ML16205A011

Examination Report No. 50-027/OL-16-01, Washington State University

ML16205A011
Person / Time
Site:	Washington State University
Issue date:	07/25/2016
From:	Anthony Mendiola Research and Test Reactors Oversight Branch
To:	Wall D Washington State Univ
Anthony Mendiola
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ml16068a003	List: ML16205A011
References
50-027/16-01 50-027/OL-16
Download: ML16205A011 (34)

Text

July 25, 2016 Dr. Donald Wall, Director Nuclear Radiation Center 50 Roundtop Drive Washington State University Pullman, WA 99164-1300

SUBJECT:

EXAMINATION REPORT, NO. 50-027/OL-16-01, WASHINGTON STATE UNIVERSITY

Dear Dr. Wall:

During the week of June 13, 2016, the U.S. Nuclear Regulatory Commission (NRC) administered an operator licensing examination at your Washington State University reactor. The examination was conducted according to NUREG-1478, Operator Licensing Examiner Standards for Research and Test Reactors, Revision 2, published in June 2007. Examination questions and preliminary findings were discussed at the conclusion of the examination with Mr.

C. Corey Hines, Assistant Director.

In accordance with Section 2.390 of Title 10 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 component of NRCs 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 the examination, please contact Phillip T. Young at 301-415-4094 or via email at phillip.young@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.50-027

Enclosures:

1. Examination Report NO. 50-027/OL-16-01

2. Facility comments with resolution

3. Written examination with facility comments incorporated cc: C. Corey Hines, Assistant Director cc: w/o enclosures: See next page

Dr. Donald Wall, Director July 25, 2016 Nuclear Radiation Center 50 Roundtop Drive Washington State University Pullman, WA 99164-1300

SUBJECT:

EXAMINATION REPORT, NO. 50-027/OL-16-01, WASHINGTON STATE UNIVERSITY

Dear Dr. Wall:

During the week of June 13, 2016, the U.S. Nuclear Regulatory Commission (NRC) administered an operator licensing examination at your Washington State University reactor. The examination was conducted according to NUREG-1478, Operator Licensing Examiner Standards for Research and Test Reactors, Revision 2, published in June 2007. Examination questions and preliminary findings were discussed at the conclusion of the examination with Mr.

C. Corey Hines, Assistant Director.

In accordance with Section 2.390 of Title 10 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 component of NRCs 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 the examination, please contact Phillip T. Young at 301-415-4094 or via email at phillip.young@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.50-027

Enclosures:

1. Examination Report NO. 50-027/OL-16-01

2. Written Examination cc: C. Corey Hines, Assistant Director, Reactor Operations, Washington State University cc: w/o enclosures: See next page DISTRIBUTION w/ encls.:

PUBLIC AMendiola MMorlang AAdams XYin ADAMS Accession No. : ML16205A011 Package: ML16068A003 OFFICE NRR/DPR/PROB/CE NRR/DPR/PROB/OLA NRR/DPR/PROB/BC NAME PYoung/pty CRevelle AMendiola DATE 0722/2016 07/21/2016 07/25/2016 OFFICIAL AGENCY RECORD

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 Washington State University Radiation Safety Office P.O. Box 641302 Pullman, WA 99164-1302 Dr. Ken Nash Chair Washington State University Reactor Safeguards Committee Nuclear Radiation Center P.O. Box 641300 Pullman, WA 99164-1300 Test, Research and Training Reactor Newsletter P.O. Box 118300 University of Florida Gainesville, FL 32611-8300

EXAMINATION REPORT NO: 50-027/OL-16-01 FACILITY: Washington State University FACILITY DOCKET NO.: 50-027 FACILITY LICENSE NO.: R-76 SUBMITTED BY: /RA/ 7/20/16 Phillip T. Young, Chief Examine Date

SUMMARY

During the week of June 13, 2016, the NRC administered operator licensing examinations to three Reactor Operator candidates. All candidates passed the examinations and will be issued a license to operate the Washington State University reactor.

REPORT DETAILS

1. Examiner: Phillip T. Young, Chief Examiner

2. Results:

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

3. Exit Meeting:

C. Corey Hines, Assistant Director, Reactor Operations, Washington State University Phillip T. Young, NRC, Examiner The NRC Examiner thanked the facility for their support in the administration of the examinations and noted how well the candidates were prepared. Mr. Young thanked the facility for their comments on the written examination.

