ML23102A204

Examination Report No. 50-027/OL-23-01, Washington State University

ML23102A204
Person / Time
Site:	Washington State University
Issue date:	08/28/2023
From:	Travis Tate NRC/NRR/DANU/UNPO
To:	Hines C Washington State Univ
References
50-027/23-01 50-027/OL-23
Download: ML23102A204 (39)

Text

August 28, 2023 Corey Hines, Director Washington State University Nuclear Radiation Center 50 Roundtop Drive Pullman, WA 99164-1300

SUBJECT:

EXAMINATION REPORT NO. 50-027/OL-23-01, WASHINGTON STATE UNIVERSITY

Dear Corey Hines:

During the week of August 7, 2023, the U.S. Nuclear Regulatory Commission (NRC) administered an operator licensing examination at your Washington State University research reactor. The examinations were conducted according to NUREG-1478, "Operator Licensing Examiner Standards for Research and Test Reactors," Revision 2. Examination questions and preliminary findings were discussed with those members of your staff identified in the enclosed report at the conclusion of the examination.

In accordance with Title 10 of the Code of Federal Regulations, Section 2.390, a copy of this letter and the enclosures will be available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records component of NRC's Agencywide Documents Access and Management System (ADAMS). ADAMS is accessible from the NRC website 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 Dan Hoang at (301) 415-3052 or via email Dan.Hoang@nrc.gov.

Sincerely, Signed by Tate, Travis on 08/28/23 Travis L. Tate, Chief Non-Power Production and Utilization Facility Oversight Branch Division of Advanced Reactors and Non-Power Production and Utilization Facilities Office of Nuclear Reactor Regulation Docket No. 50-288

Enclosures:

As Stated cc: w/enclosures: GovDelivery Subscribers

ML23102A204 NRR-079 OFFICE NRR/DANU/UNPO/CE NRR/DANU/UNPO/OLA NRR/DANU/UNPO/BC NAME DHoang NJones TTate DATE 8/28/2023 8/28/2023 8/28/2023 U.S. NUCLEAR REGULATORY COMMISSION OPERATOR LICENSING INITIAL EXAMINATION REPORT REPORT NO.: 50-027/OL-23-01 FACILITY DOCKET NO.: 50-027 FACILITY LICENSE NO.: R-76 FACILITY: TRIGA EXAMINATION DATES: August 07 - August 11, 2023 SUBMITTED BY ____Danvhoang____________ _8/16/2023__

Dan V. Hoang, Chief Examiner Date

SUMMARY

During the weeks of August 7, 2023, the NRC administered operator licensing examinations to four Reactor Operators (RO) and three Senior Reactor Operators candidates. The candidates passed all applicable portions of the examinations.

REPORT DETAILS

1. Examiner: Dan V. Hoang, Chief Examiner, NRC

2. Results:

RO PASS/FAIL SRO PASS/FAIL TOTAL PASS/FAIL Written 4/0 2/0 6/0 Operating Tests 4/0 3/0 7/0 Overall 4/0 3/0 7/0

3. Exit Meeting:

Corey Hines, Reactor Director, WSU Hillary Bennett, Reactor Supervisor, WSU Facility comments were accepted prior to the administration of the written examination.

Upon completion of an operator licensing examination, the NRC examiner met with facility staff representatives to discuss the results. At the conclusion of the meeting, the NRC examiner thanked the facility for their support in the administration of the examination.

Enclosure 1

WASHINGTON STATE UNIVERSITY Operator Licensing Examination Week of August 07, 2023 Enclosure 2

U.S. NUCLEAR REGULATORY COMMISSION NON-POWER REACTOR LICENSE EXAMINATION FACILITY: Washington State University REACTOR TYPE: TRIGA.

DATE ADMINISTERED: 08/08/2023.

