ML13081A184
| ML13081A184 | |
| Person / Time | |
|---|---|
| Site: | University of Missouri-Rolla |
| Issue date: | 04/01/2013 |
| From: | Gregory Bowman Division of Policy and Rulemaking |
| To: | Frimpong S Missouri Univ of Science & Technology |
| Nguyen J | |
| Shared Package | |
| ML12229A250 | List: |
| References | |
| 50-123/OL-13-01 | |
| Download: ML13081A184 (35) | |
Text
April 1, 2013 Dr. Samuel Frimpong, Chair Mining and Nuclear Engineering 226 McNutt Hall Missouri University of Science and Technology Rolla, MO 65409-0450
SUBJECT:
EXAMINATION REPORT NO. 50-123/OL-13-01, MISSOURI UNIVERSITY OF SCIENCE AND TECHNOLOGY
Dear Dr. Frimpong:
During the week of March 4, 2013, the U.S. Nuclear Regulatory Commission (NRC) administered operator licensing examinations 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 at the conclusion of the examination with those members of your staff identified in the enclosed report.
In accordance with Section 2.390 of Title 10 of the Code of Federal Regulations, a copy of this letter and the enclosures will be available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records component of NRCs Agencywide Documents Access and Management System (ADAMS). ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).
The NRC is forwarding the individual grades to you in a separate letter which will not be released publicly. If you have any questions concerning this examination, please contact Mr.
John T. Nguyen at (301) 415-4007 or via e-mail John.Nguyen@nrc.gov.
Sincerely,
/RA/
Gregory T. Bowman, Chief Research and Test Reactors Oversight Branch Division of Policy and Rulemaking Office of Nuclear Reactor Regulation Docket No. 50-123
Enclosures:
- 1. Examination Report No. 50-123/OL-13-01
- 2. Written examination cc: William E. Bonzer, Reactor Manager Nuclear Reactor Facility Missouri University of Science and Technology 1870 Miner Circle Rolla, MO 65409-0630 cc: w/o enclosures: See next page
Dr. Samuel Frimpong, Chair April 1, 2013 Mining and Nuclear Engineering 226 McNutt Hall Missouri University of Science and Technology Rolla, MO 65409-0450
SUBJECT:
EXAMINATION REPORT NO. 50-123/OL-13-01, MISSOURI UNIVERSITY OF SCIENCE AND TECHNOLOGY
Dear Dr. Frimpong:
During the week of March 4, 2013, the U.S. Nuclear Regulatory Commission (NRC) administered operator licensing examinations 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 at the conclusion of the examination with those members of your staff identified in the enclosed report.
In accordance with Section 2.390 of Title 10 of the Code of Federal Regulations, a copy of this letter and the enclosures will be available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records component of NRCs Agencywide Documents Access and Management System (ADAMS). ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).
The NRC is forwarding the individual grades to you in a separate letter which will not be released publicly. If you have any questions concerning this examination, please contact Mr.
John T. Nguyen at (301) 415-4007 or via e-mail John.Nguyen@nrc.gov.
Sincerely,
/RA/
Gregory T. Bowman, Chief Research and Test Reactors Oversight Branch Division of Policy and Rulemaking Office of Nuclear Reactor Regulation Docket No. 50-123
Enclosures:
- 1. Examination Report No. 50-123/OL-13-01
- 2. Written examination cc: William E. Bonzer, Reactor Manager, Nuclear Reactor Facility Missouri University of Science and Technology 1870 Miner Circle Rolla, MO 65409-0630 cc: w/o enclosures: See next page DISTRIBUTION w/ encls.:
PUBLIC PROB r/f Facility File CRevelle (O07-F8)
ADAMS ACCESSION #: ML13081A184 OFFICE PROB:CE IOLB:LA PROB:BC NAME JNguyen CRevelle GBowman DATE 3/19/2013 3/22/2013 4/01/2013 OFFICIAL RECORD COPY
University of Missouri - Rolla Docket No. 50-123 cc:
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 930 Wildwood Drive, P.O. Box 570 Jefferson City, MO 65102-0570 Deputy Director for Policy Department of Natural Resources 1101 Riverside Drive Fourth Floor East Jefferson City, MO 65101 A-95 Coordinator Division of Planning Office of Administration P.O. Box 809 State Capitol Building Jefferson City, MO 65101 Test, Research, and Training Reactor Newsletter University of Florida 202 Nuclear Sciences Center Gainesville, FL 32611
ENCLOSURE 1 U. S. NUCLEAR REGULATORY COMMISSION OPERATOR LICENSING INITIAL EXAMINATION REPORT REPORT NO.:
50-123/OL-13-01 FACILITY DOCKET NO.:
50-123 FACILITY LICENSE NO.:
R-79 FACILITY:
Missouri University of Science and Technology SUBMITTED BY:
_____________/RA/_________________ 3/19/2013 John T. Nguyen, Chief Examiner Date
SUMMARY
During the week of March 4, 2013, the NRC administered operator licensing examinations to three license candidates including one Reactor Operator (RO), one Senior Reactor Operator -
Upgrade (SRO-U), and one Senior Reactor Operator - Instant (SRO-I) license candidates. All license candidates passed all applicable portions of their examinations.