ENCLOSURE 1

FACILITY COMMENTS WITH NRC RESOLUTION Question: A.010 With the reactor critical at 10 KW a rod is pulled to insert a positive reactivity of $0.18. Which one of the following will be the stable reactor period as a result of this reactivity insertion?

a. 10 seconds

b. 45 seconds

c. 55 seconds

d. 65 seconds Answer: A.10 b.

Reference:

Reactivity added = $0.18 x .007 = 0.00126

= (-)/eff = .007 - .00126 = 45.6 seconds

(.1) (.00126)

Facility comments: The answer uses the wrong value of Beff.

Recommendation: Consider changing the answer key and question bank.

Justification: Conversion SAR 2002, page 39, Beff = 0.0075 (not 0.007 as used in the calculation.)

NRC Resolution: The facility comment is accepted and the question will be modified as shown in the attached exam.

Question: A.012 The term "Prompt Critical" refers to:

a. the instantaneous jump in power due to a rod withdrawal

b. a reactor which is supercritical using only prompt neutrons

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

d. a reactivity insertion which is less than Beta-effective Answer: A.12. b.

Reference:

Standard NRC Question Facility comments: The answer key shows b, the correct answer is NO CORRECT ANSWER.

Recommendation: Consider changing the answer key and question bank.

Reference:

Reed Manual Rev. 9/2002 Section 9.8: When a reactor is critical on prompt neutrons alone it is prompt critical.

NRC Resolution: The staff has reviewed the question and the comment and believes the question is acceptable as written. See Burns 4.2 example 4.2(a) page 4-4 and section 1.2.3 page 1 - 6 ENCLOSURE 2

Question: B.011 WSUNRC keeps ___ emergency kits available.

a. Three

b. Two

c. One

d. Zero Answer: B.11 d.

Reference:

Emergency Plan Facility comments: The answer key show d. as correct and is should be answer b.

Recommendation: The answer key should be changed. There are two emergency kits as stated in the Emergency Plan Rev. 5/21/2015, reference provided below.

Reference:

WSUNRC Emergency Plan Rev. 5/21/2015, page 33, section 8.2.

NRC Resolution: The facility comment is accepted the answer key will show b. as the correct answer.

U. S. NUCLEAR REGULATORY COMMISSION NON-POWER INITIAL REACTOR LICENSE EXAMINATION FACILITY: Washington State University REACTOR TYPE: Pool Type, Modified TRIGA DATE ADMINISTERED: 6/14/2016 CANDIDATE:

INSTRUCTIONS TO CANDIDATE:

Answers are to be written on the answer sheet provided. Attach the answer sheets to the examination. Points for each question are indicated in brackets for each question. A 70%

in each section is required to pass the examination. Examinations will be picked up three (3) hours after the examination starts.

% of Category % of Candidate Category Value Total s 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 60.00 100.0 TOTALS All work done on this examination is my own. I have neither given nor received aid.

Candidate's Signature ENCLOSURE 3

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.

13. When you have completed and turned in you examination, leave the examination area.

If you are observed in this area while the examination is still in progress, your license may be denied or revoked.

EQUATION SHEET Q&= m&c p T = m&H = UA T eff = 0.1 seconds -1 S S CR1 (1 - K eff 1 ) = CR 2 (1 - K eff 2 )

SCR = 1 - K SUR = 26.06 eff M = - 10 - K eff CR1 (-M= 1

= 2 1 eff 1 ) = CR 2 (- CR)

- 1 - K eff 1 1 - K eff CR 2 t

P = P0 10 SUR(t)

P = P0 e (1 - )

• P= P0 (1 - K eff ) - -

SDM = = = +

K eff

( K effeff- 1)

K eff 2 - K eff 1 0.693 =

K eff k eff 1 x K eff 2 T

6CiE(n)

DR = DR0 e- t DR - DR = Rem, 2 DR 1 d 1 = DR 2 d 2 2

2 Ci - R curies, E - Mev, R - feet 2

( 2 - )2 ( 1 - )