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

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 ___

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 ___

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 *****)

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

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

C01 a b c d ___

C02 a b c d ___

C03 a b c d ___

C04 a b c d ___

C05 a b c d ___

C06 a b c d ___

C07 a b c d ___

C08 a b c d ___

C09 a b c d ___

C10 a b c d ___

C11 a b c d ___

C12 a b c d ___

C13 a b c d ___

C14 a b c d ___

C15 a b c d ___

C16 a b c d ___

C17 a b c d ___

C18 a b c d ___

C19 a b c d ___

C20 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 Q m c P T m H UAT Pmax eff 0.1sec 1 2

t P P0 e S S SCR

• 110 4 sec 1 K eff CR1 1 CR2 2 eff SUR 26 .06 CR1 1 K eff1 CR2 1 K eff 2 1 M 1 CR 2

P P0 1 K eff CR1 P P0 10 SUR (t )

1 K eff1 1 K eff

• M SDM 1 K eff 2 K eff

= + 0.693 T1 K eff 2 K eff1 2

K eff1 K eff 2 K eff 1 DR DR0 e t 2 2 K eff DR1 d1 DR2 d 2 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]

What is the major source of energy released during fission?

a. Kinetic energy of prompt and delayed neutrons.

b. Kinetic energy of fission fragments.

c. Alpha and beta radiation.

d. Gamma radiation decay.

QUESTION A.02 [1.0 point]

Xenon-135 is formed from ______ decay of ______.

a. Alpha, Cesium-135.

b. Beta, Iodine-135.

c. Alpha, Tellurium-135.

d. Beta, Barium-135.

QUESTION A.03 [1.0 point]

The FAST FISSION FACTOR is defined as a ratio of:

a. the number of neutrons that reach thermal energy over the number of fast neutrons that start to slow down.

b. the number of fast neutrons produced from fission in a generation over the number of fast neutrons produced from fission in the previous generation.

c. the number of fast neutrons produced from U-238 over the number of thermal neutrons produced from U-235.

d. the number of fast neutrons produced from all fission over the number of fast neutrons produced from thermal fission.

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

How long will it take power to triple, given a reactor period of 32 seconds?

a. 62 seconds.

b. 54 seconds.

c. 41 seconds.

d. 35 seconds.

QUESTION A.05 [1.0 point]

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

to 100% power in 2 minutes?

a. 0.5 second.

b. 13 seconds.

c. 26 seconds.

d. 43 seconds.

QUESTION A.06 [1.0 point]

What is the effect of U-238 on the reactor neutron life cycle when a neutron energy is below 1 MeV?

a. The number of fissions due to U-238 decrease.

b. The number of fissions due to U-238 remains the same.

c. The number of fissions due to U-238 increase.

d. The number of fissions due to U-235 increase.

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

Which ONE of the following is the meaning of any point on a differential rod worth curve?

a. The amount of reactivity that one unit (e.g., one inch, one percent) of rod motion would insert at that position in the core.

b. The zero reactivity when the rod is on the bottom and the positive reactivity being added as the rod is withdrawn.

c. The cumulative area under the differential curve starting from the bottom of the core.

d. The negative reactivity added as the rod is inserted.

QUESTION A.08 [1.0 point]

Which of the following is an example of a FERTILE material?

a. Th-232

b. U-233

c. U-235

d. Pu-239 QUESTION A.09 [1.0 point]

Which term is described by the following?

The increase in neutron population by providing a positive additional reactivity while the reactor is subcritical.

a. Subcritical Multiplication.

b. Inverse Multiplication.

c. Neutron Production.

d. Source Strength.

Category A: Reactor Theory, Thermodynamics, and Facility Operating Characteristics QUESTION A.10 [1.00 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.11 [1.00 point]

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

a. Prompt.

b. Delayed.

c. Fast.

d. Thermal.

QUESTION A.12 [1.00 point]

Reactor period is defined as:

a. The time required for the reactor power to double.

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

c. The time required for the reactor power to be reduced to one-half the initial level.

d. The number of factors of ten that reactor power changes in one minute.

Category A: Reactor Theory, Thermodynamics, and Facility Operating Characteristics QUESTION A.13 [1.00 point]

Which ONE of the following has a long-term effect on Keff but is of no consequence during short term and transient operation?

a. Fuel burnup.

b. Increase in fuel temperature.

c. Increase in moderator temperature.

d. Xenon and Samarium fission products.

QUESTION A.14 [1.00 point]

A mechanism by which a nucleus can gain stability by converting a neutron to a proton or vice versa is called:

a. Alpha decay.

b. Beta decay.

c. Gamma decay.

d. Photoelectric effect.

QUESTION A.15 [1.00 point]

During Regulating Rod calibration, doubling time was recorded to be 68 seconds. What was reactor period?

a. 47 seconds.

b. 98 seconds.

c. 116 seconds.

d. 133 seconds.

