ML18162A315

Examination Report No. 50-297/OL-18-01, North Carolina State University

ML18162A315
Person / Time
Site:	North Carolina State University, 05574728, 05574729, 05574730
Issue date:	06/08/2018
From:	Anthony Mendiola Research and Test Reactors Oversight Projects Branch
To:	Hawari A North Carolina State University
References
50-297/18-01 50-297/OL-18
Download: ML18162A315 (39)

Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 June 8, 2018 Dr. Ayman I. Hawari, Director Nuclear Reactor Program Department of Nuclear Engineering North Carolina State University Campus Box 7909 2500 Stinson Drive Raleigh, NC 27695-7909

SUBJECT:

EXAMINATION REPORT NO. 50-297/OL-18-01, NORTH CAROLINA STATE UNIVERSITY

Dear Dr. Hawari:

During the week of April 23, 2018, the U.S. Nuclear Regulatory Commission (NRC) administered operator licensing examinations at your North Carolina State University PULSTAR reactor. The examination was conducted according to NUREG-1478, "Operator Licensing Examiner Standards for Research and Test Reactors," Revision 2. Examination questions and preliminary findings were discussed with you and 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 enclosure will be available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records (PARS) component of NRC's Agencywide Documents Access and Management System (ADAMS). ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html. The NRC is forwarding the individual grades to you in a separate letter which will not be released publicly. Should you have any questions concerning this examination, please contact Mrs. Paulette Torres at (301) 415-5656 or via e-mail Paulette.Torres@nrc.gov.

Sincerely,

/RA/

Anthony J. Mendiola, Chief Research and Test Reactors Oversight Branch Division of Licensing Projects Office of Nuclear Reactor Regulation Docket No. 50-297

Enclosures:

1. Examination Report No. 50-297/OL-18-01

2. Written Examination cc: w/o enclosure: See next page

ML18162A315 NRR-074 OFFICE NRR/DLP/PROB NRR/DLP/PROB/OLA NRR/DLP/PROB/BC NAME PTorres CRandiki AMendiola DATE 05/09/2018 06/05/2018 06/08/2018 North Carolina State University Docket No. 50-297 cc:

Office of Intergovernmental Relations 116 West Jones Street Raleigh, NC 27603 Dr. Kostadin Ivanov, Head Department of Nuclear Engineering North Carolina State University Campus Box 7909 Raleigh, NC 27695-7909 W. Lee Cox, Section Chief Department of Health and Human Services Division of Health Service Regulation Radiation Protection Section 1645 Mail Service Center Raleigh, NC 27699-1645 Dr. Louis Martin-Vega, Dean College of Engineering North Carolina State University 113 Page Hall Campus Box 7901 Raleigh, NC 27695-7901 Test, Research and Training Reactor Newsletter P.O. Box 118300 University of Florida Gainesville, FL 32611

U. S. NUCLEAR REGULATORY COMMISSION OPERATOR LICENSING INITIAL EXAMINATION REPORT REPORT NO.: 50-297/OL-18-01 FACILITY DOCKET NO.: 50-297 FACILITY LICENSE NO.: R-120 FACILITY: North Carolina State University PULSTAR reactor EXAMINATION DATE: April 23-25, 2018 SUBMITTED BY: ___________/RA/ ___________ ___05/09/2018______

Paulette Torres, Chief Examiner Date

SUMMARY

During the week of April 23, 2018 the NRC administered licensing examinations to three Reactor Operator (RO) applicants. All three RO applicants passed all portions of the examination.

REPORT DETAILS

1. Examiner: Paulette Torres, Chief Examiner, NRC

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:

Paulette Torres, Chief Examiner, NRC Gregory Gibson, Senior Reactor Operator, NCSU Andrew T. Cook, Manager of Engineering and Operations, NCSU The NRC examiner found one area of common deficiency between all three candidates: 1) Types of dosimetry and how they measure exposure to radiation.

The facility should consider strengthening this area for future examinations.