=

Peak 2 Peak 1 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 ºF = 9/5 C + 32 1 gal (H2O) . 8 lbm ºC = 5/9 (F - 32) cP = 1.0 BTU/hr/lbm/ºF cp = 1 cal/sec/gm/ºC

Section A - Reactor Theory, Thermodynamics and Facility Operating Characteristics Question A.001 [1.0 point] {1.0]

Which factor of the Six Factor formula is most easily varied by the reactor operator?

a. Thermal Utilization Factor (f)

b. Reproduction Factor ()

c. Fast Fission Factor ()

d. Fast Non-Leakage Factor ( f)

Answer: A.01 a.

Reference:

NEEP 234, p. 89.

Question A.002 [1.0 point] {2.0]

Given the data in the table to the right, which ONE of the following is the closest to the half-life of the material?

TIME ACTIVITY 0 minutes 2400 cps 10 minutes 1757 cps 20 minutes 1286 cps 30 minutes 941 cps 60 minutes 369 cps

a. 11 minutes

b. 22 minutes

c. 44 minutes

d. 51 minutes Answer: A.02 b.

Reference:

Reactor Training Manual - Reactivity

Section A - Reactor Theory, Thermodynamics and Facility Operating Characteristics Question A.003 [1.0 point] {3.0]

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

a. 35Br 87 33As83

b. 35Br 87 35Br86

c. 35Br 87 34Se86

d. 35Br 87 36Kr87 Answer: A.03 b.

Reference:

NEEP 234, p.

Question A.004 [1.0 point] {4.0]

A reactor operator understands that:

a. The more neutrons multiply during startup the lower the shim blades are at critical.

b. Neutron multiplication during startup is just neutrons getting lost at a slower rate.

c. There is no fixed relationship between neutron level and criticality.

d. Without the Sb-Be source the reactor would not go critical.

Answer: A.04 c

Reference:

Glasstone, 1958, Chapter 14 Question A.005 [1.0 point] {5.0]

The count rate is 50 cps. An experimenter inserts an experiment into the core, and the count rate decreases to 25 cps. Given the initial Keff of the reactor was 0.8, what is the worth of the experiment?

a. = - 0.42

b. = + 0.42

c. = - 0.21

d. = + 0.21 Answer: A.05 a.

Reference:

CR1 / CR2 = (1 - Keff2) / (1 - Keff1) 50 / 25 = (1 - Keff2) / (1 - 0.8)

Therefore Keff2 = 0.6 = Keff2 - Keff1 / Keff2

• Keff1 = (0.6 - 0.8)/(0.6

• 0.8) = - 0.41667

Section A - Reactor Theory, Thermodynamics and Facility Operating Characteristics Question A.006 [1.0 point] {6.0]

The following graph for U-235 depicts

a. neutron energy distribution in the moderator

b. axial flux distribution in the core

c. radial flux distribution in the core

d. fission product yield distribution Answer: A.06 d.

Reference:

DOE Manual Vol. 1, pg. 57 Question A.007 [1.0 point] {7.0]

Keff for the reactor is 0.98. If you place an experiment worth +$1.00 into the core, what will the new Keff be?

a. 0.982

b. 0.987

c. 1.013

d. 1.018 Answer: A.07 b.

Reference:

SDM = (1-keff)/keff = (1-0.98)/0.98 = 0.02/0.99 = 0.02041 or 0.02041/.0075 =

$2.72, or a reactivity worth () of -$2.72.

Adding +$1.00 reactivity will result in a SDM of $2.72 - $1.00 = $1.72, or .0129081 K/K Keff = 1/(1+SDM) = 1/(1 + 0.0129081) = 0.987

Section A - Reactor Theory, Thermodynamics and Facility Operating Characteristics Question A.008 [1.0 point] {8.0]

Which ONE of the following statements describes the difference between Differential (DRW) and Integral (IRW) rod worth curves?

a. DRW relates the worth of the rod per increment of movement to rod position. IRW relates the total reactivity added by the rod to the rod position.

b. DRW relates the time rate of reactivity change to rod position. IRW relates the total reactivity in the core to the time rate of reactivity change.

c. IRW relates the worth of the rod per increment of movement to rod position. DRW relates the total reactivity added by the rod to the rod position.

d. IRW is the slope of the DRW at a given rod position.