REPORT DETAILS
- 1.
Examiner: John T. Nguyen, Chief Examiner
- 2.
Results:
RO PASS/FAIL SRO PASS/FAIL TOTAL PASS/FAIL Written 1/0 1/0 2/0 Operating Tests 1/0 2/0 3/0 Overall 1/0 2/0 3/0
- 3.
Exit Meeting:
William Bonzer, MSTR, Reactor Manager Craig Reisner, MSTR, Reactor Training Coordinator John Nguyen, NRC, Chief Examiner Paulette Torres, NRC Examiner in Training The NRC examiners thanked the facility for their support in the administration of the examinations. The facility licensee had no comments on the written examination.
ENCLOSURE 2 U. S. NUCLEAR REGULATORY COMMISSION NON-POWER REACTOR LICENSE EXAMINATION FACILITY:
Missouri University of Science and Technology (Rolla)
REACTOR TYPE:
MTR DATE ADMINISTERED:
3/5/2013 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 18.00 33.3 A. REACTOR THEORY, THERMODYNAMICS AND FACILITY OPERATING CHARACTERISTICS 18.00 33.3 B. NORMAL AND EMERGENCY OPERATING PROCEDURES AND RADIOLOGICAL CONTROLS 18.00 33.3 C. FACILITY AND RADIATION MONITORING SYSTEMS 54.00 % TOTALS FINAL GRADE All work done on this examination is my own. I have neither given nor received aid.
Candidate's Signature
A. RX THEORY, THERMO & FAC OP CHARS 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 ___
A08 a ___ b ___ c ___ d ___ (0.25 each)
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 ___
(***** END OF CATEGORY A *****)
B. NORMAL/EMERG PROCEDURES & RAD CON 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 ___ (0.25 each)
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 ___ (0.25 each)
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 ___ (0.25 each)
B18 a b c d ___
(***** END OF CATEGORY B *****)
C. PLANT AND RAD 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 ___ (0.5 each)
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 ___ (0.25 each)
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 ___
(***** 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 C C Q = m cp T C C Q = m h SCR = S/(1-Keff)
C Q = UA T CR1 (1-Keff)1 = CR2 (1-Keff)2 26.06 (eff)
(1-Keff)0 SUR =
M =
( - )
(1-Keff)1 SUR = 26.06/
M = 1/(1-Keff) = CR1/CR0 P = P0 10SUR(t)
SDM = (1-Keff)/Keff P = P0 e(t/)
I = Io e-ux (1-)
P = Po R* = 1 x 10-4 seconds
= (R*/) + [(-)/eff]
= R*/(-)
= (Keff-1)/Keff R = 6 C E n
Keff/Keff 0.693 T1/2
= 0.007 DR1D1 2 = DR2D2 2
DR = DRoe-t Cp (H20) = 0.146 kw P = S / (1 - Keff) gpm @ EF eff = 0.1/sec 1 Curie = 3.7x1010 dps 1 kg = 2.21 lbm 1 hp = 2.54x103 BTU/hr 1 Mw = 3.41x106 BTU/hr 1 BTU = 778 ft-lbf EF = 9/5EC + 32 931 Mev = 1 amu EC = 5/9 (EF - 32)
Section A: Reactor Theory, Thermo, and Fac. Operating Characteristics QUESTION A.1
[1.0 point]
Two minutes following shutdown, reactor power is at 10 kW and decreases with a constant reactor period. Which ONE of the following is the correct power for three minutes later?
- a.
0.5 kW
- b.
1.1 kW
- c.
3.3 kW
- d.