ENCLOSURE 1

U. S. NUCLEAR REGULATORY COMMISSION NON-POWER REACTOR LICENSE EXAMINATION FACILITY: NCSU REACTOR TYPE: PULSTAR DATE ADMINISTERED: 04/25/2018 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 2

A. Reactor Theory, Thermohydraulics & 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 SECTION A *****)

B. Normal/Emergency 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 SECTION B *****)

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

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

C01 a b c d ___

C02 a b c d ___

C03 a b c d ___

C04 a b c d ___

C05 a b c d ___

C06 a b c d ___

C07 a b c d ___

C08 a b c d ___

C09 a b c d ___

C10 a b c d ___

C11 a b c d ___

C12 a b c d ___

C13 a b c d ___

C14 a b c d ___

C15 a b c d ___

C16 a b c d ___

C17 a b c d ___

C18 a b c d ___

C19 a b c d ___

C20 a b c d ___

(***** END OF SECTION 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

=

Pmax =

( )2 (2 ) eff = 0.1sec 1 t

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

SUR = 26 .06

( ) (

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

(1 ) M=

1

= 2 CR P = P0 10SUR(t )

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

• M= SDM = =

1 K eff 2 K eff

• 0.693 K eff 2 K eff1

+ T1 =

eff + & 2 K eff1 K eff 2 K eff 1

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

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

R2 Peak2 Peak1 DR - Rem, Ci - curies, E - Mev, R - feet 1 Curie = 3.7 x 1010 dis/sec 1 kg = 2.21 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

North Carolina State University Pulstar Reactor Operator Licensing Examination Week of April 23, 2018

Section A: Reactor Theory, Thermohydraulics & Facility Operating Characteristics Page 2 QUESTION A.01 [1.0 point, 0.25 each]

Match the following neutron interactions with its net result. Answers can be used more than once.

Column A Column B

a. Elastic Scattering 1. - Rays

b. Inelastic Scattering 2. Positive Ions

c. Nuclear Reactions 3. Protons

d. Capture QUESTION A.02 [1.0 point]

Which ONE of the following factors 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.03 [1.0 point]

Shutdown Margin is defined as:

a. The negative reactivity inserted by an increase in moderator temperature within the core when the reactor is brought from zero to full power.

b. Provides a measure of excess reactivity available to overcome fission product buildup, fuel burnup, and power defect.

c. The amount of negative reactivity that would be added to a core if the rods in a critical, cold, clean reactor were fully inserted.

d. The amount of reactivity available above what is required to keep the reactor critical.

Section A: Reactor Theory, Thermohydraulics & Facility Operating Characteristics Page 3 QUESTION A.04 [1.0 point]

The count rate is 100 cps. An experimenter inserts an experiment into the core, and the count rate decreases to 60 cps. Given the initial Keff of the reactor was 0.92, what is the worth of the experiment?

a. = - 0.07

b. = + 0.07

c. = - 0.02

d. = + 0.02 QUESTION A.05 [1.0 point]

Xenon-135 is formed directly by decay of __________.

a. Antimony-135

b. Cesium -135

c. Iodine-135

d. Tellurium-135 QUESTION A.06 [1.0 point]

What happens to the mass number and the atomic number of an element when it undergoes beta decay?

a. The mass number decreases by 4 and the atomic number decreases by 2.

b. The mass number does not change and the atomic number decreases by 2.

c. The mass number increases by 2 and the atomic number increases by 1.

d. The mass number does not change and the atomic number increases by 1.

Section A: Reactor Theory, Thermohydraulics & Facility Operating Characteristics Page 4 QUESTION A.07 [1.0 point]

The reactor is critical at 5 watts. Which ONE of the following correctly describes the reactor behavior when a reactivity worth of 0.50 % K/K is IMMEDIATELY inserted to the reactor core?

a. Subcritical

b. Critical

c. Supercritical

d. Delayed Critical QUESTION A.08 [1.0 point]

Which ONE of the following statements correctly describes the term neutron lifetime?

a. The mean time required for fission neutrons to slow down to thermal energies.

b. The average time that thermal neutrons diffuse before being lost in some way.

c. The time between succeeding neutron generations and is the sum of fission time, slowing down time, and diffusion time.

d. The average time between the release of a neutron in a fission reaction and its loss from the system by absorption or escape.

