ML23311A072
| ML23311A072 | |
| Person / Time | |
|---|---|
| Site: | University of Missouri-Rolla |
| Issue date: | 12/12/2023 |
| From: | Travis Tate NRC/NRR/DANU/UNPO |
| To: | Graham J Missouri Univ of Science & Technology |
| References | |
| 50-123/24-01 50-123/OL-24 | |
| Download: ML23311A072 (37) | |
Text
Dr. Joseph Graham, Reactor Director Nuclear Reactor Facility Missouri University of Science and Technology 231 Fulton Hall Rolla, MO 65409-0630
SUBJECT:
EXAMINATION REPORT NO. 50-123/OL-24-01, MISSOURI UNIVERSITY OF SCIENCE AND TECHNOLOGY
Dear Dr. Graham:
During the week of November 13, 2023, the U.S. Nuclear Regulatory Commission (NRC) administered an operator licensing examination at your Missouri University of Science and Technology 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 at Dan.Hoang@nrc.gov.
Sincerely, 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. 50-123
Enclosures:
- 1. Examination Report No. 50-123/OL-24-01
- 2. Written examination cc: w/enclosures to GovDelivery Subscribers December 12, 2023 Signed by Tate, Travis on 12/12/23
ML23111A072 NRR-079 OFFICE NRR/DANU/UNPO/CE NRR/DANU/UNPO/OLA NRR/DANU/UNPO/BC NAME DHoang NJones TTate DATE 11/30/2023 12/12/2023 12/12/2023 U.S. NUCLEAR REGULATORY COMMISSION OPERATOR LICENSING INITIAL EXAMINATION REPORT REPORT NO.:
50-123/OL-24-01 FACILITY DOCKET NO.:
50-123 FACILITY LICENSE NO.:
R-79 FACILITY:
POOL EXAMINATION DATES:
November 13 - November 17, 2023 SUBMITTED BY
____Danvhoang____________
_11/28/2023__
Dan V. Hoang, Chief Examiner Date
SUMMARY
During the weeks of November 13, 2023, the NRC administered operator licensing examinations to five Reactor Operators (ROs) and two Senior Reactor Operators candidates.
One RO applicant failed the written examination. All applicants passed the operating test.
REPORT DETAILS 1.
Examiner:
Dan V. Hoang, Chief Examiner, NRC 2.
Results:
RO PASS/FAIL SRO PASS/FAIL TOTAL PASS/FAIL Written 4/1 Waiver 4/1 Operating Tests 5/0 2/0 7/0 Overall 4/1 2/0 6/1 3.
Exit Meeting:
Ethan Taber, Reactor Supervisor, MS&T Dan Hoang, Chief Examiner, NRC 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.
U.S. NUCLEAR REGULATORY COMMISSION NON-POWER REACTOR LICENSE EXAMINATION FACILITY:
Missouri University of Science and Technology REACTOR TYPE:
POOL.
DATE ADMINISTERED:
11/13/2023.
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, and Facility Operating Characteristics A N S W E R S H E E T 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 ___ (0.25 each)
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 *****)
Category B: Normal/Emergency Procedures and Radiological Controls A N S W E R S H E E T 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 *****)
Category C: Facility and Radiation Monitoring Systems A N S W E R S H E E T 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 ___ (0.25 each)
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
=
=
+
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 1ft = 30.48 cm
2 2
max
P 1
sec 1.0
eff
2 1
1 1
2 1
eff eff K
CR K
CR
eff SUR 06 26
te P
P 0
sec 10 1
4
eff K
S S
1
2 2
1 1
CR CR
0 1
P P
)
(
0 10 t
SUR P
P 1
2 1
1 CR CR K
M eff
2 1
1 1
eff eff K
K M
eff eff K
K SDM
1
693
.0 2
1 T
2 1
1 2
eff eff eff eff K
K K
K
eff eff K
K 1
2 2
2 2
1 1
d DR d
DR
t e
DR DR
0
1 2
1 2
2 2
Peak Peak
2 6
R n
E Ci DR
Missouri University of Science and Technology Operator Licensing Examination Week of November 13, 2023
Category A: Reactor Theory, Thermodynamics, and Facility Operating Characteristics QUESTION A.01
[1.0 point]
During Reg Rod calibration, doubling time was recorded to be 78 seconds. What was reactor period?