6.7 kW QUESTION A.2
[1.0 point]
Given the following Core Reactivity Data during startup (not at MSTR):
Control Rod Total Rod Worth
($)
Rod Worth removed at 5 watts critical ($)
Rod excess at 5 watts critical ($)
Rod #1 1.50 1.50 0.00 Rod # 2 1.80 1.50 0.30 Rod # 3 2.20 2.00 0.20 Rod # 4 3.50 2.50 1.00 Total Worth 9.00 7.50 1.50 Assume all rods are scrammable. The SHUTDOWN MARGIN in accordance with the definition of Technical Specifications for this core is:
- a.
$1.5
- b.
$4.0
- c.
$5.5
- d.
$6.0
Section A L Theory, Thermo & Fac. Operating Characteristics QUESTION A.3
[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 % delta K/K is IMMEDIATELY inserted to the reactor core?
- a.
Subcritical
- b.
Critical
- c.
Supercritical
- d.
Prompt critical QUESTION A.4
[1.0 point]
Which ONE of the following correctly describes the SIX-FACTOR FORMULA?
- a.
K4 = Keff
- the reproduction factor ()
- b.
K4 = Keff
- the total non-leakage probability (Lf
- Lth)
- c.
Keff = K4
- the total non-leakage probability (Lf
- Lth)
- d.
Keff = K4 * (the resonance escape probability (p)* the reproduction factor ())
QUESTION A.5
[1.0 point]
Reactor A increases power from 10% to 20% with a period of 25 seconds. Reactor B increases power from 80% to 100% with a period of also 25 seconds. Compared to Reactor A, the time required for the power increase of Reactor B is:
- a.
longer than A
- b.
exactly the same as A
- c.
twice that of A
- d.
shorter than A
Section A L Theory, Thermo & Fac. Operating Characteristics QUESTION A.6
[1.0 point]
Which ONE of the following conditions will INCREASE the core excess of a reactor?
- a.
Increase moderator temperature (Assume negative temperature coefficient)
- b.
Insertion of a negative reactivity worth experiment
- c.
Burnout of a burnable poison
- d.
Fuel depletion QUESTION A.7
[1.0 point]
Delayed neutrons are produced by:
- a.
decay of N-16
- b.
Pair Production process
- c.
decay of fission fragments
- d.
directly from the fission process QUESTION A.8
[1.0 point, 0.25 each]
Fill out the blank with INCREASE or DECREASE due to effects of moderator temperature increase.
- a.
Slowing down length _____________
- b.
Thermal leakage _____________
- c.
Fast leakage _____________
- d.
Core excess _____________
QUESTION A.9
[1.0 point]
Which ONE of the following will be the resulting stable reactor period when a $0.20 reactivity insertion is made into an exactly critical reactor core? Neglect any effects from prompt. Given
=0.0070 and =0.1
- a.
14 seconds
- b.
28 seconds
- c.
32 seconds
- d.
40 seconds
Section A L Theory, Thermo & Fac. Operating Characteristics QUESTION A.10
[1.0 point]
Attached is the applicable portion from the chart of the nuclides, what will Mn-57 decay into?
- a.
Fe-57
- b.
Mn-58
- c.
Cr-57
- d.
V-53 QUESTION A.11 [1.0 point]
Which ONE of the following statements correctly describes thermal neutrons?
- a.
A neutron that experiences a linear decrease in energy as the temperature of the moderator increases
- b.
A neutron that experiences no net change in energy after several collisions with atoms of the moderator on average
- c.
A neutron that experiences an increase in energy levels after collisions with larger atoms of the moderator
- d.
A neutron at resonant epithermal energy levels that causes fissions to occur in U-238
Section A L Theory, Thermo & Fac. Operating Characteristics QUESTION A.12
[1.0 point]
Given the associated graph, which of the following answers best describe the neutron behavior within Region II?
- a.
The neutron cross section is inversely proportional to the neutron velocity (1/V)
- b.
The neutron cross section decreases steadily with increasing neutron energy (1/E)
- c.
Neutrons of specific energy levels (e.g., 50 ev, 100 kev) have more likely leakage from the reactor core
- d.
Neutrons of specific energy levels (e.g., 50 ev, 100 kev) are more likely to be absorbed than neutrons at other energy levels
Section A L Theory, Thermo & Fac. Operating Characteristics QUESTION A.13
[1.0 points]
Two common FISSION PRODUCTS that have especially large neutron capture cross sections and play a significant role in reactor physics. One Sm-149 is and the other is:
- a.
B-10
- b.
Ar-41
- c.
Xe-135
- d.