QUESTION A.09 [1.0 point]

Most text books list for a U235 fueled reactor as 0.0065 K/K and eff as being 0.0075 K/K.

Why is eff larger than ?

a. Delayed neutrons are born at lower energies than prompt neutrons resulting in a less loss due to leakage for these neutrons.

b. Delayed neutrons are born at higher energies than prompt neutrons resulting in a greater worth for these neutrons.

c. The fuel includes U238 which has a relatively large for fast fission.

d. Some U238 in the core becomes Pu239 (by neutron absorption) which has a larger for fission.

Section A: Reactor Theory, Thermohydraulics & Facility Operating Characteristics Page 5 QUESTION A.10 [1.0 point]

The neutron microscopic cross-section for absorption a generally:

a. Increases as neutron energy increases.

b. Decreases as neutron energy increases.

c. Increases as the mass of the target nucleus increases.

d. Decreases as the mass of the target nucleus increases.

QUESTION A.11 [1.0 point]

Which ONE is true about subcritical multiplication? As the reactor approaches criticality, the parameter:

a. keff approaches zero.

b. 1/M approaches zero.

c. M approaches one.

d. approaches infinity.

QUESTION A.12 [1.0 point]

Which ONE defines an integral rod worth curve?

a. Conforms to an axial flux shape.

b. Any point on the curve represents the amount of reactivity that one inch of rod motion would insert at that position in the core.

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

d. Reactivity is highest at the top of the core and lowest at bottom of the core.

Section A: Reactor Theory, Thermohydraulics & Facility Operating Characteristics Page 6 QUESTION A.13 [1.0 point]

Which ONE of the following is the correct reason for the 80 second negative period following a reactor scram?

a. The fuel temperature coefficient adding positive reactivity due to the fuel temperature decrease following a scram.

b. The ability of U-235 to fission with source neutrons.

c. The decay constant for the longest lived precursor.

d. The amount of negative reactivity added on a scram being greater that the shutdown margin.

QUESTION A.14 [1.0 point]

A reactor is operating at a power of 10 W. If there is a reactivity insertion of = 0.00065, how long is it before the reactor power reaches 10 kW? (Assume eff = 0.0065, = 0.07 sec-1 and T

= 129 sec)

a. 2 min

b. 10 min

c. 15 min

d. 20 min QUESTION A.15 [1.0 point]

The term ____________ defines the condition where no delay neutrons are required.

a. Prompt Jump

b. Prompt Drop

c. Asymptotic Period

d. Prompt Critical

Section A: Reactor Theory, Thermohydraulics & Facility Operating Characteristics Page 7 QUESTION A.16 [1.0 point]

A subcritical reactor is being started up. A control blade is raised in four equal steps. Which ONE of the following statement most accurately describes the expected reactor response?

a. Power increases by the same amount for each withdrawal.

b. Each withdrawal will add the same amount of reactivity.

c. The time for power to stabilize after each successive withdrawal increases.

d. A lower critical rod height is attained by decreasing the time intervals between withdrawals.

QUESTION A.17 [1.0 point]

Which ONE of the following describes the characteristics of a good moderator?

a. Large scattering cross section and small absorption cross section.

b. Small scattering cross section and large absorption cross section.

c. Small scattering cross section and small absorption cross section.

d. Large scattering cross section and large absorption cross section.

QUESTION A.18 [1.0 point, 0.25 each]

The six factor formula is stated as keff = Lf p Lt f .

Match with the correct answer:

Column A Column B

a. Thermal utilization factor (f) 1. Change as fertile material is converted to fissile material.

b. f and p factors 2. Can be changed, by inserting movable control rods in and out.

c. f, p, Reproduction () factors 3. Changes reactor power.

d. Resonance escape probability (p) 4. Change as fuel is burned.