- a. 39 seconds
- b. 54 seconds c.
113 seconds
- d. 156 seconds QUESTION A.02
[1.0 point]
While a reactor is at 5 W, the reactor operator is withdrawing a control rod to insert a positive reactivity of 0.00156 (K/K). Which ONE of the following will be the stable reactor period as a result of this withdrawal? Given beta-effective= 0.0073 and eff = 0.1.
- a. 17 seconds
- b. 27 seconds c.
37 seconds
- d. 47 seconds QUESTION A.03
[1.0 point]
What is the meaning of any point on a differential rod worth curve?
- a. The negative reactivity added as the rod is inserted.
- b. The cumulative area under the differential curve starting from the bottom of the core.
- c. The amount of reactivity that one inch of rod motion would insert at that position in the core.
- d. The zero reactivity when the rod is on the bottom and the positive reactivity being added as the rod is withdrawn.
Category A: Reactor Theory, Thermodynamics, and Facility Operating Characteristics QUESTION A.04
[1.0 point]
Which ONE of the following changes does NOT require a movement of control rods in order to maintain constant reactor power?
- a. Pool water temperature decrease.
- b. U-235 burnup.
- c. Xe-135 buildup.
- d. N-16 formation.
QUESTION A.05
[1.0 point]
The effective multiplication factor (Keff) can be determined by dividing the number of neutrons produced from fission in the fourth generation by the number of neutrons produced from fission in the _________ generation.
- a. First
- b. Second
- c. Third
- d. Fifth QUESTION A.06
[1.0 point]
Most textbooks list for a U235 fueled reactor as 0.0065 K/K and eff as being 0.0075 K/K.
What is a main reason that eff is larger than ?
a.
The fuel includes U238 which has a relatively large for fast fission.
b.
Some U238 in the core becomes Pu239 (by neutron absorption) which has a larger for fission.
c.
Delayed neutrons are born at higher energies than prompt neutrons resulting in a greater worth for these neutrons.
- d. Delayed neutrons are born at lower energies than prompt neutrons resulting in a less loss due to leakage for these neutrons.
Category A: Reactor Theory, Thermodynamics, and Facility Operating Characteristics QUESTION A.07
[1.0 point, 0.25 each]
Match the items in Column A with the isotopes in Column B.
The most important fission product poison is 135Xe. The process that shows how this isotope is formed and its decay is:
Column A Column B 1.
135 Ba 2.
135 Cs 3.
135 I a
fission 11 0
1 + b fission 6.7 0
1+ 135 fission 9.2 0
1+ c 2.36 d()
4.
135 Te QUESTION A.08
[1.0 point]
INELASTIC scattering is the process by which a neutron collides with a nucleus and:
- a. Is absorbed, with the nucleus emitting a gamma ray.
- b. Recoils with the same kinetic energy it had prior to the collision.
- c. Recoils with a lower kinetic energy than it had prior to the collision, with the nucleus emitting gamma ray.
- d. Recoils with a higher kinetic energy than it had prior to the collision, with the nucleus emitting a gamma ray.
QUESTION A.09
[1.0 point]
Which ONE of the following is a number of neutrons in the Uranium-235 nucleus (92U235)?
- a. 92.
- b. 143.
- c. 235.
- d. The U-235 doesnt have a constant number of neutrons, it fluctuates between 95 and 140.
Category A: Reactor Theory, Thermodynamics, and Facility Operating Characteristics QUESTION A.10
[1.0 point]
Reactor period is defined as ____________.
a.
The time required for a reactor power to double.
- b. The time required for a reactor power to change by a factor of e.
- 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.11
[1.0 point]
Which ONE of the following describes the production of fission neutrons resulting from thermal neutrons being absorbed in the fuel?
- a. Fast Non-Leakage Probability (Lf).
- b. Resonance Escape Probability (p).
- c. Thermal Utilization Factor (f).
- d. Reproduction Factor ().
QUESTION A.12
[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
Category A: Reactor Theory, Thermodynamics, and Facility Operating Characteristics QUESTION A.13
[1.0 point]
Which ONE of the following is the major source of heat generation after an operating reactor has been shut down and cooled down for several days?
- a. Resonance capture.
- b. Fission fragment decay.
- c. Delayed neutron reactions.
- d. Corrosion product activation.
