ML20238C081
| ML20238C081 | |
| Person / Time | |
|---|---|
| Site: | University of Missouri-Columbia |
| Issue date: | 09/28/2020 |
| From: | Tate L NRC/NRR/DANU/UNPO |
| To: | Robertson D Univ of Missouri - Columbia |
| Nguyen J., 415-4007 | |
| Shared Package | |
| ML20163A021 | List: |
| References | |
| 50-186/OL-20-01 | |
| Download: ML20238C081 (39) | |
Text
September 28, 2020 Dr. J. David Robertson Reactor Facility Director University of Missouri- Columbia Research Reactor Center 1513 Research Park Columbia, MO 65211
SUBJECT:
EXAMINATION REPORT NO. 50-186/OL-20-01, UNIVERSITY OF MISSOURI
- COLUMBIA
Dear Dr. Robertson:
During the week of July 6, 2020, the U.S. Nuclear Regulatory Commission (NRC) administered an operator licensing examination at your University of Missouri - Columbia 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 (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 Mr. John Nguyen at (301) 415-4007 or via internet e-mail John.Nguyen@nrc.gov.
Sincerely, Digitally signed by Travis L.
Travis L. Tate Tate Date: 2020.09.28 12:18:10
-04'00' Travis 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. 50-186
Enclosures:
- 1. Examination Report No. 50-186/OL-20-01
- 2. Written examination cc: w/o enclosures: See next page
ML20238C081 NRR-079 OFFICE NRR/DANU/UNPO/CE NRR/DANU/UNPO NRR/DANU/UNPO/BC NAME JNguyen ZTaru TTate DATE 07/22/2020 08/25/2020 09/28/2020 University of Missouri-Columbia Docket No. 50-186 cc:
Les Foyto, Associate Director Reactor and Facilities Operations University of Missouri - Columbia Research Reactor Center 1513 Research Park Drive Columbia, MO 65211 Homeland Security Coordinator Missouri Office of Homeland Security P.O. Box 749 Jefferson City, MO 65102 Planner, Dept of Health and Senior Services Section for Environmental Public Health P.O. Box 570 Jefferson City, MO 65102 Deputy Director for Policy Department of Natural Resources 1101 Riverside Drive Fourth Floor East Jefferson City, MO 65101 A-95 Coordinator Commissioners Office Office of Administration P.O. Box 809 State Capitol Building, Room 125 Jefferson City, MO 65101 Planning Coordinator Missouri Department of Natural Resources 1101 Riverside Drive Jefferson City, MO 65101 Test, Research and Training Reactor Newsletter Attention: Amber Johnson Dept of Materials Science and Engineering University of Maryland 4418 Stadium Drive College Park, MD 20742-2115
U.S. NUCLEAR REGULATORY COMMISSION OPERATOR LICENSING INITIAL EXAMINATION REPORT REPORT NO.: 50-186/OL-20-01 FACILITY DOCKET NO.: 50-186 FACILITY LICENSE NO.: R-103 FACILITY: Tank EXAMINATION DATES: July 06 - 07, 2020 SUBMITTED BY: John Nguyen 07/22/2020 John Nguyen, Chief Examiner Date
SUMMARY
During the week of July 6, 2020, the NRC administered an operator licensing examination to one Reactor Operator (RO) candidate. The candidate passed all applicable portions of the examinations.
REPORT DETAILS
- 1. Examiner: John Nguyen, Chief Examiner, NRC
- 2. Results:
RO PASS/FAIL SRO PASS/FAIL TOTAL PASS/FAIL Written 1/0 0/0 1/0 Operating Tests 1/0 0/0 1/0 Overall 1/0 0/0 1/0
- 3. Exit Meeting:
Les Foyto, Associate Director, MURR Bruce Meffert, Reactor Manager, MURR Sean Schaefer, Assistant Reactor Manager, MURR Rob Hudson, Training Coordinator, MURR John Nguyen, Chief Examiner, NRC Dan Hoang, Civil Engineer, NRC Per discussion with the facility, prior to administration of the written examination, adjustments were accepted. At the conclusion of the meeting, the NRC examiner thanked the facility for their support in the administration of the examinations. The examiner also discussed the candidates weaknesses observed during the operating test to include modifications to procedures and equipment, operational limits and requirements, and portable radiation monitoring equipment.