Section A: Reactor Theory, Thermohydraulics & Facility Operating Characteristics Page 8 QUESTION A.19 [1.0 point]

Reactor period is defined as ____________.

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

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

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

d. The fraction of all neutrons that are born as delayed neutrons.

QUESTION A.20 [1.0 point]

Which ONE of the following is the best approximation of the amount of energy released by the fission of one atom of U-235?

a. 5 - 10 MeV

b. 50 - 70 MeV

c. 100 - 120 MeV

d. 180 - 210 MeV

• • • • • • • • • • • • • • • • • End of Section A *****************

Section B: Normal/Emergency Procedures and Radiological Controls Page 9 QUESTION B.01 [1.0 point]

All of the following materials shall be doubly encapsulated EXCEPT:

a. Corrosive

b. Explosives

c. Gases

d. Liquids QUESTION B.02 [1.0 point]

To prevent an inadvertent reactor SCRAM due to moving an irradiated fuel assembly near the Linear Channel detector, the Linear Channel should be set to the __________

range.

a. 30 mW

b. 1 mW

c. 10 kW

d. 1 MW QUESTION B.03 [1.0 point]

The reactor shall not be operated unless the excess reactivity is not greater than 3970 pcm. This is an example of a:

a. Safety Limit.

b. Limiting Safety System Setting.

c. Limiting Condition of Operation.

d. Surveillance Requirement.

Section B: Normal/Emergency Procedures and Radiological Controls Page 10 QUESTION B.04 [1.0 point]

The nominal specifications of the reactor fuel shall be:

a. 6% enriched uranium clad with aluminum.

b. 94% enriched uranium clad with aluminum.

c. 96% enriched uranium clad with zircaloy.

d. 4% enriched uranium clad with zircaloy.

QUESTION B.05 [1.0 point]

Per Technical Specifications, the Control rod drop times shall be determined:

a. Daily

b. Monthly

c. Annually

d. Biennially QUESTION B.06 [1.0 point]

The Quality Factor (Q) is used to convert:

a. Dose in rads to dose equivalent in rems.

b. Dose in rems to dose equivalent in rads.

c. Contamination in rads to contamination equivalent in rems.

d. Contamination in rems to contamination equivalent in rads.

Section B: Normal/Emergency Procedures and Radiological Controls Page 11 QUESTION B.07 [1.0 point]

Reactor Operator works in a high radiation area for eight (8) hours a day. The dose rate in the area is 100 mR/hour. Which ONE of the following is the MAXIMUM number of days in which Reactor Operator may perform his duties WITHOUT exceeding 10 CFR 20 limits?

a. 5 days

b. 6 days

c. 7 days

d. 12 days QUESTION B.08 [1.0 point]

Radiation dose to Emergency personnel is limited to __________ TEDE for lifesaving actions or for the protection of large populations by volunteers fully aware of risk involved.

a. > 25 rem

b. Up to 25 rem

c. Up to 10 rem

d. Up to 5 rem QUESTION B.09 [1.0 point, 0.25 each]

Match the 10 CFR 55 requirements for maintaining an active operator license in column A with the corresponding time period from column B (answers can be used more than once).

Column A Column B

a. Medical Exam 1. 1 year

b. Pass Requalification Operating Test 2. 2 years

c. Renewal Application of Existing License 3. 4 years

d. Pass Requalification Written Examination 4. 6 years

Section B: Normal/Emergency Procedures and Radiological Controls Page 12 QUESTION B.10 [1.0 point]

Which ONE of the following terms defines the actions taken to avoid or reduce the potential dose to individuals and to prevent damage to property?

a. Assessment Actions

b. Corrective Actions

c. Protective Actions

d. Recovery Actions QUESTION B.11 [1.0 point]

After a building evacuation, the reactor building re-entry point shall be determined by the

__________ on the basis of available information.

a. Incident Commander

b. Reactor Health Physicist

c. Emergency Operations Manager

d. Emergency Coordinator QUESTION B.12 [1.0 point]

Significant releases of radioactive materials as a result of experiment failures is a situation that can be classified as:

a. Notification of Unusual Event

b. Alert

c. Site Area Emergency

d. General Emergency

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

Which ONE of the following is the 10 CFR 20 definition of Total Effective Dose Equivalent (TEDE)?

a. The sum of the deep dose equivalent and the committed effective dose equivalent.

b. The dose that your whole body receives from sources outside the body.

c. The sum of the external deep dose and the organ dose.

d. The dose to a specific organ or tissue resulting from an intake of radioactive material.