QUESTION A.14
[1.0 point]
Control Rod withdrawal predominantly changes Keff by changing the _________.
- a. Fast fission factor ().
- b. Thermal utilization factor (f).
- c. Neutron reproduction factor ().
- d. Resonance escape probability (p).
QUESTION A.15
[1.0 point]
The reaction 93Np239 _____ + 94Pu239 is an example of:
- a. Alpha Decay
- b. Beta Decay
- c. Gamma Emission
- d. Electron Capture
Category A: Reactor Theory, Thermodynamics, and Facility Operating Characteristics QUESTION A.16
[1.0 point]
What is the effect of delayed neutrons on the neutron flux decay following a scram from full power?
- a. Decreases the mean neutron lifetime.
- b. Adds positive reactivity creating a greater shutdown margin.
- c. The shortest-lived precursors cause power to decrease rapidly as they decay.
- d. Adds positive reactivity due to the fuel temperature decrease following the scram.
QUESTION A.17
[1.0 point]
The product of number density and microscopic cross section of an element is defined as:
- a. Macroscopic Cross Section.
- b. Thermal Cross Section.
- c. Mean Free Path.
- d. Decay Constant.
QUESTION A.18
[1.0 point]
The longest-lived Delay Neutron Precursor group has a half-life of seconds.
a.
0.026 b.
0.10
- c. 55
- d. 80
Category A: Reactor Theory, Thermodynamics, and Facility Operating Characteristics QUESTION A.19
[1.0 point]
During a fuel loading of the core, as the reactor approaches criticality, the value of 1/M:
- a. Increases toward one.
- b. Decreases toward one.
- c. Increases toward infinity.
- d. Decreases toward zero.
QUESTION A.20
[1.0 point]
The reactor is critical and increasing in power. Power has increased from 10 watts to 40 watts in 20 seconds. How long will it take at this rate for power to increase from 40 watts to 10 kW? Note:
neglect the negative temperature coefficient.
- a. 14 seconds
- b. 46 seconds
- c. 56 seconds
- d. 80 seconds
- End of Category A *****************
Category B: Normal and Emergency Operating Procedures and Radiological Controls QUESTION B.01
[1.0 point]
The operator licensing candidate requires submitting the NRC Form 396, Certification of Medical Examination by Facility Licensee, to the NRC Chief Examiner before start date of the examination. This requirement can be found in:
a.
10 CFR Part 73 QUESTION B.02
[1.0 point]
In an emergency in order to protect the public health and safety, 10 CFR 50.54 allows the operator to depart from a license condition or a technical specification. What is the MINIMUM level of authorization needed to deviate from this action?
- a. Reactor Director.
- b. Radiation Safety Officer.
- c. Licensed Senior Reactor Operator.
- d. Licensed Reactor Operator.
QUESTION B.03
[1.0 point]
The exposure rate for a point source is 100 mR/hr at a distance of 4 m. What is the exposure rate at a distance of 2 m?
- a. 200 mR/hr.
- b. 400 mR/hr.
- c. 600 mR/hr.
- d. 800 mR/hr.
Category B: Normal and Emergency Operating Procedures and Radiological Controls QUESTION B.04
[1.0 point]
One of the principal objectives of the Emergency plan is to establish the safety of reactor personnel and all persons within the __________ boundary.
a.
Site b.
Exclusion c.
Operations d.
MST campus QUESTION B.05
[1.0 point]
15 rem (0.15 Sv) is the Annual Dose Limit for occupationally exposed adults for:
a.
Elbows to hands.
- b. Eyes.
- c. Knees to feet.
d.
Skin.
QUESTION B.06
[1.0 point]
The MSTR excess reactivity limit and shutdown margin limit may be temporarily exceeded following a core configuration change under which ONE the following conditions.
a.
The reactor power is limited to 5 kW.
b.
The regulating rod shall be worth no more than 0.7% k/k in reactivity.
c.
Reactor operations are limited to the measurement of excess reactivity, control rod worths, and shutdown margin.
d.
The reactor shall be operated only when all lattice positions internal to the active fuel boundary are occupied by a fuel element, a control rod fuel element, or an experimental facility.
Category B: Normal and Emergency Operating Procedures and Radiological Controls QUESTION B.07
[1.0 point]
Per Emergency Plan, the Emergency Action Levels specified in Table 4.1 Emergency Classes are appropriate to initiate protective actions for members of the general public onsite. The
__________ Guide shall be 1 rem whole body or 5 rem thyroid.
a.