ENCLOSURE 1
University of Missouri of Science -
Columbia Operator Licensing Examination Week of July 6, 2020 ENCLOSURE 2
U.S. NUCLEAR REGULATORY COMMISSION NON-POWER REACTOR LICENSE EXAMINATION FACILITY: University of Missouri -
Columbia REACTOR TYPE: Tank DATE ADMINISTERED: 07/07/2020 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 ___ (0.25 each)
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 ___ (0.25 each)
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 ___ (0.25 each)
B02 a b c d ___
B03 a b c d ___
B04 a b c d ___
B05 a b c d ___
B06 a ___ b ___ c ___ d ___ (0.25 each)
B07 a b c d ___
B08 a b c d ___
B09 a b c d ___
B10 a b c d ___
B11 a b c d ___
B12 a b c d ___
B13 a b c d ___
B14 a b c d ___
B15 a b c d ___
B16 a b c d ___
B17 a b c d ___
B18 a ___ b ___ c ___ d ___ (0.50 each)
B19 a b c d ___
(***** END OF CATEGORY B *****)
Category C - Facility and Radiation Monitoring Systems ANSWER SHEET Multiple Choice (Circle or X your choice)
If you change your answer, write your selection in the blank.
C01 a b c d ___
C02 a b c d ___
C03 a b c d ___
C04 a b c d ___
C05 a b c d ___
C06 a b c d ___
C07 a b c d ___
C08 a b c d ___
C09 a b c d ___
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
Pmax =
( )2 eff = 0.1sec 1 Q = m c P T = m H = UAT (2 )
t P = P0 e S S SCR = * =1x10 4 sec 1 K eff eff +
SUR = 26.06
( ) (
CR1 1 K eff1 = CR2 1 K eff 2 ) CR1 ( 1 ) = CR2 ( 2 )
(1 ) 1 CR P= P0 M= = 2 P = P0 10 SUR (t )
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 = =
2 K eff1 K eff 2 K eff 1
= DR = DR0 e t 2 DR1 d1 = DR2 d 2 2
K eff 6 Ci E (n ) ( 2 )2 = (1 )2 DR =
R2 Peak2 Peak1 DR - Rem, Ci - curies, E - Mev, R - feet 1 Curie = 3.7 x 1010 dis/sec 1 kg = 2.21 lb 1 Horsepower = 2.54 x 103 BTU/hr 1 Mw = 3.41 x 106 BTU/hr 1 BTU = 778 ft-lb °F = 9/5 °C + 32 1 gal (H2O) 8 lb °C = 5/9 (°F - 32) cP = 1.0 BTU/hr/lb/°F cp = 1 cal/sec/gm/°C
Category A: Reactor Theory, Thermodynamics, and Facility Operating Characteristics QUESTION A.01 [1.0 point]
Attached is the applicable portion from the chart of the nuclides, what will Fe-60 decay into?
- a. Mn-57
- b. Fe-61
- c. Co-62
- d. Co-60 28 Z
23 29 N 35 QUESTION A.02 [1.0 point]
A reactor is critical at 18.2 inches on a controlling blade. The controlling blade is inserted to a position of 17.9 inches. The reactivity removal during the insertion is 0.1%k/k. What is the differential rod worth?
- a. 0.1%k/k /inch at 18.20 inches
- b. 0.1%k/k /inch at 18.05 inches
- c. 0.33%k/k /inch at 17.9 inches
- d. 0.33%k/k /inch at 18.05 inches
Category A: Reactor Theory, Thermodynamics, and Facility Operating Characteristics QUESTION A.03 [1.0 point]
A reactor is subcritical with a Keff of 0.945. Which ONE of the following is the MINIMUM reactivity (K/K) that must be added to produce PROMPT criticality? Given eff=0.0078
- a. 0.0078 k/k
- b. 0.0550 k/k
- c. 0.066k/k
- d. 0.078 k/k QUESTION A.04 [1.0 point]
Which ONE of the following factors in the "six factor" formula is most affected by the non-fuel core material such as control rods, moderator, and structural components?
- a. The fast fission factor.
- b. The thermal utilization factor.
- c. The resonance escape probability.
- d. The thermal non-leakage probability.
QUESTION A.05 [1.0 point]
The reactor is critical at 500 watts. A control rod is withdrawn, adding a positive reactivity of
$0.25. Which ONE of the following will be the stable reactor period as a result of this reactivity insertion? Given beta effective = 0.0078
- a. 15 seconds
- b. 30 seconds
- c. 45 seconds
- d. 60 seconds
Category A: Reactor Theory, Thermodynamics, and Facility Operating Characteristics QUESTION A.06 [1.0 point, 0.25 each]
Identify whether each of the following conditions will INCREASE or DECREASE the shutdown margin of a reactor.