Answer: A.08 a.

Reference:

Standard NRC Question Question A.009 [1.0 point] {9.0]

Given: Primary coolant flow rate is 500 gallons/minute and secondary flow rate is 700 gallons/minute. The T across the primary side of the heat exchanger is 13°F and secondary inlet temperature to the heat exchanger is 73°F. Assuming both the primary and secondary coolants have the same Cp value, which ONE of the following is the secondary outlet temperature?

a. 82° F

b. 85° F

c. 89° F

d. 91° F Answer: A.09 a.

Reference:

Tsec= (Flowpri/Flowsec) x Tpri Tsec= (500/700) x 13° F = 9.28° F Secondary outlet = 73° F + 9.28° F = 82.3° F

Section A - Reactor Theory, Thermodynamics and Facility Operating Characteristics Question A.010 [1.0 point] {10.0] Changed per facility comment With the reactor critical at 10 KW a rod is pulled to insert a positive reactivity of $0.18. Which one of the following will be the stable reactor period as a result of this reactivity insertion?

a. 10 seconds 45 seconds

b. 50 seconds

c. 55 seconds

d. 65 seconds Answer: A.10 b.

Reference:

Reactivity added = $0.18 x .0075 = 0.00126

= (-)/eff = .0075 - .00126 = 49.5 seconds

(.1) (.00126)

Question A.011 [1.0 point] {11.0]

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

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

b. There are more delayed neutrons than prompt neutrons.

c. Delayed neutrons increase the average neutron lifetime.

d. Delayed neutrons readily fission in U-238.

Answer: A.11 c.

Reference:

DOE Manual, Section 3 Question A.012 [1.0 point] {12.0]

The term "Prompt Critical" refers to:

a. the instantaneous jump in power due to a rod withdrawal

b. a reactor which is supercritical using only prompt neutrons

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

d. a reactivity insertion which is less than Beta-effective Answer: A.12. b.

Reference:

Standard NRC Question

Section A - Reactor Theory, Thermodynamics and Facility Operating Characteristics Question A.013 [1.0 point] {13.0]

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

a. Reflectors decrease core leakage while moderators thermalize neutrons

b. Reflectors shield against neutrons while moderators decrease core leakage

c. Reflectors decrease thermal leakage while moderators decrease fast leakage

d. Reflectors thermalize neutrons while moderators decrease core leakage Answer: A.13 a.

Reference:

Introduction to Nuclear Reactor Operations, Reed Robert Brown, Section 5.4 Question A.014 [1.0 point] {14.0]

Complete the following sentence.

A dollar ($) is a unit of reactivity, where one dollar ($1) is equal to the .

a. Delayed neutron precursor decay constant ().

b. Effective delayed neutron precursor decay constant (eff).

c. Delayed neutron fraction ().

d. Effective delayed neutron fraction (eff).

Answer: A.14 d.

Reference:

Reactor Theory (Neutron Characteristics)

DOE-HDBK-1019/1-93 PROMPT AND DELAYED NEUTRONS Question A.015 [1.0 point] {15.0]

An initial count rate of 100 is doubled five times during a startup. Assuming an initial Keff of 0.950, which one of the following is the new Keff?

a. 0.957

b. 0.979

c. 0.985

d. 0.998 Answer: A.15 d.

Reference:

CR1 (1-Keff1) = CR2 (1 - Keff2) or M1 (1-Keff1) = M2 (1 - Keff2)

CR2/CR1 = 32 ÷CR1 (1-Keff1)/CR2 = 1 - Keff2) ÷ 100 (1-0.950)/3200 = 1 - Keff2 Keff2 = 1 - .0015625 = .998

Section A - Reactor Theory, Thermodynamics and Facility Operating Characteristics Question A.016 [1.0 point] {16.0]

The associated graph depicts a plot of reactor period as a function of time. What best describes the behavior of REACTOR POWER between points A and B:

a. Constant

b. Decreasing then increasing

c. Continually increasing

d. Continually decreasing Answer: A.16 d.

Reference:

DOE Manual Vol. 1, Section 2 From point A to B, reactor period is negative, power will continue to decrease.