QUESTION B.14 [1.0 point]

If a gamma source measures 425 mR/hr at one foot, what will it measure at three feet?

a. 0.021 mR/hr

b. 47 mR/hr

c. 142 mR/hr

d. 207 mR/hr QUESTION B.15 [1.0 point]

An example of a record to be retained for the lifetime of the reactor facility is:

a. Audit summaries.

b. Reportable events.

c. Experiments performed with the reactor.

d. Gaseous and liquid radioactive waste released to the environs.

Section B: Normal/Emergency Procedures and Radiological Controls Page 14 QUESTION B.16 [1.0 point]

The preferred way of approaching reactor criticality is by a series of doubling counts on the __________. After approximately 5 doublings the reactor will be close to critical.

a. Source Range Channel

b. Linear Channel

c. Log N Channel

d. Safety Channel QUESTION B.17 [1.0 point]

Upon activation of the evacuation alarm, personnel in the Reactor Bay will assemble:

a. Outside the North entrance of the BEL

b. In the Control Room

c. In the Change Room

d. In the BEL Conference Room on the first floor QUESTION B.18 [1.0 point]

__________ is an experiment which contains fissionable material with the exception of detectors.

a. Tried Experiment

b. Fueled Experiment

c. Movable Experiment

d. Secured Experiment

Section B: Normal/Emergency Procedures and Radiological Controls Page 15 QUESTION B.19 [1.0 point]

Which ONE of the following systems is used primarily to fill the pool and beam tubes?

a. Service Water System

b. Secondary Coolant System

c. Primary Coolant Cleanup System

d. Primary Coolant Makeup Water System QUESTION B.20 [1.0 point]

No console annunciation or external indicator lights are associated with this SCRAM.

a. Low Pool Level SCRAM

b. Low Primary Flow SCRAM

c. Ground Fault Detection SCRAM

d. Safety Flapper Not Closed SCRAM

• • • • • • • • • • • • • • • • • • • • • • • • • • • • • • End of Section B ********************************

Section C: Facility and Radiation Monitoring Systems Page 16 QUESTION C.01 [1.0 point]

Which ONE of the following Control Rod Drive Mechanisms components can be de-energized in less than 50 milliseconds after a SCRAM demand?

a. Motor

b. Electromagnet

c. Lead Screw Drive

d. Gear Reduction System QUESTION C.02 [1.0 point]

Which ONE of the following interlocks prevent the drive mechanisms from being moved in the down direction?

a. Magnet power.

b. Automatic power control.

c. Up-drive power for the individual control rod drive mechanisms.

d. There are no interlocks that prevent this action.

QUESTION C.03 [1.0 point]

The neutron startup source used in the NCSU PULSTAR reactor is:

a. Am-Be

b. Ra-Be

c. Sb-Be

d. Pu-Be

Section C: Facility and Radiation Monitoring Systems Page 17 QUESTION C.04 [1.0 point]

The coolant system is designed to remove up to 1 MW of heat from the PULSTAR Reactor and maintain a _________ flow rate on the primary side.

a. 500 gpm

b. 700 gpm

c. 800 gpm

d. 1150 gpm QUESTION C.05 [1.0 point]

Which ONE of the following locations shows the highest percentage measurement of routine Ar-41 production?

a. Air at the pool surface

b. Air dissolved in pool water

c. Pneumatic Transfer System

d. Beam Tubes and Thermal Column QUESTION C.06 [1.0 point]

Which ONE of the following Required Radiation Area Monitors has an alarm setpoint of 5 mR/hr?