- a. Building up a Xenon peak in the reactor core.
- b. Inserting the Boron experiment to the reactor core.
- c. Removing a control rod from the reactor core.
- d. Increasing moderator temperature (assume negative temperature coefficient).
QUESTION A.07 [1.0 point]
Which term is described by the following?
The time from birth of a neutron to absorption and is the sum of slowing down time and diffusion time.
- a. Reactor period
- b. Neutron lifetime
- c. Multiplication time
- d. Delayed generation Time QUESTION A.08 [1.0 point]
A fissile material is one that will fission upon absorption of a thermal neutron. A fertile material is one that absorbs a neutron and becomes a fissile material. Which ONE of the following isotopes is the fertile material?
- a. U-235
- b. Pu-239
- c. Pu-241
- d. U-238
Category A: Reactor Theory, Thermodynamics, and Facility Operating Characteristics QUESTION A.09 [1.0 point]
Which ONE of the following is a number of proton(s), Z, in the tritium nucleus (1T3 or 1 H3)?
- a. 1 b.
- b. 2
- c. 3
- d. 4 QUESTION A.10 [1.0 point]
You are conducting a reactor startup after installing two (2) new fuel assemblies in the core.
Given the following rod withdrawal data, estimate the rod position when the reactor criticality would occur. The initial count rate on the nuclear instrumentation prior to rod withdrawal is 55 counts per second (cps).
Rod Count
- a. 13 in Withdrawal Rate (Inches) (cps)
- b. 14 in 0 55 2 58
- c. 15 in 4 60 6 61
- d. 16 in 8 69 10 78 12 137 QUESTION A.11 [1.0 point]
If the multiplication factor, k, is increased from 0.80 to 0.95, the amount of reactivity added is:
- a. 0.197 k/k
- b. -0.197 k/k
- c. 0.217 k/k
- d. 0.317 k/k
Category A: Reactor Theory, Thermodynamics, and Facility Operating Characteristics QUESTION A.12 [1.0 point]
The reactor is critical and increasing in power. Power has increased from 200 kW to 400 kW in 10 seconds. How long will it take at this rate for power to increase from 400 kW to 1 MW?
- a. 13.2 seconds
- b. 14.4 seconds
- c. 15.6 seconds
- d. 16.8 seconds QUESTION A.13 [1.0 point]
A reactor is changing from the criticality to prompt criticality. Which ONE of the following best describes the values of Keff and during the change?
- a. Keff = 1 and = 1
- b. Keff = 1 and = -eff
- c. Keff > 1 and 0 < < -eff
- d. Keff > 1 and -eff < < 1 QUESTION A.14 [1.0 point]
A reactor is decreasing with a - 80 second period shortly after shutdown. What is the time for power decreasing by a factor of 5?
- a. 40 seconds
- b. 55 seconds
- c. 129 seconds
- d. 400 seconds
Category A: Reactor Theory, Thermodynamics, and Facility Operating Characteristics QUESTION A.15 [1.0 point]
If a source strength is 5000 neutrons per second (N/sec) and it produces the stable neutron count rate of 20000 N/sec. What is a multiplication factor?
- a. 0.70
- b. 0.75
- c. 0.85
- d. 0.90 QUESTION A.16 [1.0 point]
The reactor is on a constant period. Which ONE of the following changes in reactor power would take the SHORTEST time?
- a. 5% from 1% to 6%
- b. 15% from 20% to 35%
- c. 20% from 40% to 60%
- d. 25% from 75% to 100%
QUESTION A.17 [1.0 point, 0.25 each]
The most important fission product poison is Xe-135. The diagram below shows production and removal paths of Xe-135 Match the items in the letter with the appropriate isotopes listed :Te-135, Ba-135, Cs-135, I-135.
QUESTION A.18 [1.0 point]
What is the kinetic energy range of a thermal neutron?
- a. > 1 MeV
- b. 100 KeV - 1 MeV
- c. 1 eV - 100 KeV
- d. < 1 eV
Category A: Reactor Theory, Thermodynamics, and Facility Operating Characteristics QUESTION A.19 [1.0 point]
A reactor is subcritical with k- effective of 0.9. If a reactor operator makes a mistake by removing the control blade worth of 0.01 k/k out of the reactor core. Which ONE of the following best describes the reactor kinetic if removing the control blade?