Question A.017 [1.0 point] {17.0]

Isotopes are nuclides that have the same atomic number and are therefore the same element, but differ in number of .

a. protons

b. electrons

c. neutrons

d. positrons Answer: A.17 c.

Reference:

DOE Fundamentals Handbook DOE-HDBK-1019/1-93 Nuclear Physics and Reactor Theory Vol. 1

Section A - Reactor Theory, Thermodynamics and Facility Operating Characteristics Question A.018 [1.0 point] {18.0]

A nuclear reactor startup is in progress. Control rod withdrawal was stopped several minutes ago to assess criticality. Which one of the following is the correct set of indications which supports a declaration that the reactor has achieved criticality?

a. Period is stable at ; source range count rate is stable.

b. Period is stable at 60 sec; source range count rate is stable.

c. Period is stable at ; source range count rate is slowly increasing.

d. Period is stable at 60 sec; source range count rate is slowly increasing.

Answer: A.18 d.

Reference:

NRC Generic Fundamentals Examination Question BankPWR2010, Question ID #P1766, Question A.019 [1.0 point] {19.0]

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

a. Xe136

b. Sm136

c. Cs135

d. I135 Answer: A.19 d.

Reference:

Burn, R., Introduction to Nuclear Reactor Operations, © 1988,

§§ 8.1 8.4, pp. 8-3 8-14.

Section A - Reactor Theory, Thermodynamics and Facility Operating Characteristics Question A.020 [1.0 point] {20.0]

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 Answer: A.20 b.

Reference:

TRIGA Fuel Design END OF SECTION A

Section B. - Normal & Emerg Operating Procedures & Radiological Controls Question B.001 [1.0 point] {1.0}

The term, ALARA, means:

a. As Low As Reasonably Attainable

b. As Little As Reasonably Attainable

c. A Low Ambient Radiation Area

d. As Low As Reasonably Achievable Answer: B.01 d.

Reference:

10 CFR20 Question B.002 [1.0 point] {2.0}

Per the 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)

Answer: B.02 b.

Reference:

TS 3.4 Question B.003 [1.0 point, 0.25 each] {3.0}

Match each of the Technical Specification Limits in column A with its corresponding value in column B. (Each limit has only one answer, values in Column B can be used once, more than once or not at all.)

Column A Column B (limit shall not exceed)

a. A secured experiment 1. $0.50

b. A movable experiment 2. $1.00

c. The sum of the absolute values of 3. $2.00 all individual experiments

4. $5.00

d. Maximum excess reactivity

5. $6.56

6. $7.46

Section B. - Normal & Emerg Operating Procedures & Radiological Controls Answer: B.03 a. = 3; b. = 2; c. = 4; d. = 6

Reference:

TS 3.1 and 3.6 Question B.004 [1.0 point] {4.0}

The ventilation system shall automatically switch to dilute mode upon a high activity alarm from the ___________.

a. Reactor bridge radiation monitor

b. Beam room radiation monitor

c. Continuous air monitor

d. Exhaust gas monitor Answer: B.04 c.

Reference:

TS 3.4 (3), pg. 22 Question B.005 [1.0 point] {5.0}

Which of the following would be considered the most correct method for environmental monitoring at the WSU NRC which satisfies the requirements of 10 CFR 20?

a. Continuous air monitoring for N-16 in the Exhaust Gas Monitoring System.

b. Processing highly sensitive thermoluminescent dosimeters (TLDs) placed in unrestricted areas adjacent to the facility.

c. Surveillance monitoring of personnel operating around exposure beam ports.

d. Performing periodic pool water samples with a high purity germanium (HPGe) detector, Answer: B.05 b.

Reference:

SOP No. 17, Standard Procedure for Environmental Monitoring Question B.006 [1.0 point] {6.0}

Which ONE of the following modifications would be considered a 50.59 in which the WSU must file a request to NRC for change? The facility plans to:

a. Replace an identical NLW-1000

b. Measure a xenon poisoning characteristics with new method

c. Replace a fission chamber with an un-compensated ion chamber in the Wide Rang Log Channel

Section B. - Normal & Emerg Operating Procedures & Radiological Controls

d. Perform a reactor power calibration with the new resistance temperature detector (RTD) probe Answer: B.06 c.