a. Control Room

b. Over-the-Pool

c. Stack Gas

d. West Wall

Section C: Facility and Radiation Monitoring Systems Page 18 QUESTION C.07 [1.0 point]

What kind of detector feeds the Safety Channel?

a. Fission Chamber

b. Compensated Ion Chamber

c. Uncompensated Ion Chamber

d. Scintillation QUESTION C.08 [1.0 point]

Which ONE of the following experimental facilities is considered an In-reflector facility?

a. Beam Ports

b. Rotating Exposure Ports

c. Pneumatic Transfer System

d. Thermal Column Enclosure QUESTION C.09 [1.0 point]

The neutron absorbing blades are comprised of all of the following elements EXCEPT:

a. Cadmium

b. Boron

c. Silver

d. Indium

Section C: Facility and Radiation Monitoring Systems Page 19 QUESTION C.10 [1.0 point]

__________ of the Linear Channel prevents an automatic channel operation when the demand potentiometer setting exceeds actual reactor power by more than +/-9%.

a. Trip #1

b. Trip #2

c. Trip #3

d. Trip #4 QUESTION C.11 [1.0 point]

The below picture show a typical detail of the:

a. Reactor Tank

b. Delay Tank

c. Waste Tank

d. Void Tank

Section C: Facility and Radiation Monitoring Systems Page 20 QUESTION C.12 [1.0 point]

In support of ALARA, the PULSTAR goal for the typical occupational worker is established as the total effective dose equivalent equal to:

a. 2% of the NRC limit

b. 10% of the NRC limit

c. 20% of the NRC limit

d. Not applicable. Same as the NRC limit QUESTION C.13 [1.0 point]

In accordance with Technical Specifications, the Reactor is SECURE when all of the following conditions exist EXCEPT:

a. The reactor key switch is in the OFF position and the key is removed from the lock

b. Power is unavailable to the control rod drive mechanism electromagnets.

c. No work is in progress involving core fuel, core structure, installed control rods, or control rod drives unless they are physically decoupled from the control rods.

d. No experiments are being moved or serviced that have, on movement, a reactivity worth exceeding one dollar (730 pcm).

QUESTION C.14 [1.0 point]

Two cylindrical fuel storage pits, 2 feet in diameter and 4 feet deep extend below the bottom of the pool liner. Each fuel storage pit has _________ locations in a subcritical configuration.

a. 7

b. 10

c. 13

d. 20

Section C: Facility and Radiation Monitoring Systems Page 21 QUESTION C.15 [1.0 point]

The Auxiliary Generator Distribution Panel (AGDP), houses the feeder breakers that supply auxiliary power to:

a. Exhaust Fan

b. Confinement Fans #1 and #2

c. Reactor Bay Supply Fan

d. Control Room Supply Fan QUESTION C.16 [1.0 point]

Following a loss of reactor building differential pressure (P) it is assumed that the reactor is operating with the __________ operating when the loss of P occurs.

a. Main HVAC System

b. Primary Coolant System

c. Radiation Monitoring System

d. Instrumentation and Control System QUESTION C.17 [1.0 point]

There are four one-inch diameter holes in the zircaloy box just below the fuel pin support plate located in each fuel assembly box. These holes are provided as an Engineered Safety Feature design in order to:

a. Eliminate the blocked flow type of accident.

b. Ensure proper alignment of the core grid plate.

c. Ensure unimpeded coolant flow through the core.

d. Allow thermocouple leads from instrumented fuel elements to pass out of the core.