Assessment Action
- b. Corrective Action
- c. Protective Action d.
Recovery Action QUESTION B.08
[1.0 point]
Which ONE of the following is NOT an action specified in the Reactor Operator Evacuation Checklist?
a.
Verify Rod Insertion b.
Secure Magnet Key c.
Announce Facility Status d.
Personnel Accountability QUESTION B.09
[1.0 point]
The reactor thermal power shall be no greater than 300 kW. This is an example of a:
a.
Safety Limit.
- b. Surveillance Requirement.
- c. Limiting Safety System Setting.
d.
Limiting Condition of Operation.
Category B: Normal and Emergency Operating Procedures and Radiological Controls QUESTION B.10
[1.0 point]
Which ONE of the following RECORDS is required by Technical Specifications to be maintain for facility lifetime?
a.
Hourly Log Sheets b.
Staffing Log Sheets c.
As-build drawing of the facility.
d.
Equipment Discrepancy Reports QUESTION B.11
[1.0 point]
Per 10 CFR 20, which ONE of the following is defined as a radiation area?
- a. 5 mrem/hr at 30 cm b.
50 mrem/hr at 1cm c.
120 mrem/hr at 1 m d.
600 rads/hr at 1 m QUESTION B.12
[1.0 point]
Which ONE of the following changes must be submitted to NRC for approval prior to implementation?
a.
Replace a new scram button on the reactor console.
- b. Replace a primary cooling pump with an identical pump.
- c. Add a new requirement in Section B, Section B, Precautions, Prerequisites, or Limitations, in SOP 213.
d.
Change a composition of the Radiation Safety Committee described in MS&T Technical Specification Specifications from at least five members to at least four members.
Category B: Normal and Emergency Operating Procedures and Radiological Controls QUESTION B.13
[1.0 point]
Per Technical Specifications, in the irradiation fuel element, which fuel plate position (s) are left unoccupied?
a.
1 - 9 b.
10 and 17 c.
11 - 16
- d. 18 QUESTION B.14
[1.0 point]
The recovery from emergency conditions will be instituted at the highest organizational level activated during the emergency. However, the recovery and re-entry of affected areas offsite will be performed under the direction of the ___________.
- a. MS&T health physicist b.
MS&T Radiation Safety Officer
- c. Emergency support center manager
- d. Missouri Bureau of Radiological Health QUESTION B.15
[1.0 point]
All the following safety system channels shall automatically scram if exceeding their limits EXCEPT:
- a. Loss of Coolant.
- b. Safety Channel #1.
- c. Manual Scram Button.
- d. The resistivity of the pool water.
Category B: Normal and Emergency Operating Procedures and Radiological Controls QUESTION B.16
[1.0 point]
Which ONE of the following is NOT part of the procedure for Entry into A High Radiation Area?
a.
The doors leading to the High Radiation Area shall be locked.
b.
The RO entering a High Radiation Area is responsible for entering their name and time in and out of the area.
c.
The SRO on Duty or Health Physicist shall be responsible for determining when a High Radiation Area exists.
d.
An announcement will be made to ensure that no one is present in the area to become a High Radiation Area over the building public address system.
QUESTION B.17
[1.0 point]
Which ONE of the following is NOT considered Special Nuclear Material (SNM)?
a.
Control rods b.
Reactor fuel c.
PuBe source d.
Fission Chamber QUESTION B.18
[1.0 point]
Per 10 CFR 20, the sum of the deep-dose equivalent and the committed dose equivalent to any individual organ or tissue other than the lens of eyes being equal to ______.
- a. 5 rem
- b. 15 rem
- c. 50 rem
- d. No limit required
Category B: Normal and Emergency Operating Procedures and Radiological Controls QUESTION B.19
[1.0 point]
Which ONE of the following individuals assumes the role of Emergency Support Center (ESC)
Manager during an emergency?
a.
Reactor Director.
b.
Reactor Manager.
c.
Radiation Safety Officer.
d.
Senior Reactor Operator on duty.
QUESTION B.20
[1.0 point]
Irradiation of explosive materials in quantities greater than 25 milligrams (TNT-equivalent), is permitted to be carried out if it is located at:
- a. Thermal column.