- a. Critical, Keff = 1 and = 0
- b. Super critical, Keff =1 and < -eff
- c. Prompt critical, Keff > 1 and > -eff
- d. Subcritical, Keff < 1 and > -eff QUESTION A.20 [1.0 point]
Which ONE of the following describes the term PROMPT JUMP?
- a. A reactor is subcritical at negative 80-second period
- b. A reactor has attained criticality on prompt neutrons alone
- c. The instantaneous change in power level due to inserting a control blade
- d. The instantaneous change in power level due to withdrawing a control blade
(***** END OF CATEGORY A *****)
Category B - Normal/Emergency Operating Procedures and Radiological Controls QUESTION B.01 [1.0 point, 0.25 each]
Identify the PRIMARY source (irradiation of air, irradiation of water, irradiate of reactor structure, or fission product) of EACH of the following radioisotopes.
- a. Co-60
- b. Ar-41
- c. H-3
- d. I-131 QUESTION B.02 [1.0 point]
A radioactive source currently has an activity of 5 Curies. The half-life of the radioactive source is 5 years. What is the activity of the source 25 years ago?
- a. 15 Curies
- b. 25 Curies
- c. 125 Curies
- d. 160 Curies QUESTION B.03 [1.0 point]
Which parts in 10CFR states that each applicant for a license authorizing operation of a production or utilization facility shall include in his application proposed technical specifications.
- a. 10CFR20
- b. 10CFR50
- c. 10CFR55
- d. 10CFR74
Category B - Normal/Emergency Operating Procedures and Radiological Controls QUESTION B.04 [1.0 point]
A two-curie source, emitted 80% of 3 Mev gamma, is to be stored in the reactor building. What is a dose rate at 5 ft?
- a. 0.96 R/hr
- b. 1.15 R/hr
- c. 14.4 R/hr
- d. 144 R/hr QUESTION B.05 [1.0 point]
Which ONE of the following is acceptable pH levels for pumping a waste tank to the sanitary sewer?
- a. 3.2 - 4.5
- b. 4.6 - 5.9
- c. 6.2 - 8.3
- d. 8.4 -10.1 QUESTION B. 06 [1.0 point, 0.25 each]
Match the following events in accordance with MURR Emergency Plan Classification
[Notification of Unusual Event (NUE), Alert (A), Site Area Emergency (SAE)]
- a. Tornado directed toward the reactor facility.
- b. A terrorist triggered a bomb directed to the reactor core, causing multiple fuel damage and releasing significant fission products to the environment.
- c. Significant fuel damage indicated by high coolant fission product activity.
- d. Release significant radioactive materials to containment during a fuel handling accident outside the core.
Category B - Normal/Emergency Operating Procedures and Radiological Controls QUESTION B.07 [1.0 point]
During a stuck control blade, the licensed operators need to remove a control rod offset mechanism from its installed position. Which ONE of the following permissions must be met to remove the control rod?
- a. Get an authorization from any Senior Reactor Operator.
- b. Get an authorization from the Lead Senior Reactor Operator.
- c. Get an authorization from the Reactor Manager.
- d. This is a Technical Specification violation. The licensee shall NOT remove the control rod until getting a permission from NRC.
QUESTION B.08 [1.0 point]
A Radiation Work Permits (RWP) will be completed as determined by the __________ , AND for any non-routine work that could results in _____________.
- a. SRO / Radiation exposure rate of greater 100 mR/hr.
- b. SRO / Produce unusual surface contamination.
- c. LSRO / Potential to release radioactive airborne contamination.
- d. LSRO / Radiation Exposure dose of 100 mRem per day to the licensed operator.
QUESTION B.09 [1.0 point]
Which ONE of the following Reactor Emergencies would require you to insert a Manual Rod Run-in as an immediate action to reduce power to an acceptable level?
- a. High radiation levels
- b. Nuclear instrumentation failure
- c. Single phasing or low line voltage
- d. Failure of experimental apparatus
Category B - Normal/Emergency Operating Procedures and Radiological Controls QUESTION B.10 [1.0 point]
Per MURR Technical Specification, the pH of the water in the primary coolant system shall be maintained between _________ when averaged over a period of one quarter.
- a. 3.0 and 5.0
- b. 5.0 and 7.0
- c. 7.0 and 9.0
- d. 9.0 and 11.0 QUESTION B.11 [1.0 point]
Per MURR Technical Specification, all fuel elements or fueled devices outside the reactor core shall be stored in a geometrical array such that the calculated Keff is less than ________ under all conditions of moderation.