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

Some neutrons do not come directly from fission, but from fission product decay. These neutrons are called:

a. Thermal neutrons.

b. Delayed neutrons.

c. Neutron Production.

d. Fission neutrons.

QUESTION A.17 [1.0 point]

Excess reactivity is the amount of reactivity ________.

a. associated with burnable poisons.

b. needed to achieve prompt criticality.

c. available below that which is required to make the reactor subcritical.

d. available above that which is required to keep the reactor critical.

QUESTION A.18 [1.00 point]

The count rate for a reactor is 200 cps. An operator inserts an experiment into the core, and the count rate decreases to 110 cps. Given the initial Keff of the reactor was 0.95, what is the worth of the experiment?

a. = - 0.02

b. = + 0.02

c. = - 0.05

d. = + 0.05

Category A: Reactor Theory, Thermodynamics, and Facility Operating Characteristics QUESTION A.19 [1.00 point]

Which ONE of the following is the main reason for the decrease in reactivity following an increase in fuel temperature?

a. A fuel matrix in the reactor core.

b. High fuel element reactivity worth.

c. Reactor fuel type.

d. A long delay time for transferring heat to the core cooling water.

QUESTION A.20 [1.00 point]

Given a source strength of 200 neutrons per second (N/sec) and a multiplication factor of 0.6, 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.

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

Category B: Normal/Emergency Operating Procedures and Radiological Controls QUESTION B.01 [1.00 point]

Which ONE of the following correctly describes the limitations of experiment? The experiment with shall NOT be placed inside the reactor experimental facilities.

a. total non-secured reactivity worth exceeding 0.06 %k/k

b. total secured reactivity worth exceeding 0.4 %k/k

c. explosive materials greater than 25 mg

d. fissionable materials QUESTION B.02 [1.00 point]

An annual test of the nuclear instrument was performed. Which ONE of the following is the latest the test that must be performed AGAIN without violation of the Technical Specifications?

a. Not to exceed 13 months.

b. Not to exceed 14 months.

c. Not to exceed 15 months.

d. Not to exceed 16 months.

QUESTION B.03 [1.00 point]

What is the MINIMUM level of management who shall be present at the facility during a recovery from an unplanned or unscheduled shutdown?

a. Reactor Operator.

b. Senior Reactor Operator.

c. Reactor Facility Director.

d. Reactor Operations Committee.

Category B: Normal/Emergency Operating Procedures and Radiological Controls QUESTION B.04 [1.00 point]

The Regulating Rod shall be visually inspected _________while the Transient Rod Drive shall be inspected ________.

a. Monthly, annually

b. Every six months, every year

c. Every year, semiannually

d. Every two years, every six months QUESTION B.05 [1.00 point]

A radioactive source reads 5 Rem/hr on contact. Five hours later, the same source reads 1.25 Rem/hr. How long is the time for the source to decay from a reading of 5 Rem/hr to 625 mRem/hr?

a. 6.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />.

b. 7.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />.

c. 8.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />.

d. 9.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />.

QUESTION B.06 [1.00 point]

The requalification program must be conducted for a continuous period not to exceed 24 months in duration, in accordance with _______.

a. 10 CFR 19

b. 10 CFR 20

c. 10 CFR 50

d. 10 CFR 55

Category B: Normal/Emergency Operating Procedures and Radiological Controls QUESTION B.07 [1.0 point]

Which ONE of the following conditions is a NOT violation of WSU Technical Specifications, Primary Coolant Conductivity?

a. Conductivity of the pool water is > 5 x 10-6 mhos/cm.

b. Conductivity of the pool water is < 5 x 10-6 mhos/cm.

c. Conductivity of the pool water is < 5 x 10-4 mhos/cm.

d. Conductivity of the pool water is > 5 x 10-4 mhos/cm.

QUESTION B.08 [1.0 point]

Which ONE of the following is the renewal requirement for an existing license?

a. Every year.

b. Biennially.

c. Every six months.

d. Every six years.

QUESTION B.09 [1.0 point]

A radioactive material is decayed 30% after one hour. Determine its half-life?

a. 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.

b. 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />.

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

d. 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />.

Category B: Normal/Emergency Operating Procedures and Radiological Controls QUESTION B.10 [1.0 point]

Per 10 CFR 20, what is the annual limit of radiation exposure for a visitor?

a. 2 mRem/hr.

b. 100 mRem/hr.

c. 100 mRem.

d. No limit defined, just need to meet an ALARA program.