- b. 5 feet above the reactor core.
- c. Near the Safety control rod.
- d. Not allowed at all.
- End of Category B ********************************
Category C: Facility and Radiation Monitoring Systems QUESTION C.01
[1.0 point]
Technical Specifications state that all the following shall be visually checked for proper operation quarterly EXCEPT:
- a. Ventilation Inlet.
- b. Exhaust Duct Louvers.
- c. Radiation Area Monitors.
- d. Personnel Security Door.
QUESTION C.02
[1.0 point]
The neutron-absorbing material in the MS&T control rods contained:
- a. Beryllium b.
Boron c.
Aluminum Oxide
- d. Zirconium Hydride QUESTION C.03
[1.0 point]
The start-up source used in the MS&T is a ____________ neutron source.
- a. Am-Li
- b. Am-Be
- c. Sb-Be
- d. Pu-Be
Category C: Facility and Radiation Monitoring Systems QUESTION C.04
[1.0 point]
Which ONE of the following is the initial position of the SHIM rods that the reactor operator needs to withdraw during a startup to lower power.
- a. 5.5 and 6.0 inches.
- b. 10.5 and 11.0 inches.
- c. 12.5 and 13.0 inches.
- d. 14.5 and 15.0 inches.
QUESTION C.05
[1.0 point]
Why is nitrogen gas used as the transport system in the pneumatic tube rabbit system?
- a. Availability at the facility.
b.
The gases chocking properties.
c.
To reduce Ar-41 activation.
- d. To prevent fire.
QUESTION C.06
[1.0 point]
Which ONE of the following channels has a detector that is attached to a motor driven positioning mechanism?
- a. Start-Up Channel
- b. Linear Channel c.
Log and Linear Channel d.
Safety Channel #1
Category C: Facility and Radiation Monitoring Systems QUESTION C.07
[1.0 point]
Technical Specifications require pool water resistivity to be measured at least __________ during periods when the reactor is operating.
- a. Once a month
- b. Twice a month
- c. Once every week
- d. Once every two weeks QUESTION C.08
[1.0 point]
When the reactor is started up at the usual operating pool water temperature of about 20°C (68°F), what will the bulk temperature in the pool be after about 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> at full power?
a.
57°C (135°F) b.
90°C (194°F) c.
100°C (212°F) d.
103°C (217.4°F)
QUESTION C.09
[1.0 point]
The reactor power range safety channel and period channel shall be____________
annually.
a.
Channel-Checked b.
Channel-Calibrated c.
Channel-Replaced
- d. Channel-Tested
Category C: Facility and Radiation Monitoring Systems QUESTION C.10
[1.0 point]
Which ONE of the following systems is used at MS&T to reduce the N-16 radiation exposure levels?
- a. A diffuser system.
- b. A pool cooling system.
- c. A siphon break system.
- d. A continuous air monitoring system.
QUESTION C.11
[0.25 each]
Match the type of automatic engineered protective actions listed in column A with its corresponding color alarm listed in column B.
Column A Column B
- a. Rod Withdrawal Prohibit (RWP)
- 1. WHITE alarms
- b. Reactor Scram with audio/visual 2
- 2. YELLOW alarms
- c. Informational with audio/visual
- 3. BLUE alarm
- d. Reactor Rundown with audio/visual
- 4. RED alarms QUESTION C.12
[1.0 point]
A ventilation fan with a rated capacity of at least ___________ shall be turned on within 10 minutes after the reactor reaches full power.
- a. 117.4 cubic meters per minute
- b. 127.4 cubic meters per minute
- c. 137.4 cubic meters per minute
- d. 147.4 cubic meters per minute
Category C: Facility and Radiation Monitoring Systems QUESTION C.13
[1.0 point]
Which ONE of the following of functions may be key bypassed at the reactor console by the Senior Operator on Duty as provided for in the Standard Operating Procedures?
- a. Reactor Power 120% Rundown b.
Linear Power Demand 120% Rundown c.
Radiation Area Monitors (RAMs) 20 mrem/hr Rundown
- d. Low Compensating Ion Chamber Voltage 80% Rundown QUESTION C.14
[1.0 point]
Which ONE of the following best describes the proper state of the ventilation system exhaust fans (F) and intake louvers (IL) during a significant airborne release? Open = O, Close = C
- a. F1 = O, F2 = O; F3 = C, IL = C
- b. F1 = C, F2 = C; F3 = O, IL = O c.