- a. 0.75
- b. 0.80
- c. 0.85
- d. 0.90 QUESTION B.12 [1.0 point]
Per MURR Technical Specifications, the absolute value of the reactivity worth of each secured removable experiment shall be limited to _________.
- a. 0.3 %k/k
- b. 0.6 %k/k
- c. 0.006 %k/k
- d. 0.003 %k/k
Category B - Normal/Emergency Operating Procedures and Radiological Controls QUESTION B.13 [1.0 point]
To access an area posted as a Radiation Area, all of the following are true for visitors EXCEPT:
- a. Complete all applicable information in the visitor log book and sign it.
- b. Received prior approval and applicable dosimetry from Reactor Health Physics.
- c. Be provided with an estimate of the dose received during the current calendar year.
- d. Be continually escorted by a person having unescorted access to the Radiation Area.
QUESTION B.14 [1.0 point]
Area for which emergency planning is performed and bounded by a 150-meter radius from the MURR exhaust stack and lies within the site boundary is defined as __________.
- a. Emergency Planning Zone
- b. Site Boundary
- c. Operations Boundary
- d. Emergency Control Center QUESTION B.15 [1.0 point]
Per MURR OP-RO-210, the fastest reactor period which may be used to raise power from 1 MW to 10 MW is:
- a. 10 seconds
- b. 30 seconds
- c. 50 seconds
- d. 100 seconds
Category B - Normal/Emergency Operating Procedures and Radiological Controls QUESTION B.16 [1.0 point]
Which ONE of the following is NOT considered an abnormal occurrence?
- a. During the reactor operation, a student inserted an experiment that causes a short period scram.
- b. During the reactor operation, the operator noted the pool water level indicates 29 feet.
- c. During the reactor operation, the operator couldnt withdraw the regulating rod from 6-in position.
- d. During the reactor training, a student lets the power drift up to the 120 % of full power, whereupon a rod run-in occurs.
QUESTION B.17 [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 mrem/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.18 [2.0 points, 0.5 each]
Match the annual dose limit values to the type of exposure. Answer in Column B can be used more than once, or not at all.
Type of Exposure Annual Dose Limit Value
- a. Extremities 1. 0.1 rem
- b. Lens of the Eye 2. 0.5 rem
- 5. 50.0 rem
Category B - Normal/Emergency Operating Procedures and Radiological Controls QUESTION B.19 [1.0 point]
To prevent damage to the reactor or excessive release of radioactive materials in the event of an experiment failure, experiments containing corrosive materials shall:
- a. be doubly encapsulated.
- b. be limited to less than 25 milligrams.
- c. not be inserted into the reactor or stored at the facility.
(***** End of Category B *****)
Category C - Facility and Radiation Monitoring Systems QUESTION C.01 [1.0 point]
Which ONE of the following electrical loads CANNOT be supplied by the Emergency Generator?
- a. Airlock doors
- b. Exhaust Fan EF-13
- c. Exhaust Fan EF-14
- d. Pool Pump P508A QUESTION C.02 [1.0 point]
What is the minimum time required for the primary cooling system be operated after the reactor shutdown from full power?
- a. 5 minutes
- b. 10 minutes
- c. 15 minutes
- d. 30 minutes QUESTION C.03 [1.0 point]
The waste water from Waste Tank # 3 is gravity drain to Waste Tank # 2 through a _________.
- a. Orifice
- b. Heat exchanger
- c. Set of filters
- d. Demineralizer
Category C - Facility and Radiation Monitoring Systems QUESTION C.04 [1.0 point]
The Vent Tank System is connected to the primary coolant loop, at the highest points of the inverted loop and the in-pool heat exchanger through a _________.
- a. Half inch lines
- b. Plastic lines
- c. Filter
- d. Gate valve QUESTION C.05 [1.0 point]
Which one is true for the pool outlet isolation vale (V509) in the Pool Coolant System?
- a. Air to open, spring to close
- b. Air to close, spring to open
- c. Stainless steel, air to close
- d. Stainless steel, spring to open QUESTION C.06 [1.0 point]
High Voltage Panel # 3 (HVP-3) is provides power to:
- a. Distribution Center-1 only.
- b. Distribution Center-2 only.
- c. Distribution Center-1 and Distribution Center-3.
- d. Distribution Center-1 and Distribution Center-2.
