:

DR = DR*e -X Find : 125 = 1000* e -*60 ; = 0.03466 If insertion of an HVL (thickness of lead), the original intensity will be reduced by half.

Find X: 1 = 2* e -0.03466*X ; X= 20 mm Find HVL by shortcut:

1000mR- 500 mR is the 1st HVL 500 mR - 250 mR is the 2nd HVL 500mR-125 mR is the 3rd HVL So HVL=60mm/3 = 20 mm B.13 Answer: c

Reference:

6 Ci E (n )

DR =

R2 Dose rate at 1 ft = 6CEN = 6 x 4Ci x 1.17 Mev x 1 =28.08 Rem/hr Distant at 5 mrem/hr = R= sqrt(28080 mR/5 mR) = 75 ft B.14 Answer: b

Reference:

TS 4.1.2 B.15 Answer: c

Reference:

10 CFR 55.21 B.16 Answer: c

Reference:

EP 7.2.1 B.17 Answer key changed to either c or d, both answers will be accepted as correct.

Answer: d or c

Reference:

TS 6.6.2 and TS1.28 B.18 Answer: b

Reference:

Standard NRC question B.19 Answer: c

Reference:

TS 5.5 B.20

Section B Normal, Emergency and Radiological Control Procedures Page 31 Answer: d.

Reference:

10CFR20.1003 Definitions

Section C Facility and Radiation Monitoring Systems Page 32 C.1 Answer: b

Reference:

TS 5.2 and SAR 4.2.1 C.2 Answer: d

Reference:

TS 3.2.4 C.3 Answer: a

Reference:

SAR 4.2.2 and Figure 4-16 C.4 Answer key changed to f(1) and h(3) as correct answers Answer: a(3) b(3) c(1) d(2) e(3) f(2) f(1) g(1) h(1) h(3)

Reference:

TS table 3.2 and SAR 7.4 C.5 Answer: d

Reference:

SOP #13 C.6 Answer: d

Reference:

SOP #7, Sec B.9 C.7 Answer: d

Reference:

SAR Figure 7-6 C.8 Answer: b

Reference:

SOP #4, Section D C.9 Answer: a

Reference:

SOP # 17, Section B.4 C.10 Answer: c

Reference:

TS 3.1.6 C.11 Answer: b

Reference:

TS Table 3.3

Section C Facility and Radiation Monitoring Systems Page 33 C.12 Answer key changed to either a(4) or a(3) and d(3) or d(4), these answers will be accepted as correct.

Answer: a(4) or a(3) b(1) c(2) d(3) or d(4)

Reference : SAR 7.2 C.13 Answer: c

Reference:

TS 3.5.1 C.14 Answer: a

Reference:

Training Manual, Section 5.1 C.15 Answer: c.

Reference:

SAR Figure 7-4 C.16 Answer: a

Reference:

SAR Table 5.3-1 (secondary flow rate > primary flow rate, and secondary water conductivity > pool water conductivity)

C.17 Answer: a

Reference:

SAR Figure 7-6 C.18 Answer: c

Reference:

SAR, Figure 4-9 C.19 Answer: d

Reference:

Standard NRC question

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Latest revision as of 10:00, 6 February 2020

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