F1 = C, F2 = C; F3 = C, IL = C
- d. F1 = C, F2 = C; F3 = C, IL = O QUESTION C.15
[1.0 point]
During a loss of building electrical power, the power supplied to the reactor instrumentation will be:
- a. lost and it will not return until building power returns and the power supplies are manually reset.
- b. lost, but it will be automatically restored when building power returns.
c.
automatically switched to the emergency power generator.
- d. automatically switched to the UPS backup.
Category C: Facility and Radiation Monitoring Systems QUESTION C.16
[1.0 point]
Inadvertent movement of the reactor bridge will result in:
- a. A rod rundown.
- b. An automatic scram.
- c. An evacuation alarm.
- d. Illumination of a status light in the reactor control console only.
QUESTION C.17
[1.0 point]
Experiments worth more than 0.4% k/k shall be all the following EXCEPT:
a.
A secured experiment.
b.
A movable experiment.
c.
Inserted and removed with the reactor shut down.
- d. Inserted and removed from the reactor with a procedure approved by the Radiation Safety Committee.
QUESTION C.18
[1.0 point]
Which ONE of the following equipment can initiate a rod withdraw prohibit, a rundown, and a reactor scram?
- a. CAM.
- b. RAM.
- c. Linear Recorder.
- d. Log & Linear Drawer.
Category C: Facility and Radiation Monitoring Systems QUESTION C.19
[1.0 point]
Before unloading of fuel elements from the reactor core to fuel storage rack, which ONE of the following tasks needs to be performed FIRST?
a.
Calculate the shutdown margin.
b.
Complete a Pre-startup checklist.
c.
Turn off the Constant Air Monitor (CAM).
d.
Withdraw Shim rods 1, 2 and 3 to Shim range.
QUESTION C.20
[1.0 point]
The MAIN reason to have a hole in the top tube end plug of the regulating rod is to:
- a. Reduce the amount of Ar-41 release.
- b. Minimize trapping air in the regulating rod.
- c. Bolt the regulating rod to the drive mechanism.
- d. Allow water to flow through in order to cool the regulating rod.
- End of Category C ****************************
- End of the Exam ***************************
Category A: Reactor Theory, Thermodynamics, and Facility Operating Characteristics A.01 Answer:
c REF:
T = Doubling Time/ln(2) = 78 seconds/0.693 = 112.55 113 seconds A.02 Answer:
c REF:
Reactivity added = 156 pcm = 0.00156 k/k T = (-)/et1p = (0.0073 - 0.00156)/((0.1)*(0.00156)) = 37 seconds A.03 Answer:
c REF:
Burns, Example 7.2 (b), page 7-4.
A.04 Answer:
d REF:
Burns, Problem 7.7.4, page 7-17.
A.05 Answer:
c REF:
Burns, Section 3.3.1, page 3-16.
A.06 Answer:
d REF:
Burns, Section 3.2.4, page. 3-12.
A.07 Answer:
a-4; b-3; c-2; d-1.
REF:
Burns, Figure 8.1, page 8-6.
A.08 Answer:
c REF:
DOE Volume 1, NP-01, page 45.
A.09 Answer:
b REF:
Nuclides and Isotopes N = A - Z, 235-92 = 143.
A.10 Answer:
b REF:
DOE Volume 2, NP-04, page 11.
A.11 Answer:
c REF:
DOE Volume 2, NP-03, page 4.
Category A: Reactor Theory, Thermodynamics, and Facility Operating Characteristics A.12 Answer:
b REF:
CR = S/(1-K) 20000 = 5000/(1 - K) = 1 - K = 5000/20000, or K = 0.75.
A.13 Answer:
b REF:
DOE Fundamentals Handbook, Vol. 2, NP-03, pg. 34.
A.14 Answer:
b REF:
Burn, Section 3.3.2, page 3-18.
A.15 Answer:
b REF:
DOE Fundamentals Handbook, Vol. 1, NP-01, page 24.
A.16 Answer:
c REF:
Burns, Section 4.10.12.(c), pg. 4-33.
A.17 Answer:
a REF:
Burns, Section 2.5.2, page 2-43.
A.18 Answer:
c REF:
Burns, Sec 3.2.2, Table 3.3, page 3-8.