QUESTION C.07 [1.0 point]
The Off-Gas Radiation Monitoring System continuously monitors the air exiting the facility:
- a. For airborne radioactivity levels.
- b. Through a set of general air filters.
- c. To purify the air in the control room.
- d. To monitoring from a fixed contaminated.
Category C - Facility and Radiation Monitoring Systems QUESTION C.08 [1.0 point]
For the reactor containment integrity to exist, one of the following conditions shall be satisfied:
- a. The truck entry door is open.
- b. The personnel airlock is operable (one door shut and sealed).
- c. The reactor containment building pressure is at positive pressure.
- d. The reactor containment building ventilation doors placed in open position.
QUESTION C.09 [1.0 point]
Where does the Drain Collection tank overflow line discharges to?
- a. Reactor Pool.
- b. Sanitary Sewer.
- c. Retention Tank #3.
- d. Room 114 pipe tunnel floor.
QUESTION C.10 [1.0 point]
To prevent the spread of radioactive contamination such as airborne radioactive materials, the ventilation system maintains the reactor containment and laboratory buildings at:
- a. Slightly positive pressure.
- b. Five pounds positive pressure.
- c. Same as an outside pressure.
- d. Slightly negative pressure.
Category C - Facility and Radiation Monitoring Systems QUESTION C.11 [1.0 point]
Which ONE of the following systems provides a majority of heat removal from in-pool components such as control blade gaps, the center test hole and the reflector region?
- a. Pool Coolant System.
- b. Primary Coolant System.
- c. Secondary Coolant System.
- d. Reactor Coolant Clean Up System.
QUESTION C.12 [1.0 point]
Which of the following conditions will result in an automatic rod run-in?
- a. Low Pressurizer Pressure.
- b. Thermal Column Door Open.
- c. Channel 4, 5, and 6 High Power.
- d. Anti-Siphon System Pressure High.
QUESTION C.13 [1.0 point]
WHICH ONE of the following detectors is used primarily to measure N16 release to the environment?
- a. Stack Gas Monitor
- b. Stack Particulate Monitor
- c. Bridge Area Monitor Stack Gas Monitor
- d. NONE, N16 has too short a half-life to require environmental monitoring
Category C - Facility and Radiation Monitoring Systems QUESTION C.14 [1.0 point]
Each reactor fuel element shall contain 24 fuel-bearing plates with a nominal active length of 24 inches and a nominal plate thickness of?
- a. 0.025 inch.
- b. 0.050 inch.
- c. 0.075 inch.
- d. 0.100 inch.
QUESTION C.15 [1.0 point]
The primary coolant system fuel element failure monitor shall be _________ on a semiannual basis.
- a. Channel-Checked
- b. Channel-Calibrated
- c. Channel-Replaced
- d. Channel-Tested QUESTION C.16 [1.0 point]
The requirements of 10 CFR 20.1502(b) are met by regular monitoring for airborne radionuclides and bioassay of exposed personnel. The primary air effluent from MURR is:
- a. 41 Ar
- b. 3 H
- c. 23 Na
- d. 131 I
Category C - Facility and Radiation Monitoring Systems QUESTION C.17 [1.0 point]
Radiation protection instrumentation used at the MURR is periodically calibrated according to:
- a. Written procedures.
- b. Manufacture manual.
- c. Electronic maintenance procedure.
- d. 10 CFR 20 requirements.
QUESTION C.18 [1.0 point]
What should you do, when a high radiation level condition is detected by the Air Plenum 1 and Air Plenum 2 channels?
- a. Nothing, keep working
- b. Notify the Control Room Director only
- c. Notify the Health Physic department only
- d. Verify the containment building isolation QUESTION C.19 [1.0 point]
Pressurizer Relief Valve (V537) will relieve pressure directly from the pressurizer to the facility exhaust system at the minimum of?