QUESTION B.11 [1.00 point]

Which ONE of following types of radiation is the HIGHEST Quality Factor specified in 10 CFR 20?

a. Alpha.

b. Beta.

c. Gamma.

d. Neutron (unknown energy).

QUESTION B.12 [1.0 point]

A radioactive source reads 4 Rem/hr on contact. Five hours later, the same source reads 2.0 Rem/hr. How long is the time for the source to decay from a reading of 4 Rem/hr to 250 mRem/hr?

a. 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />.

b. 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br />.

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

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

Category B: Normal/Emergency Operating Procedures and Radiological Controls QUESTION B.13 [1.0 point]

What is the exposure rate at a distance of 4 meters, if the initial exposure rate for a point source is 400 mR/hr at a distance of 2 meters?

a. 75 mR/hr.

b. 100 mR/hr.

c. 125 mR/hr.

d. 45 mR/hr.

QUESTION B.14 [1.0 point]

The reactor building (or the nearest physical personnel barrier in cases where the reactor building is not a principal physical barrier), where the Facility Director has direct authority over all activities is:

a. Operations Boundary.

b. Reconvening boundary.

c. Site area boundary.

d. Material boundary.

QUESTION B.15 [1.00 point]

WSU Emergency Plan allows a one-time MAXIMUM exposure limit of to save a life or protect large populations.

a. 5 rem

b. 10 rem

c. 25 rem

d. 50 rem

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

The air flow rates in the ventilation system shall be measured_______

a. Quarterly.

b. Semi-annually.

c. Monthly.

d. Biennially.

QUESTION B.17 [1.0 point]

The Quality Factor is used to convert:

a. External dose to internal dose.

b. Dose in rems to dose equivalent in rads.

c. Dose in rads to dose equivalent in rems.

d. Derived air concentration (DAC) to Annual limit on Intake (ALI).

QUESTION B.18 [1.00 point]

Which ONE of the following radioactive GASES might be an indication of a fuel element leak?

a. N16

b. Ar41

c. I131

d. Cs137

Category B: Normal/Emergency Operating Procedures and Radiological Controls QUESTION B.19 [1.00 point]

Which ONE of the following hospitals has agreed to accept contaminated victims for medical treatments?

a. Pullman Regional Hospital.

b. Pullman Memorial Hospital.

c. Gritman Memorial Hospital.

d. Moscow Hospital.

QUESTION B.20 [1.00 point]

The principal barrier to be used for specification of the safety limit is the:

a. Reactor fuel cladding temperature.

b. Reactor thermal power.

c. Bulk pool temperature.

d. Coolant height.

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

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

Which ONE of the following statements concerning the WSU STANDARD fuel rods is TRUE?

a. The uranium content shall be 30% by weight enriched to less than 20% 235U.

b. The uranium content shall be 9% by weight enriched to less than 20% 235U.

c. The uranium content shall be 20% by weight enriched to less than 20% 235U.

d. The uranium content shall be 10% by weight enriched to less than 20% 235U.

QUESTION C.02 [1.0 point]

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 QUESTION C.03 [1.0 point]

Which ONE of the following components is used to reduce drive speed on the blade type control rods?

a. Worm Gear Assembly

b. Magnetic Coupler

c. Mechanical Drive Clutch.

d. Nut and Ball Bearing Screw System

Category C: Facility and Radiation Monitoring Systems QUESTION C.04 [1.0 point]

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

a. Control rod.

b. Pool level alarm.

c. Primary coolant pump.

d. Pneumatic transfer system.

QUESTION C.05 [1.0 point]

What is the response of the ventilation system upon a reactor SCRAM?

a. Automatic shutdown.

b. Continues to operate normally.

c. Switches to dilute mode.

d. Switches to isolation mode.

QUESTION C.06 [1.0 point]

Which ONE of the following is TRUE about the facility ventilation system?

a. In normal mode, all of the air is exhausted through a series of charcoal and HEPA filters before going out through the stack.

b. The ventilation system shall manually switch to dilute mode upon a high activity alarm from the Continuous Air Monitor.

c. The exhaust flow rate of the ventilation system in the dilute mode, from the reactor pool room, shall be 400 cfm.

d. The ventilation system shall be switched to the isolate mode upon initiation of a reactor scram.