Cs-137 QUESTION A.14
[1.0 point]
A reactor is operating at 100 KW. The reactor operator withdraws the control rod allowing power to increase. The operator then inserts the same rod to its original position, decreasing power. In comparison to the rod withdrawal, the rod insertion will result in:
- a.
a slower period due to long lived delayed neutron precursors
- b.
a faster period due to long lived delayed neutron precursors
- c.
the same period due to equal amounts of reactivity being added
- d.
the same period due to equal reactivity rates from the rod QUESTION A.15
[1.0 point]
The neutron microscopic cross-section for absorption a generally:
- a.
increases as neutron energy increases
- b.
decreases as target nucleus mass increases
- c.
increases as target nucleus mass increases
- d.
decreases as neutron energy increases QUESTION A.16 [1.0 point]
Which ONE of the following describes the term PROMPT DROP?
- a.
A reactor is critical at POSITIVE 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 rod
- d.
The instantaneous change in power level due to withdrawing a control rod
Section A L Theory, Thermo & Fac. Operating Characteristics QUESTION A.17
[1.0 point]
Which ONE of the following ranges in the Safety rod position provides the HIGHEST worth during operation? Total length of the Safety rod is 24 inches.
- a.
From 4 to 8 inches
- b.
From 10 to 14 inches
- c.
From 14 to 18 inches
- d.
From 18 to 22 inches QUESTION A.18
[1.0 point]
Use Figure 3.3 attached. Calculate the effective delayed neutron fraction (-effective). At birth energies, there are 65 delayed neutrons and 9935 prompt neutrons. In the process of slowing down, there are only 56 delayed neutrons and 7352 prompt neutrons at the thermal range. The resultant -effective of Figure 3.3 is:
- a.
0.00654
- b.
0.00756
- c.
0.00762
- d.
0.00348
(***** END OF CATEGORY A *****)
Section B Normal/Emergency Procedures and Radiological Controls QUESTION B.1
[1.0 points]
The MST Safety Limit is on:
- a.
the reactor pool level, which is 16 ft above core
- b.
the reactor inlet pool temperature, which is 135 °F
- c.
the temperature of fuel cladding, which is 950 °F
- d.
the temperature at the center fuel element, which is 950 °F QUESTION B.2
[1.0 points, 0.25 each]
Match the radiation reading from Column A with its corresponding radiation area classification (per 10 CFR 20) listed in Column B. Answer can be used more than once. Assume a Quality factor of 1.
Column A Column B
- a.
10 mrem/hr at 30 cm
- 1. Unrestricted Area
- b.
550 mrem/hr at 30 cm
- 2. Radiation Area
- c.
10 mrem/hr at 1 m
- d.
550 rem/hr at 1 m
- 4. Very High Radiation Area QUESTION B.3
[1.0 point]
Per MST Technical Specifications, which ONE of the following isotopes is the radioactive airborne effluent which is limited a release from the facility per 10 CFR 20, Appendix B, Table 2?
- a.
- b.
Argon -41
- c.
- d.
Section B Normal/Emergency Procedures and Radiological Controls QUESTION B.4
[1.0 points]
Per MST Technical Specifications, which ONE of the following is the MAXIMUM reactivity worth of the regulating rod?
- a.
0.30 % k/k
- b.
0.70 % k/k
- c.
0.75 % k/k
- d.
1.00% k/k QUESTION B.5
[1.0 point]
The shim/safety rod drop times shall be measured:
- a.
Monthly
- b.
Semiannually
- c.
Annually
- d.
Bianually QUESTION B.6
[1.0 point]
The following measurements are made from a beta-gamma point source:
2 rem/hr at 6 inches 0.5 mrem/hr at 10 feet What is the relative fraction of betas and gammas emitted at 6 inches?
- a.
(1800/200) = 9
- b.
(2000/200) = 10
- c.
(1800/20) = 90
- d.
(2200/200) = 11
Section B Normal/Emergency Procedures and Radiological Controls QUESTION B.7
[1.0 point]
The Quality Factor is used to convert
- a.
an absorbed dose in rads to dose equivalent in rems
- b.
an absorbed 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 QUESTION B.8
[1.0 point]
___________ specifies the limiting conditions for operations of the facility.
- a.
- b.
Physical Security Plan
- c.
Technical Specifications
- d.
Operator Licensing Requalification Plan QUESTION B.9
[1.0 point]
Which ONE of the following is the MINIMUM staffing requirement when the reactor is NOT shutdown?
- a.
1 SRO in the control room and 1 health physics on call
- b.