- a. 25 psig
- b. 50 psig
- c. 100 psig
- d. 250 psig
Category C - Facility and Radiation Monitoring Systems QUESTION C.20 [1.0 point]
The Automatic Transfer Switch (ATS) houses the sensing and control devices to ensure emergency electrical distribution is powered from:
- a. From the normal source only
- b. From emergency source only
- c. From the temporary battery only
- d. From either the normal or emergency source
(***** END OF CATEGORY C *****)
((***** END OF EXAM *****))
Category A - Reactor Theory, Thermodynamics, & Facility Operating Characteristics A.01 Answer: d
Reference:
- decay (np + -) Fe57 (N-1, Z+1)
Chart of the Nuclides A.02 Answer: d
Reference:
Burn, R., Introduction of Nuclear Reactor Operations, © 1988, Sec 7.3 Differential position is at the midpoint (18.05)
= 0.1%k/k x = 18.2 - 17.9 = 0.3 inche Differential rod worth (/in) = ()/(x)
= 0.1%k/k /0.3 = 0.33%k/k at midpoint (18.05 inches)
A.03 Answer: c
Reference:
from k=-1 0.945 to criticality (k=1), the reactivity required from subcritical to critical is = (1-k)/k = 0.055/(0.945) k/k = 0.582. From criticality to JUST prompt, = eff is needed. Therefore, the minimum reactivity required to produce prompt criticality is 0.0582 k/k +0.0078k/k = 0.066 k/k A.04 Answer: b
Reference:
Glasstone, S. and Sesonske, A, Nuclear Reactor Engineering, 1991, § 5.98.
A.05 Answer: b
Reference:
Reactivity added = $0.25 or $0.25 x0.0078= 0.00195 k/k
= (-)/eff* = 0.0078 - 0.00195 = 30 seconds (0.1) (0.00195)
A.06 Answer: a, INCREASE b, INCREASE c, DECREASE d, INCREASE (0.25 each)
Reference:
DOE Fundamentals Handbook, NPRT, Vol. 2, Module 4, EO 3.6, p.28 A.07 Answer: b
Reference:
Burn, R., Introduction to Nuclear Reactor Operations, © 1988, Section 5.1 A.08 Answer: d
Reference:
Burn, R., Introduction of Nuclear Reactor Operations, © 1988, Sec 3.2 A.09 Answer: a
Reference:
Nuclides and Isotopes Z=1, A=3 , N=2
Category A - Reactor Theory, Thermodynamics, & Facility Operating Characteristics A.10 Answer: c
Reference:
Burn, R., Introduction to Nuclear Reactor Operations, © 1982, Sec 5.5 A.11 Answer: a
Reference:
= keff1-keff2/(keff1 x keff2)
(0.95-0.80) /(0.95*0.80) = 0.197 A.12 Answer: a
Reference:
P = Poet/T 400 kW = 200 kW* e 10 sec/T T = 14.4 sec 1000 kW = 400 kW e (t/14.4) t = 13.2 sec A.13 Answer: d
Reference:
Burn, R., Introduction of Nuclear Reactor Operations, © 1988, Sec 4.2 A.14 Answer: c
Reference:
P/P0 = e-t/ ln(1/5) = - (t)/(-80sec) Time (t) = ln (0.2) x -80 sec = 129 seconds A.15 Answer: b
Reference:
CR = S/(1-K) 20000 = 5000/(1 - X) 1 -X = 5000/20000 X = 0.75 A.16 Answer: d
Reference:
P = P0 e t/ Ln(P/P0) = t/ Since you are looking for which would take the shortest time it is obvious to the most casual of observers that the ratio P/P0 must be the smallest value.
A.17 Answer: a, Te-135 b, I-135 c, Cs-135 d, Ba-135
Reference:
Burn, R., Introduction of Nuclear Reactor Operations, © 1988, Figure 8.1 A.18 Answer: d
Reference:
Burn, R., Introduction to Nuclear Reactor Operations, © 1988, Section 2.5.1
Category A - Reactor Theory, Thermodynamics, & Facility Operating Characteristics A.19 Answer: d
Reference:
From k =0.9 to critical (k=1) the reactivity needed is
= keff1-keff2/(keff1 x keff2)
(1.0-0.90)/(1.0*0.90) = 0.10 k/k By adding a worth of 0.01 k/k (even > -eff ), a reactor is still subcritical because 0.01 k/k << 0.10 k/k.
Burn, R., Introduction of Nuclear Reactor Operations, © 1988, Sec 4.2 A.20 Answer: d
Reference:
Burn, R., Introduction to Nuclear Reactor Operations, © 1982, Page 4-21.
Category B: Normal/Emergency Operating Procedures and Radiological Controls B.01 Answer: a. = Structure; b. = Air; c. = Water, d. = Fission (0.25 each)
Reference:
MURR Reactor Operations Training Manual, MURR Isotopes of Interest (1-11A)
B.02 Answer: d
Reference:
T A = A*e -t 5Ci = X Ci* e -(t) Note: = ln2/t1/2 = 0.1386 5 Ci = X* exp-(0.1386 *25) solve for X: 160 years B.03 Answer: b
Reference:
10 CFR 50.36 B.04 Answer: b
Reference:
6CEN = R/hr @ 1 ft. -> 6 x 2 x 0.8 x 3 = 28.8 R/hr at 1ft.