Category C: Facility and Radiation Monitoring Systems QUESTION C.07 [1.0 point]

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 QUESTION C.08 [1.0 point]

Which ONE of the following materials is the regulating blade made of?

a. Aluminum.

b. Boron.

c. Cadmium.

d. Stainless Steel.

QUESTION C.09 [1.0 point]

The CAM filter shall be changed ___________.

a. as part of the reactor startup checkout

b. daily

c. weekly

d. monthly

Category C: Facility and Radiation Monitoring Systems 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]

Which of the following is NOT a mode of operation for the containment HVAC system at the WSU?

a. Normal.

b. Isolation.

c. Evacuation.

d. Dilute.

QUESTION C.12 [1.0 point]

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.

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

Which of the following alarms/indications in the REACTOR SAFETY CHANNELS 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.

QUESTION C.14 [1.0 point]

Reactor is at 100 kW. You receive an Exhaust Gas Monitor (EGM) alarm. Per SOP #15, 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 notify the Senior Reactor Operator on duty.

QUESTION C.15 [1.0 point]

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.

Category C: Facility and Radiation Monitoring Systems QUESTION C.16 [1.0 point]

Which ONE of the following is currently the source of neutrons for INITIAL startup operation of the WSU reactor?

a. Americium - Beryllium.

b. Antimony - Beryllium.

c. Radon - Beryllium.

d. Beryllium Reflector.

QUESTION C.17 [1.0 point]

The Main purpose for setting a conductivity limit of the pool water is to:

a. Maintain the departure of nucleate boiling ratio (DNBR) greater than the unity.

b. Minimize the possibility of corrosion of the cladding on the fuel elements.

c. Extend integrity of resin bed on the demineralizer.

d. Minimize Ar-41 released to the public.

QUESTION C.18 [1.0 point]

WSU Technical Specifications requires all dry new fuel storage facilities shall have a configuration where keff is less than ______ under water flooded conditions.

a. 0.6

b. 0.7

c. 0.8

d. 0.9

Category C: Facility and Radiation Monitoring Systems QUESTION C.19 [1.0 point]

The MAIN purpose of small flow holes drilled at the bottom of the shroud of the control rod drive system 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.

QUESTION C.20 [1.0 point]

How much water is required above the top of the core to maintain the radiation shielding requirements of the Reactor Pool Water System?

a. 10 feet

b. 12 feet

c. 14 feet

d. 16 feet

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

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

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

Reference:

Glasstone, Nuclear Reactor Engineering, Section 1.47 & Burns, Section 3.2.1, page 3-5 A.02 Answer: b

Reference:

LaMarsh 3rd ed., Section 7.5, pg. 377 & Burns, Figure 8.1, page. 8-6 A.03 Answer: d

Reference:

Burn, R., Introduction of Nuclear Reactor Operations, © 1982, Sec 3.3.1, page 3-16.

A.04 Answer: d

Reference:

P = P0et/T 3 = 1

• et/32 ; t = 32

• ln(3) ; t = 35.2 sec A.05 Answer: c

Reference:

P = P et/T --> T= t/Ln(P/ P0 ); T= 120/Ln(100 ); T = 26 sec.

A.06 Answer: a

Reference:

DOE Handbook, Vol.1, Module 1, EO 4.7, p. 51 A.07 Answer: a

Reference:

Burns, Example 7.2 (b), page 7-4 A.08 Answer a

Reference:

DOE Handbook, Vol. 1, Module 1, EO 4.3, p.52 A.09 Answer: a

Reference:

Burn, R., Introduction to Nuclear Reactor Operations, © 1988, Section 5.1, Subcritical Multiplication A.10 Answer: b

Reference:

DOE Handbook Vol. 2 Module 4 A.11 Answer: b

Reference:

DOE Handbook Vol. 1 Module 2, Section 3.0

Category A: Reactor Theory, Thermodynamics, and Facility Operating Characteristics A.12 Answer: b

Reference:

DOE Handbook, Vol. 2, Module 4, EO 2.1, p.17 A.13 Answer: a

Reference:

Standard NRC question A.14 Answer: b

Reference:

Standard NRC question A.15 Answer: b

Reference:

T = DT/ln(2) = 68 seconds/0.693 = 98.124 98 seconds A.16 Answer: b

Reference:

Burn, R., Introduction to Nuclear Reactor Operations, © 1988, Section 3.2.2.