1 RO on call, 1 RO in the control room, and 1 staff member
- c.
1 SRO on call, 1 RO in the control room, and 1 staff member
- d.
1 SRO on call, 1 reactor manager in the control room, and 1 staff member
Section B Normal/Emergency Procedures and Radiological Controls QUESTION B.10
[1.0 point]
Which ONE of the following materials shall be doubly encapsulated at MSTR?
- a.
A volatile material
- b.
A corrosive material
- c.
An explosive material
- d.
A short half-life material QUESTION B.11
[1.0 point]
Per NRC regulation, the reactor operator must be actively performed for a minimum of _______
to maintain an active Reactor Operator/Senior reactor Operator license.
- a.
4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> per calendar quarter
- b.
8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> per month
- c.
five 8-hour shifts per calendar quarter
- d.
40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> per calendar year QUESTION B.12
[1.0 point, 0.25 each]
Match the license requirement listed in Column A for an actively licensed operator with the correct 10 CFR regulatory requirement listed in Colum B.
Column A Column B
- a.
Facility licenses
- 1.
- 2.
- c.
Radiation protection
- 3.
- d.
Maintain an active operator or senior operator license
- 4.
Section B Normal/Emergency Procedures and Radiological Controls QUESTION B.13
[1.0 point]
Per the Emergency Plan, If an emergency situation requires personnel to search for and remove injured person(s) or entry is necessary to prevent conditions that would probably injure numbers of people, a planned emergency exposure to the whole body could be allowed up to
_____________ to save a life.
- a.
25 rem
- b.
50 rem
- c.
75 rem
- d.
100 rem QUESTION B.14
[1.0 point]
The MSTR reactor operator, who receives the total effective dose equivalent (TEDE) of 5.0 Rems, shall be _____________.
- a.
placed under medical observation
- b.
restricted from any further radiation work
- c.
allowed to continue working until exceeding of 50 rems (TEDE)
- d.
restricted from any further radiation work and placed under medical observation QUESTION B.15
[1.0 point]
Which one of the following does NOT require NRC approval for changes?
- a.
Facility License
- b.
- c.
Requalification plan
- d.
Emergency Implementation Procedures
Section B Normal/Emergency Procedures and Radiological Controls QUESTION B.16
[1.0 point]
Two point sources have the same Curie strength. Source As gammas have an energy of 1 MeV, while Source Bs gammas have an energy of 2 MeV. You obtain a reading from the same GM tube 10 feet from each source. Concerning the two readings, which ONE of the following statements is true?
- a.
The reading from Source B is four times that of Source A
- b.
The reading from Source B is twice that of Source A
- c.
The reading from Source B is the same as Source A
- d.
The reading from Source B is half that of Source A QUESTION B.17
[1.0 point, 0.25 each]
Match the Control Channel in Column A with its respective Rundown Setpoint in Column B.
Column A Column B
- a.
Linear power Demand (%)
- 1. 15
- b.
Reactor period (seconds)
- 2. 20
- c.
Low Compensating Ion Chamber Voltage (%)
- 3. 80
- d.
Demineralizer RAM (mrem/hr)
- 4. 120 QUESTION B.18
[1.0 point]
Per Technical Specifications, a ventilation fan with a rated capacity of at least 127.4 cubic meters per minute (m3/min) shall be turned on within 10 minutes after ___________.
- a.
the reactor is critical
- b.
the reactor is at full power
- c.
the control rods are latched
- d.
the reactor power level exceeds 20 kilowatts
(***** END OF CATEGORY B *****)
Section C Facility and Radiation Monitoring Systems QUESTION C.1
[1.0 point]
Normal evaporation of the MSTR pool is approximately between:
- a.
0.09 - 0.11 inch per day
- b.
0.30 - 0.50 inch per day
- c.
0.60 - 0.80 inch per day
- d.
0.90 - 1.10 inch per day QUESTION C.2
[1.0 point]
Which one of the following conditions will cause a control rod interlock (RWP)?
- a.
Activate the Bridge motion switch
- b.
High Neutron Flux in Beam Room
- c.
Core Inlet Water Temperature exceeds 136 °F
- d.
Linear Recorder exceeds 120 % demand power QUESTION C.3
[2.0 points, 0.5 each]
Match the following actions used in Column A with their respective definitions in Column B:
COLUMN A COLUMN B
- a.
- 1. Channel Check observation of a normal reading
- 2. Channel Test
- b.
Depress the zero check button. Verify the digital display reads 0000 on Linear
- 3. Channel Calibration Channel
- c.