At 5 ft, a dose rate is 28.8 R/hr/25 = 1.15 R/hr B.05 Answer: c
Reference:
MURR OP-RO-741, Waste Tank System Operation, Section 3.1 B.06 Answer: a, NUE b, SAE c, A d, A (0.25 each)
Reference:
MURR EP 3.2, 3.3, and 3.4 B.07 Answer: c
Reference:
MURR AP-RO-110, Conduct of Operations B.08 Answer: c
Reference:
MURR AP-RO-110, Conduct of Operations, Section 6.12 B.09 Answer: d
Reference:
MURR REP-RO-100 Emergency Procedure, REP 12 B.10 Answer: b
Reference:
Reference:
Category B: Normal/Emergency Operating Procedures and Radiological Controls B.12 Answer: b
Reference:
Reference:
MURR AP-HP-123 B.14 Answer: a
Reference:
Reference:
MURR OP-RO-210, Section 3.7 B.16 Answer: b
Reference:
MURR TS 1.1 and 3.2 B.17 Answer: b
Reference:
10CFR20.1201(a)(1) [5000 mr x 1 hr x day = 6.25 days 100 mr
- 8 hr B.18 Answer: a = 5; b = 4; c = 3; d = 1 (0.5 each)
Reference:
10 CFR 20 §§ 1201.a(2)(ii), 1201.a(1), 1201.a(2)(i), 1301 B.19 Answer: a
Reference:
Category C: Facility and Radiation Monitoring Systems C.01 Answer: d
Reference:
MURR Operations Training Manual, Emergency Electrical Distribution,Section II, System Description/Operation, 4th and 6th paragraphs, Page 2-2B.
C.02 Answer: c
Reference:
MURR OP-RO-410, Primary Coolant System, Section 6.1, Page 9.
C.03 Answer: c
Reference:
MURR Operations Training Manual, Liquid Waste Retention System,Section II, Page 2-1C.
C.04 Answer: a
Reference:
MURR Operations Training Manual, Primary Coolant System,Section II, Page 2-4A.
C.05 Answer: a
Reference:
MURR Operations Training Manual, Pool Coolant System,Section III.A, Page 2-5A.
C.06 Answer: d
Reference:
MURR Operations Training Manual, Normal Electrical Distribution,Section II, Page 2-2A.
C.07 Answer: a
Reference:
MURR Operations Training Manual, Stack Monitor, Section IA, Page 1-9F.
C.08 Answer: b
Reference:
MURR TS 3.4, Reactor Containment Building, Section 3.4.a, Page A-24.
C.09 Answer: d
Reference:
MURR Operation Training Manual, Drain Collection System,Section III.B, Page 3-7B.
C.10 Answer: d
Reference:
MURR SAR, Chapter 11, Radiation Protection Program and Waste Management, Section 11.1.5.2, Page 11-50.
C.11 Answer: a
Reference:
MURR Operations Training Manual, Pool Coolant System,Section I.A, Page 1-5A.
Category C: Facility and Radiation Monitoring Systems C.12 Answer: c
Reference:
MURR SAR, Chapter 7, Instrumentation and Control System, Table 7-6, Rod Run-Ins, Page 7-32.
C.13 Answer: d
Reference:
Standard NRC question.
C.14 Answer: b
Reference:
MURR TS 5.3 Reactor Core and Fuel, Section 5.3.e, Page A-58.
C.15 Answer: b
Reference:
MURR TS 4.3, Reactor Coolant System, Section 4.3.b, Page A-45.
C.16 Answer: a
Reference:
MURR TS 3.7, Radiation Monitoring Systems and Airborne Effluents, Section 3.7.b, page A-31.
C.17 Answer: a
Reference:
MURR SAR, Instrumentation Calibration, Section 11.1.4.3, Page 11-28.
C.18 Answer: d
Reference:
MURR Operations Training Manual, Area Radiation Monitor System,Section III.C, Page 4-9B.
C.19 Answer: c
Reference:
MURR Operations Training Manual, Pressurizer System,Section III.C, Page 4-4E.
C.20 Answer: d
Reference:
MURR Operations Training Manual, Automatic Transfer Switch,Section II, Page 2-2B.