Reference:

Administrative Procedure # 3 Approval and Review of Facility Modifications and Special Tests or Experiments (10 CFR 50.59 changes)

Question B.007 [1.0 point] {7.0}

In accordance with 10 CFR 20, the "Annual Limit on Intake (ALI)" refers to:

a. The concentration of a given radionuclide in air which, if breathed for a working year of 2000 hours0.0231 days <br />0.556 hours <br />0.00331 weeks <br />7.61e-4 months <br />, would result in a committed effective dose equivalent of 5 rems.

b. The dose equivalent to organs that will be received from an intake of radioactive material by an individual during the 50-year period following the intake.

c. The amount of radioactive material taken into the body by inhalation or ingestion in one year which would result in a committed effective dose equivalent of 5 rems.

d. Limits on the release of effluents to an unrestricted environment.

Answer: B.07 c.

Reference:

10CFR20.1003 Question B.008 [1.0 point] {8.0}

The staff has just completed maintenance on a potentially contaminated system. You need to perform a survey to determine if there is any loose contamination in the vicinity that needs removal. Which of the following types of detectors would you most likely use in this instance?

a. Rem Ball

b. Scintillation Detector

c. Geiger Mueller (GM) Detector

d. Ion Chamber Answer: B.08 c.

Reference:

DOE Fundamentals Handbook Nuclear Physics and Reactor Theory Vol. 2 Question B.009 [1.0 point] {9.0}

___________ are thresholds for establishing emergency classes and initiating appropriate emergency measures.

a. Emergency Action Levels

Section B. - Normal & Emerg Operating Procedures & Radiological Controls

b. Emergency Planning Zones

c. Emergency Procedures

d. Protection Action Guides Answer: B.09 a.

Reference:

Emergency Plan Definitions, 2.2 - Emergency Action Levels Question B.010 [1.0 point] {10.0}

The Emergency Director is responsible for all of the following EXCEPT:

a. Alerting the dispatcher of the condition.

b. Ensuring the reactor is placed in a safe shutdown condition.

c. Terminating or minimizing releases of radioactive materials.

d. Protecting the health and safety of facility personnel and visitors.

Answer: B.10 a.

Reference:

Emergency Plan Question B.011 [1.0 point] {11.0}

WSUNRC keeps ___ emergency kits available.

a. Three

b. Two

c. One

d. Zero Answer: B.11 d. b. per facility comment

Reference:

Emergency Plan Question B.012 [1.0 point] {12.0}

The duties and responsibilities of a Reactor Operator shall include all of the following EXCEPT:

a. operating the reactor console

b. keeping records of all important events

c. performing all required maintenance and repair work on the reactor

d. shutting down the reactor immediately if any abnormal condition develops Answer: B.12 c.

Reference:

Administrative Procedures

Section B. - Normal & Emerg Operating Procedures & Radiological Controls Question B.013 [1.0 point] {13.0}

Per SOP-2, the cooling system pumps and tower fan are ON if:

a. reactor console power key and switch are in the ON position.

b. fuel temperature begins to increase upon startup

c. before the pool water temperature reaches 45 °C.

d. operating above 1 kW.

Answer: B.13 d.

Reference:

SOP Startup, Operation, and Shutdown of the Reactor (B.7.e)

Question B.014 [1.0 point] {14.0}

The exposure rate measured from a radioactive experiment at 1 foot is 500 mrem/hr. What would be the exposure rate at 3 feet from the experiment?

a. 20.2 mrem/hr

b. 55.6 mrem/hr

c. 166.7 mrem/hr

d. 277.8 mrem/hr Answer: B.14 b.

Reference:

Radiation Protection Training (500 mrem/hr)(1 ft)2= (x)(3 ft)2= 55.6 mrem/hr Question B.015 [1.0 point] {15.0}

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 Answer: B.15 b.

Reference:

TS 6.2.1 Question B.016 [1.0 point] {16.0}

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:

Section B. - Normal & Emerg Operating Procedures & Radiological Controls

a. a Safety Limit (SL)

b. a Surveillance Requirement (SR)

c. a Limiting Safety System Setting (LSSS)

d. a Limiting Conditions for Operation (LCO)

Answer: B.16 b.