Turn the Log Count Rate selector switch in different power levels. Verify the meter and recorder follow
- d.
Place the Cs-137 source at a distance of 1.6 ft.
Observe the RAM reading in the control room is within 20% of the target dose rate. If not, adjust the RAM setting.
Section C Facility and Radiation Monitoring Systems QUESTION C.4
[1.0 point]
Core inlet temperature is measured by using thermocouple. A thermocouple is
- a.
a precision wound resistor which changes resistance proportional to the change in temperature.
- b.
a bi-metallic junction which changes voltage proportional to the change in temperature.
- c.
a sphere containing a liquid which changes volume with temperature. Expansion and contraction cause an arm in an inductor to move changing inductance proportional to the change in temperature.
- d.
a mercury filled balloon inside an inductor, the expansion and contraction of the mercury causes a variation in the circuit inductance proportional to the change in temperature.
QUESTION C.5
[1.0 point]
Which ONE of the following correctly describes how heat is removed from the core at 100%
power?
- a.
Forced flow due to the diffuser pumps
- b.
Natural convection of the water within the core
- c.
Nucleate boiling of the water within the core
- d.
Forced flow due to flow through the demineralizer system QUESTION C.6
[1.0 point]
One of the rabbit tubes is lined with cadmium to reduce sample activation by
- a.
Fast neutrons
- b.
Thermal neutrons
- c.
Gamma
- d.
Beta
Section C Facility and Radiation Monitoring Systems QUESTION C.7
[1.0 point]
The heat capacity of the reactor pool is sufficient to cool the reactor for ______ before reaching its operation limit of 135 °F. Assumption: Starting bulk temperature = 20 °C and the reactor operating at full power of 200 Kilowatts.
- a.
about 20 minutes
- b.
about 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />
- c.
about a day (24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />)
- d.
about a week (168 hours0.00194 days <br />0.0467 hours <br />2.777778e-4 weeks <br />6.3924e-5 months <br />)
QUESTION C.8
[1.0 point, 0.25 each]
Match each instrument (channel) listed in column A with a specific purpose in column B. Items in column B is to be used only once.
Column A Column B
- a.
Log & Linear Power Channel
- 1.
Provide RWP if count rate is less than 2 cps
- b.
Safety Channel
- 2.
Provide a period Rundown
- c.
Servo Amplifier System
- 3.
Provide a high power level scram
- d.
Start up Channel
- 4.
Permit reactor power to be automatically controlled during steady state operations QUESTION C.9
[1.0 point]
Which ONE of the following is the correct parameter for the Thermal Power Calibration at MSTR? The operator stabilizes the reactor at 40 kW and determines:
- a.
pool level vs. time
- b.
temperature vs. time
- c.
pool level vs. reactivity
- d.
temperature vs. rod height
Section C Facility and Radiation Monitoring Systems QUESTION C.10
[1.0 point]
The MSTR is licensed to receive, possess and use
- a.
up to 10 kg of U-235 enriched to less than 30 % in the form of reactor fuel
- b.
up to 10 kg of U-235 enriched to less than 20 % in the form of reactor fuel
- c.
up to 5.5 kg of U-235 enriched to less than 30 % in the form of reactor fuel
- d.
up to 5.5 kg of U-235 enriched to less than 20 % in the form of reactor fuel QUESTION C.11
[1.0 point, 0.25 each]
Match each monitor listed in column A with a specific purpose in column B. Items in column B is to be used only once.
Column A Column B
- a.
Particulate monitor
- 1.
Monitor radiation level in the reactor bay
- b.
Area radiation monitor
- 2.
Protect the demineralizer resins
- c.
Portable monitor
- 3.
Detect radioisotopes released due to fuel failure
- d.
Core Inlet Temperature
- 4.
Survey of laboratory QUESTION C.12
[1.0 point]
Which ONE of the following is the actual design feature which prevents siphoning of pool water on a failure of the purification system?
- a.
Vacuum breaks are located in the system which prevents draining the pool below about 16 feet above the core
- b.
A valve downstream of the primary pump will shut automatically
- c.
The Emergency Fill system will automatically maintain pool level
- d.