Section C: Facility and Radiation Monitoring Systems Page 22 QUESTION C.18 [1.0 point]

The nuclear detector nitrogen purge pressure output is set at _________ psig.

a. 14

b. 16

c. 19

d. 21 QUESTION C.19 [1.0 point]

The fission chamber full out position is:

a. 0

b. 12

c. 24

d. 36 QUESTION C.20 [1.0 point]

Which ONE of the following is referred as the 12 square beam tube?

a. BP 3

b. BP 4

c. BP 5

d. BP 6

• • • • • • • • • • • • • • • • • • • End of Section C ****************************

• • • • • • • • • • • • • • • • • • • End of the Exam ***************************

Section A: Theory, Thermo & Facility Operating Characteristics Page 23 A.01 Answer: a,3 b,1 c,2 d,1 REF: Denaro and Jayson, Fundamentals of Radiation Chemistry, pg. 51 A.02 Answer: a REF: Burns, Session 3.3.2, pg. 3-18 A.03 Answer: c REF: Burns, example 6.2.3 (a), pg. 6-4 A.04 Answer: a REF: CR1 / CR2 = (1 - Keff2) / (1 - Keff1) 100 / 60 = (1 - Keff2) / (1 - 0.92)

Therefore Keff2 = 0.867

= (Keff2 - Keff1) / (Keff2

• Keff1)

= (0.867 - 0.92) / (0.867

• 0.92)

= - 0.0664 A.05 Answer: c REF: Burns, Figure 8.1, pg. 8-6 A.06 Answer: d REF: DOE Handbook volume 1, NP-01, pg. 24, decay = ZXA Z+1YA +e + ,

A = atomic mass = proton + neutrons Z = # protons A.07 Answer: c REF: Burn, Section 4.2, Figure 4-1, pg. 4-2 0.5 % K/K = 0.005 K/K = , > 0

= (keff -1) / keff, then keff = 1.005 When k > 1, > 0 and reactor is supercritical A.08 Answer: d REF: Burns, section 3.3.5, pg. 3-23 A.09 Answer: a REF: Burns, Section 3.2.4, pg. 3-12

Section A: Theory, Thermo & Facility Operating Characteristics Page 24 A.10 Answer: b REF: Foster & Wright, Basic Nuclear Engineering 4th ed., Figure 8.3, pg. 202 A.11 Answer: b REF: Burns, Table 5.5, pg. 5-15 A.12 Answer: c REF: Burns, Section 7.3, pg. 7-5 to 7-7 A.13 Answer: c REF: Lamarsh, 3rd ed., pg. 345 A.14 Answer: c REF: Reactor power: P(t) = P(0) exp(t/T)

Solving for t, we find t = T ln [P(t)/P(0)] = 129 ln (10,000/10) = 891 s =

14.9 min Also,

= 0.00065, then T = (eff - )/( ) = (0.0065 - 0.00065)/(0.07)(0.00065) = 129 seconds A.15 Answer: d REF: Knief, Nuclear Engineering, 2nd ed., pg. 142 A.16 Answer: c REF: Burns, Section 5.3, pg. 5-7 A.17 Answer: a REF: DOE Handbook part 2, module 2, pg. 24 A.18 Answer: a,2 or B b,4 or D c,1 or A d,3 or C REF: DOE Handbook part 2, module 3, pg. 10, 15 A.19 Answer: a REF: DOE Handbook part 2, module 4, pg. 21

Section A: Theory, Thermo & Facility Operating Characteristics Page 25 A.20 Answer: d REF: Lamarsh, Table 3.6, pg. 88 Foster and Wright, Basic Nuclear Engineering, 4th ed., table 4.2, pg. 76, The energy release per fission is approximately 200 MeV.

Section B Normal, Emergency and Radiological Control Procedures Page 26 B.01 Answer: b REF: TS 3.7 a., pg. 23 B.02 Answer: c REF: NRP-OP-301, Section 2.6, pg. 4 of 8 B.03 Answer: c REF: TS 3.2 b, pg. 14 B.04 Answer: d REF: TS 5.1 a., pg. 38 B.05 Answer: c REF: TS 4.2 b., pg. 32 B.06 Answer: a REF: 10 CFR 20.1004(b)