Reference:

TS 4.8 Question B.017 [1.0 point] {17.0}

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 <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br />

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

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

d. 25 hours2.893519e-4 days <br />0.00694 hours <br />4.133598e-5 weeks <br />9.5125e-6 months <br /> Answer: B.17 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 <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> From 5 Rem to 0.5 Rem: 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> From 0.5 Rem to 0.05 Rem: 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> Total: 15 hours1.736111e-4 days <br />0.00417 hours <br />2.480159e-5 weeks <br />5.7075e-6 months <br /> Question B.018 [1.0 point] {18.0}

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:

a. 10 CFR Part 26

b. 10 CFR Part 50.59

c. 10 CFR Part 55

d. 10 CFR Part 73 Answer: B.18 c.

Reference:

10 CFR 55.21

Section B. - Normal & Emerg Operating Procedures & Radiological Controls Question B.019 [1.0 point] {19.0}

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. Annually

b. Biennially

c. Triennially

d. Semiannually Answer: B.19 a.

Reference:

TS 4.1.2 Question B.020 [1.0 point] {20.0}

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 Answer: B.20 c.

Reference:

Emergency Plan, Section 4.0 END OF SECTION B

Question C.001 [1point, 0.166 each] {1.0}

During a Reactor Power Calibration in accordance with SOP-20, indicate whether each of the components a. through f. are ON and operating or OFF during the power run.

a. Primary cooling pump

b. Secondary cooling pump

c. Cooling tower

d. Diffuser pump

e. Purification system

f. Pool mixer Answer: C.01 a. = off; b. = off: c. = off; d. = on; e. = off; f. = on

Reference:

SOP Reactor Power Calibration (C.1)

Question C.002 [1point] {2.0}

The CAM filter shall be changed ___________.

a. as part of the reactor startup checkout

b. daily

c. weekly

d. monthly Answer: C.02 c.

Reference:

SOP-8, Maintenance of the Continuous Air Monitor (A)

Question C.003 [1point] {3.0}

Which ONE of the following is the correct source to be used for the Channel Test of the Area Radiation Monitors?

a. C-14

b. Cl-36

c. Sr-90

d. Ra-226 Answer: C.03 d.

Reference:

SOP-6, Maintenance of the Area Radiation Monitors (C)

Question C.004 [1point] {4.0}

Per SOP-10 Maintenance of the Reactor Pool Facilities, the reactor pool level alarm shall be tested monthly for operability. What is the total number of float switches test?

a. 1

b. 2

c. 3

d. 4 Answer: C.04 c.

Reference:

SOP-10, Maintenance of the Reactor Pool Facilities (C.a through .c)

Question C.005 [1point] {5.0}

Which of the following statements is correct, regarding a reactor pulse at the WSU NRC?

a. Typically, control blade #1, 2, or 4 is withdrawn to a desired power level of 2 kW.

b. The magnitude of the pulse is determined by the anvil height in the rod cylinder.

c. When the mode selector switch is positioned to the Pulse mode, only the standard control blades are inhibited from being withdrawn.

d. A transient rod scram occurs 20 seconds on a preset timer once the reactor operator initiates the fire button Answer: C.05 b.

Reference:

SAR 4.2.2 Control Rods - Transient Control Rod and Figure 4-15 SOP-2 Startup, Operation, and Shutdown of the Reactor Section D.

Pulsing Operations

Question C.006 [1point] {6.0}

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 Answer: C.06 b.

Reference:

Core 35-A diagram, WSU SAR. June 2002, Section 4 and 10 TS 5.2 Reactor Fuel Question C.007 [1point] {7.0}

The Beam Port Plug alarm signal will trigger:

a. a RED light on its panel ONLY

b. a YELLOW light on Console Alarm Board ONLY

c. a RED light on its panel and a YELLOW light on Console Alarm Board

d. a RED light on its panel, a YELLOW light on Console Alarm Board, and Annunciator sounding Answer: C.07 a.

Reference:

SOP-15 Action in the Event of an Alarm - Section B.3.a Question C.008 [1point] {8.0}

Which of the following is NOT a mode of operation for the pool room and air handling system at the WSU NRC?

a. Normal

b. Isolation

c. Evacuation

d. Dilute

Answer: C.08 c.