A valve upstream of the primary pump will shut automatically
Section C Facility and Radiation Monitoring Systems QUESTION C.13
[1.0 point]
To reduce radiological activity within the demineralizer tank, the reactor operator needs to:
- a.
encapsulate the corrosive material
- b.
change the resin in the demineralizer tank by quarterly
- c.
turn ON the reactor pools water pump after a high power run is performed
- d.
turn OFF the reactor pools water pump after a high power run is performed QUESTION C.14
[1.0 point]
Which ONE of the following correctly describes the reactor conditions when the power level deviates outside of the +/- 2 % limit in the Automatic Mode?
- a.
Scram; Visual and Audible alarms
- b.
RWP; Visual and Audible alarms
- c.
Revert to Manual; Visual and Audible alarms
- d.
Revert to Manual; Visual alarm ONLY QUESTION C.15
[1.0 point]
During a full power, which ONE of the following is the correct method that helps to mitigate the buildup of Ar41 in the reactor bay?
- a.
Turn Purification system ON to absorb more Ar41 from the pool
- b.
Turn Diffuser pumps ON to reduce the release of Ar41 from the pool
- c.
Operation of the ventilation system, which releases the Ar41 through the stack
- d.
None required due to the relatively short half-life of Ar41 (seven seconds)
QUESTION C.16 [1.0 point]
For a shim-safety rod, the "withdraw limit" light is OFF, the "insert limit" light is ON, and the "contact" light is OFF. Assume that no light bulb failure. This means that:
- a.
Normal condition, rod insertion permissible
- b.
Normal condition, rod withdrawal permissible
- c.
Abnormal condition, misadjusted rod down limit switch
- d.
Abnormal condition, rod has stuck above lower limit
Section C Facility and Radiation Monitoring Systems QUESTION C.17 [1.0 point]
Which ONE of the following experimental facilities will have highest ratio between thermal neutron flux and fast neutron flux (flux in thermal/flux in fast) during full power operation?
- a.
Thermal Column in T mode
- b.
Sample Rotor Assembly
- c.
Core Access Element
- d.
Beam Tube
- END OF CATEGORY C *****)
(***** END OF EXAMINATION *****)
Section A L Theory, Thermo & Fac. Operating Characteristics A.1 Answer:
b
Reference:
P=Poet/ x =10 kW* e180/-80 x = 10 kW *0.105 = 1.05 kW A.2 Answer:
b
Reference:
Tech Spec SDM = 3rod worth removed at critical - most reactivity control rod worth= $7.5 -$3.5 = $4.0 or Tech Spec SDM = total rod worth -(3(rod excesses) + most reactivity control rod worth)= $9.0
-($1.5+$3.5) = $4.0 A.3 Answer:
c
Reference:
Burn, R., Introduction of Nuclear Reactor Operations, © 1988, Sec 4.2 0.5 % delta-K/K =0.005 delta-K/K <0.007, so reactor is supercritical A.4 Answer:
c
Reference:
DOE Handbook Vol 2, L Theory (Nuclear Parameters), E.O. 1.1 a&b, pg. 9 A.5 Answer:
d
Reference:
The power of reactor A increases by a factor of 2, while the power of reactor B increases by a factor of 1.25. Since the periods are the same (rate of change is the same),
power increase B takes a shorter time.
A.6 Answer:
c
Reference:
Burn out a poison, increasing neutron population in the reactor core, increasing the core excess A.7 Answer:
c
Reference:
Burn, R., Introduction of Nuclear Reactor Operations, © 1982, Sec 3.2.1 A.8 Answer:
a, Increase b, Decrease c, Decrease d, Decrease
Reference:
Burn, R., Introduction of Nuclear Reactor Operations, © 1988, Sec 3.3.2 A.9 Answer:
d
Reference:
=$*
=$0.20*0.007 =0.0014 k T = (-)/
T = (0.0070 - 0.0014)/0.1 x 0.0014 = 40 seconds A.10 Answer:
a
Reference:
- decay (np + -) Fe57 (N-1, Z+1)
Chart of the Nuclides
Section A L Theory, Thermo & Fac. Operating Characteristics A.11 Answer:
b
Reference:
NRC Standard Question A.12 Answer d
Reference:
DOE Fundamentals Handbook Nuclear Physics and Reactor Theory Vol. 2 A.13 Answer c
Reference:
Burn, R., Introduction to Nuclear Reactor Operations, © 1988, Sec 8.1 A.14 Answer:
a
Reference:
Burn, R., Introduction of Nuclear Reactor Operations, © 1982, Sec 3.2.2 A.15 Answer:
d
Reference:
Burn, R., Introduction to Nuclear Reactor Operations, © 1982 A.16 Answer:
c
Reference:
Burn, R., Introduction to Nuclear Reactor Operations, © 1982, Page 4-21.