B.07 Answer: b REF: 10 CFR 20.1201(a)(1) 1hr 1day 5000 mR = 6.25days 100 mR 8hr B.08 Answer: a REF: Emergency Procedure 1, Section 5.4 (10)(d), pg. 10 EP 7.5.7 b., pg. 32 B.09 Answer: a, 2 b, 1 c, 4 d, 2 REF: 10 CFR 55.53 Conditions of Operator Licenses 10 CFR 55.55 Expiration 10 CFR 55.59 Requalification B.10 Answer: c REF: EP Section 2, pg. 7

Section B Normal, Emergency and Radiological Control Procedures Page 27 B.11 Answer: a REF EP 7.5.4, pg. 31 B.12 Answer: b REF: Emergency Procedure 4, Section 5.1 (b), pg. 2 B.13 Answer: a REF: 10 CFR 20.1003, Definitions B.14 Answer: b REF: Given DR1(d1)2 = DR2 (d2)2 Then DR2 = DR1 (d2/d1)2 DR2 = 425 mR (3/1)2 DR2 = 47.2 mR/hr B.15 Answer: d REF: TS 6.8.2 a., pg. 56 B.16 Answer: a REF: NRP-OP-101, Section 2.12 NOTE, pg. 5 of 35 B.17 Answer: c REF: EP 7.5.1, pg. 30 Emergency Procedure 1, Section 5.1 (2), pg. 3 and Section 5.1 (3), pg. 4 B.18 Answer: b REF: NRP-OP-104, Section 1.2.3, pg. 3 of 20 B.19 Answer: a REF: NRP-OP-202, Section 1.1, pg. 3 of 7 B.20 Answer: c REF: NRP-OP-105, Section 2.3.8, pg. 5 of 18

Section C Facility and Radiation Monitoring Systems Page 28 C.01 Answer: b REF: SAR 4.2.2, pg. 4-8 C.02 Answer: d REF: SAR 7.3.3, pg. 7-2 C.03 Answer: d REF: SAR Table 1-1, pg. 1-14 and SAR 4.2.4, pg. 4-10 C.04 Answer: a REF: SAR Table 1-1, pg. 1-14, SAR Table 4-10, pg. 4-74, SAR 5.1, pg. 5-1 TS 2.1.1, pg. 7-9 C.05 Answer: c REF: SAR 11.1.1.1, pg. 11-2 C.06 Answer: a REF: TS Table 3.5-1, pg. 19 C.07 Answer: c REF: SAR Figure 7.2, pg. 7-6, SAR 7.4.3.4, pg. 7-12 C.08 Answer: b REF: SAR 10.2.2.1, pg. 10-8 C.09 Answer: b REF: SAR 4.5.3.2.5, Section 5.4, pg. 4-61 C.10 Answer: d REF: SAR 7.4.3.3, pg. 7-12 C.11 Answer: b REF: SAR Figure 5-4, pg. 5-14 C.12 Answer: b REF: HP 1 Radiation Protection Program, Section 4.3.4, pg. 6

Section C Facility and Radiation Monitoring Systems Page 29 C.13 Answer: b REF: TS 1.2.22, pg. 4 C.14 Answer: c REF: SAR Table 4-1, pg. 4-3, SAR 5.2, pg. 5-2 C.15 Answer: b REF: TS 4.5.b, pg. 36 SAR Figure 8-2, pg. 8-5 C.16 Answer: a REF: NRP-OP-105, Section 4.4, pg. 13 of 18 TS 3.6 c, NOTE (3), pg. 22 C.17 Answer: a REF: SAR 6.2.5, pg. 6-11, SAR 13.2.5, pg. 13-21 C.18 Answer: b REF: NRP-OP-101, Appendix A - Startup Checklist (pg. 1 of 5), Part C.4, pg.

14 of 35 NRP-OP-101, Appendix B - Startup Checklist Instructions (pg. 1 of 17),

Part C.4, pg. 19 of 35 NRP-OP-103, Section 3.2.1.2, pg. 7 of 12 C.19 Answer: c REF: NRP-OP-101, Section 2.18, pg. 5 of 35 C.20 Answer: d REF: SAR Table 4-1, pg. 4-4 SAR Figure 4-7, pg. 4-12 SAR Table 4-2, pg. 4-28