A.19 Answer:
d REF:
Burns, Table 5.5, page 5-15.
A.20 Answer:
d REF:
P = Poet/T 40 = 10 exp(20 sec/T) period (T) = 14.4 sec 10000 watts = 40 watts*exp(time/14.4) time = 79.5 sec
Category B: Normal/Emergency Operating Procedures and Radiological Controls B.01 Answer:
a REF:
10 CFR Part 55.21 B.02 Answer:
c REF:
B.03 Answer:
b REF:
I2=I1D12/d22 = (100 mR/hr)(4m)2 / (2m)2 = 400 mR/hr.
B.04 Answer:
a REF:
MS&T EP 1.4.2, page 1-1.
B.05 Answer:
b REF:
B.06 Answer:
c REF:
MS&T TS 3.1.3.b, page 7.
B.07 Answer:
c REF:
MS&T Emergency Plan, Section 5, page. 5-1.
B.08 Answer:
d REF:
MS&T SOP 501, page 5 of 7 B.09 Answer:
c REF:
MS&T TS Section 2.2, page 6.
B.10 Answer:
c REF:
MS&T TS 6.8.3.3, page 34.
Category B: Normal/Emergency Operating Procedures and Radiological Controls B.11 Answer:
a REF:
10 CFR 20.1003 Definitions 0.005 rem/hr (0.05mSv) in I hour at 30 cm :=> radiation area 0.1 rem (1 mSv) in I hour at 30 cm :=> high radiation area 500 rads/hr (5 grays) in I hour at 1 m :=> Very high radiation area B.12 Answer:
d REF:
10 CFR 50.59 - Any changes in TS required an amendment.
B.13 Answer:
c REF:
MS&T TS Section 5.3.2.4, page 23.
B.14 Answer:
d REF:
MS&T Emergency Plan, Section 9, page 9-1.
B.15 Answer:
d REF:
MS&T TS Section 3.2.2, page 10.
B.16 Answer:
b REF:
MS&T SOP 602, Entry into A High Radiation Area, Section C, page 1 of 2.
B.17 Answer:
a REF:
MS&T SOP 511 Section A, page 1 of 2.
B.18 Answer:
c REF:
B.19 Answer:
d REF:
MS&T EP3.1, page 3-1.
B.20 Answer:
d REF:
MS&T TS Section 3.7.2.2, page 16.
C.01 Answer:
c REF:
MS&T TS Section 4.4, page 20.
C.02 Answer:
b REF:
MS&T SAR Section 4.2.2, page 4-9 and TS 5.3.3, page 23.
C.03 Answer:
d REF:
MS&T SAR Section 4.2.4, page 4-10.
C.04 Answer:
c REF:
MS&T SOP 103, Section C.1.b.i, page 2 of 10.
C.05 Answer:
c REF:
MS&T SAR Section 10.2.3, page 10-4.
C.06 Answer:
a REF:
MS&T SAR Figure 7.1, page 7-4.
C.07 Answer:
d REF:
MS&T SAR Section 5.1, page 5-1.
C.08 Answer:
a REF:
MS&T SAR Section 4.6, page 4-16.
C.09 Answer:
b REF:
MS&T TS Section 4.2.2.2, page 19.
C.10 Answer:
a REF:
MS&T SAR Section 5.3, page 5-5.
C.11 Answer:
a-2; b-4; c-1; d-3.
REF:
MS&T SAR Section 7.2, page 7-1.
C.12 Answer:
b REF:
MS&T TS Section 3.5, page 12.
C.13
Category B: Normal/Emergency Operating Procedures and Radiological Controls Answer:
c REF:
MS&T TS Table 3.1, page 9.
C.14 Answer:
c REF:
MS&T SAR Section 9.1, page 9-1.
C.15 Answer:
a REF:
MS&T SOP 308, Section C, page 1 of 1.
C.16 Answer:
b REF:
MS&T TS Section 3.2.2, Table 3.2, page 10.
C.17 Answer:
b REF:
MS&T TS 3.7.1, page 15.
C.18 Answer:
d REF:
MS&T SAR Table 7.2, page 7-14.
C.19 Answer:
b REF:
MS&T SOP 207, Section B.10, page 2 of 9.
C.20 Answer:
b REF:
MS&T SAR Section 4.2.2, page 4-9.