A.17 Answer:
b
Reference:
MSTR Worth Curve (note: center of safety rod provides the highest worth)
A.18 Answer:
b
Reference:
-effective =56/(56+7352) =0.00756 Burn, R., Introduction of Nuclear Reactor Operations, © 1988, Figure 3.3
Section B Normal/Emergency Procedures and Radiological Controls B.1 Answer:
c
Reference:
Technical Specifications, Section 2.1 B.2 Answer:
a(2);
b(3);
c(3);
d(4)
Reference:
10 CFR 20.1003 Definitions equivalent dose: 1 rem= 1 rad x Q (quality factor) 550 rads/hr x QF = 1 550 rem/hr, Very High Radiation Area = 500 rads/hr at 1 m 10 mrem/hr at 1 m = 10 mR/hr at 100 cm = 111 mrem/hr at 30 cm, Definition of High Radiation Area = 100 mrem/hr at 30 cm Radiation Area = 5 mrem/hr at 30 cm B.3 Answer:
b
Reference:
Technical Specifications, Section 3.6.2(1)
B.4 Answer:
b
Reference:
Technical Specifications, Section 3.1, Specification 5 B.5 Answer:
b
Reference:
Technical Specifications, Section 4.2.1 B.6 Answer:
a
Reference:
Standard Health Physics definition Assume beta will not travel 10 feet in air, therefore 0.5 mrem/hr is gamma only and dose at 6 inches (1/2ft) is:
(DR1) (d1
- 2) = (DR2) (d2
- 2)
DR2 = (DR1) (d1
- 2) / d2 2; DR1= 0.5 mrem/hr, d1 2 = (10 ft)2, d2 2 = (0.5 ft)2 DR2 = 0.5 mrem/hr (100 ft2)/ 0.25 ft2 = 200 mrem/hr Therefore, beta contribution at 1/2 ft is 2000 mrem/hr - 200 mrem/hr = 1800 mrem/hr Beta contribution/Gamma contribution = 1800/200 = 9 B.7 Answer:
a
Reference:
10CFR20.1003 and 10CFR20.1004 B.8 Answer:
c
Reference:
10 CFR 50.36 B.9 Answer:
c
Reference:
Technical Specifications, Section 6.1.3 B.10 Answer:
b
Reference:
Technical Specifications, Section 3.7.2
Section B Normal/Emergency Procedures and Radiological Controls B.11 Answer:
a
Reference:
B.12 Answer:
a (2);
b(4);
c(1);
d(3)
Reference:
10 CFR B.13 Answer:
c
Reference:
Emergency Plan, Section 7.4.6 B.14 Answer:
b
Reference:
Emergency Plan, Section 7.4.6 B.15 Answer:
d
Reference:
10 CFR 50.54 (q); 10 CFR 50.59 B.16 Answer:
c
Reference:
Standard Health Physics definition GM tubes cannot distinguish between energies B.17 Answer:
a(4);
b(1);
c(3);
d(2)
Reference:
Technical Specifications, Section 3.2, Table 3.1 and 3.3 B.18 Answer:
b
Reference:
Technical Specifications, Section 3.5
Section C Facility and Radiation Monitoring Systems C.1 Answer:
a
Reference:
SOP 309, Sec B C.2 Answer:
c
Reference:
SAR Table 7.2 C.3 Answer:
- a. = 1;
- b. = 2;
- c. = 2;
- d. = 3
Reference:
TS 1.0 C.4 Answer:
b
Reference:
Information from site visit C.5 Answer:
b
Reference:
SAR 5.1 C.6 Answer:
b
Reference:
SAR 10.2.3 C.7 Answer:
c
Reference:
SAR 4.6 C.8 Answer:
a(2) b(3) c(4) d(1)
Reference:
SAR 7.2.2 C.9 Answer:
a
Reference:
SOP 816 C.10 Answer:
d
Reference:
SAR 9.5 C.11 Answer:
a(3) b(1) c(4) d(2)
Reference:
TS 3.6 C.12 Answer:
a
Reference:
SOP 309 Response to a Coolant System Leak
Section C Facility and Radiation Monitoring Systems C.13 Answer:
d
Reference:
SOP 101, Sec B.5 C.14 Answer:
c
Reference:
SAR 7.2.2.6 C.15 Answer:
c
Reference:
Information during site visit C.16 Answer:
c
Reference:
SAR 7.2.2.6 C.17 Answer:
a
Reference:
SAR 10.2