Reference:

WSU SAR. June 2002, Section 6.2.2 Containment Question C.009 [1point] {9.0}

Which ONE of the following systems obtains emergency power in the event of a power loss by the Auxiliary Reactor Emergency Supply (ARIES)?

a. Pool Level Alarm

b. Primary Coolant Pump

c. Control Rods

d. Pneumatic Transfer System Answer: C.09 a.

Reference:

SAR 7.4.6, pg. 7-17 Question C.010 [1point] {10.0}

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.

Answer: C.10 c.

Reference:

SAR Figure 7-4 Question C.011 [1point] {11.0}

Which of the following alarms/indications WILL directly require a reactor scram?

a. Red HIGH ALARM and light from the Continuous Air Monitor (CAM)

b. Low Pool Water Level

c. Alarm on the Exhaust Gas Monitor

d. < 2 cps on the wide range power instrumentation

Answer: C.11 b.

Reference:

WSU SAR, June 2002, Table 7.2-2 Question C.012 [1point] {12.0}

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)

Answer: C.12 a.

Reference:

SAR Figure 7-6 Question C.013 [1point] {13.0}

Reactor is at 100 kW. You receive an Exhaust Gas Monitor (EGM) alarm. Per SOP #18, you should:

a. Immediately secure reactor and notify the Health Physicist on duty

b. Continue with reactor operations and deactivate the EGM alarm

c. Immediately secure reactor and notify the Senior Reactor Operator on duty

d. Continue reactor operations after isolation of the ventilation and also notify the Senior Reactor Operator on duty Answer: C.13 d.

Reference:

SOP Action in the Event of an Alarm Rev Section C.e. Exhaust Gas Monitor Question C.014 [1point] {14.0}

A system of limit switches is used to indicate the position of the air cylinder and the transient rod. Which ONE is the switch actuated when the piston reaches its lower limit of travel?

a. The Drive Up switch

b. The Drive Down switch

c. The Rod Up switch

d. The Rod Down switch Answer: C.14 d

Reference:

SAR 4.2.2, pg. 4-29 Question C.015 [1point] {15.0}

In the event that fuel must be unloaded from the reactor pool, two storage racks in the reactor pool are provided. Which of the following statements correctly identifies an adequate safe storage condition (by TS) of the fuel at the WSU NRC?

a. Keff = 0.75

b. Keff = 1.0

c. pH of the storage water= 8.0

d. storage water temperature= 60 °C Answer: C.15 a.

Reference:

WSU TS, April 26, 2002, Sections 3.3 and 5.5, Question C.016 [1point] {16.0}

Using the following diagram of an instrumented fuel element match the correct position locator (Column A) to the correct component (Column B).

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

a. I.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

Answer: C.16 c. (I-D, II-E, III-A, IV-G)

Reference:

NRC Reference Material for a Standard TRIGA Instrumented Fuel Element

Question C.017 [1point] {17.0}

The source interlock system will prevent rod withdrawal unless source level is above a preset level. This source interlock signal comes from:

a. Log-N Power Channel

b. Linear Channel

c. Fuel Temperature Channel

d. Percent Power Channel (Safety Chanel #2)

Answer: C.17 a.

Reference:

SAR 7.3 Question C.018 [1point] {18.0}

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 Answer: C.18 d.

Reference:

Standard NRC question Question C.019 [1point] {19.0}

The MAIN purpose of small flow holes drilled at the bottom of the shroud is to:

a. reduce the effects of viscous damping on the blade fall time

b. increase of the blade speed during withdrawal

c. allow water to cool the blade during shutdown

d. prevent corrosion on the control blade Answer: C.19 a.

Reference:

SAR 4.2.2

Question C.020 [1point] {20.0}

A MAIN purpose of the interlock to prevent withdrawal of more than one control rod at a time is to prevent:

a. inadvertently large reactivity insertion

b. damage of control rod drive system

c. initiation of a pulse while on a positive period

d. initiation of a pulse during a reactor startup Answer: C.20 a.

Reference:

TS 3.2.3 Basis END OF SECTION C END OF WRITTEN EXAMINATION