A.17 Answer: d

Reference:

DOE Fundamentals of Nuclear Engineering, Chapter 3, page 61 A.18 Answer: c

Reference:

1 2 = (1 2)/(1 1) 200 1 2 Solve for Keff2, 110 = 1 0.95 ; therefore Keff2 = 0.91 (2 1) (0.91 0.95)

= = = 0.046 21 (0.91)(0.95)

A.19 Answer: c

Reference:

NRC Standard Question A.20 Answer: c

Reference:

Burn, R., Introduction to Nuclear Reactor Operations, © 1988, Section 5.7.3

Category B: Normal/Emergency Operating Procedures and Radiological Controls B.01 Answer: c

Reference:

WSU TS 3.6.4 B.02 Answer: c

Reference:

WSU TS Definition B.03 Answer: b

Reference:

WSU TS 6.2.3 B.04 Answer: d

Reference:

WSU TS 4.2.1 B.05 Answer: b

Reference:

DR = DR0*e -t 1.25 rem/hr = 5 rem/hr* e -(5hr)

Ln(1.25/5) = -*5 --> =0.277; solve for t: Ln(.625/5)=-0.277 *t 5 or t = 7.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> B.06 Answer: d

Reference:

10 CFR 55.59(a)(1)

B.07 Answer: b

Reference:

WSU TS 3.3.1 B.08 Answer: d

Reference:

10 CFR 55(a)

B.09 Answer: a

Reference:

DR = DR0*e -t 30% is decayed, so 70% is still there 70% =100%* e -(3hrs)

Ln(70/100) = -*1 -->=0.357 t1/2=Ln(2)/ --> .693/.357 or t=1.94 hours0.00109 days <br />0.0261 hours <br />1.554233e-4 weeks <br />3.5767e-5 months <br /> B.10 Answer: c

Reference:

10 CFR 20.1301(1)

B.11 Answer: a

Reference:

10 CFR 20.1004

Category B: Normal/Emergency Operating Procedures and Radiological Controls B.12 Answer: d

Reference:

DR = DR*e -t 2 rem/hr =4 rem/hr* e -(5hr)

Ln(2/4) = -*5 --> =0.1386; solve for t: Ln(.25/4)=-0.1386 (t) t=20 hours B.13 Answer: b

Reference:

l2 = l1D12/d22; l2 = (400 mR/hr)(2m)2 / (4m)2; l2 = 100 mR/hr B.14 Answer: a

Reference:

WSU EP Section 2.9 B.15 Answer: c

Reference:

WSU EP Table 3.5 B.16 Answer: d

Reference:

WSU TS 4.4.3 B.17 Answer: c

Reference:

10 CFR 20.1004, Table 1004(b).1 B.18 Answer: c

Reference:

Standard NRC question B.19 Answer: a

Reference:

WSU EP 3.1.12 B.20 Answer: a

Reference:

WSU TS 2.1

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

Reference:

WSU TS 5.2 C.02 Answer: c

Reference:

WSU SOP-10, Maintenance of the Reactor Pool Facilities (C.1 through 3)

C.03 Answer: a

Reference:

WSU SAR 4.2.2 C.04 Answer: b

Reference:

WSU SAR7.4.6 C.05 Answer: d

Reference:

WSU TS 3.4.4 C.06 Answer: d

Reference:

WSU TS 3.4.4 C.07 Answer: d

Reference:

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

C.08 Answer: d

Reference:

WSU SAR 4.2.2 C.09 Answer: c

Reference:

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

C.10 Answer: c

Reference:

WSU TS 3.1.6.1 C.11 Answer: c

Reference:

WSU SAR 6.2.2 Containment C.12 Answer: a

Reference:

WSU TS 3.2.3 Basis C.13 Answer: b

Reference:

WSU SAR Table 7.2-2

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

Reference:

WSU SOP-15 Section C.2.e. Exhaust Gas Monitor C.15 Answer: d

Reference:

WSU SAR 4.2.2 C.16 Answer: b

Reference:

WSU SAR 11.1.1.b C.17 Answer: b

Reference:

WSU TS 3.3.1 C.18 Answer: c

Reference:

WSU TS 5.5.1 C.19 Answer: a

Reference:

WSU SAR 4.2.2 C.20 Answer: d

Reference:

WSU TS 5.8.4