ML103430495
| ML103430495 | |
| Person / Time | |
|---|---|
| Site: | Rensselaer Polytechnic Institute |
| Issue date: | 12/10/2010 |
| From: | Johnny Eads Research and Test Reactors Branch B |
| To: | Trumbull T Rensselaer Polytechnic Institute |
| Isaac P, NRC/NRR/DPR/PRTB, 301-415-1019 | |
| Shared Package | |
| ML102280258 | List: |
| References | |
| 50-225/11-001 | |
| Download: ML103430495 (30) | |
Text
December 10, 2010 Mr. Timothy Trumbull, Director Reactor Critical Facility Nuclear Engineering and Science Building, 2nd floor Rensselaer Polytechnic Institute Troy, NY 12181
SUBJECT:
INITIAL EXAMINATION REPORT NO. 50-225/OL-11-01, RENSSELAER POLYTECHNIC INSTITUTE
Dear Mr. Trumbull:
During the week of October 18, 2010, the U.S. Nuclear Regulatory Commission (NRC) administered operator licensing examination at your Rensselaer Polytechnic Institute reactor.
The examination was conducted according to NUREG-1478, "Operator Licensing Examiner Standards for Research and Test Reactors," Revision 2, published in June 2007. 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 Title 10, Section 2.390 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 (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 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 Patrick Isaac at 301-415-1019 or via email at patrick.isaac@nrc.gov.
Sincerely,
/RA Thomas Blount for/
Johnny H. Eads, Jr., Chief Research and Test Reactors Oversight Branch Division of Policy and Rulemaking Office of Nuclear Reactor Regulation Docket No. 50-225
Enclosures:
- 1. Examination Report No. 50-225/OL-11-01
- 2. Corrected Written Examination cc: Mr. Jason Thompson, Rensselaer Polytechnic Institute cc w/o enclosures: See next page
Mr. Timothy Trumbull, Director December 10, 2010 Reactor Critical Facility Nuclear Engineering and Science Building, 2nd floor Rensselaer Polytechnic Institute Troy, NY 12181
SUBJECT:
INITIAL EXAMINATION REPORT NO. 50-225/OL-11-01, RENSSELAER POLYTECHNIC INSTITUTE
Dear Mr. Trumbull:
During the week of October 18, 2010, the U.S. Nuclear Regulatory Commission (NRC) administered operator licensing examination at your Rensselaer Polytechnic Institute reactor.
The examination was conducted according to NUREG-1478, "Operator Licensing Examiner Standards for Research and Test Reactors," Revision 2, published in June 2007. 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 Title 10, Section 2.390 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 (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 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 Patrick Isaac at 301-415-1019 or via email at patrick.isaac@nrc.gov.
Sincerely,
/RA Thomas Blount for Johnny H. Eads, Jr., Chief Research and Test Reactors Oversight Branch Division of Policy and Rulemaking Office of Nuclear Reactor Regulation Docket No. 50-225
Enclosures:
- 1. Examination Report No. 50-225/OL-11-01
- 2. Corrected Written Examination cc: Mr. Jason Thompson, Rensselaer Polytechnic Institute cc w/o enclosures: See next page DISTRIBUTION w/ encls.:
PUBLIC PROB r/f JEads Facility File (CRevelle)
ADAMS ACCESSION #: ML103430495 OFFICE PROB:CE IOLB:LA PROB:BC NAME PIsaac CRevelle JEads DATE 12/09/2010 12/10/2010 12/10/2010 OFFICIAL RECORD COPY
Rensselaer Polytechnic Institute Docket No. 50-225 cc:
Mayor of the City of Schenectady Schenectady, NY 12305 Barbara Youngberg Chief, Radiation Section Division of Hazardous Waste and Radiation Management NY State Dept. of Environmental Conservation 625 Broadway Albany, NY 12233-7255 Peter F. Caracappa, Ph.D, CHP Radiation Safety Officer NES Building, Room 1-10, MANE Department Rensselaer Polytechnic Institute 110 8th St.
Troy, NY 12180-3590 Peter Collopy, Director EH&S Rensselaer Polytechnic Institute 21 Union Street Gurley Building 2nd Floor Troy, NY 12180 John P. Spath, State Liaison Officer Designee Program Manager Radioactive Waste Policy and Nuclear Coordination New York State Energy Research & Development Authority 17 Columbia Circle Albany, NY 12203-6399 Test, Research, and Training Reactor Newsletter University of Florida 202 Nuclear Sciences Center Gainesville, FL 32611
ENCLOSURE 1 EXAMINATION REPORT NO:
50-225/OL-11-01 FACILITY:
Rensselaer Polytechnic Institute FACILITY DOCKET NO.:
50-225 FACILITY LICENSE NO.:
CX-22 SUBMITTED BY:
_________/RA/____________
12/09/2010 Patrick J. Isaac, Chief Examiner Date
SUMMARY
During the week of October 18, 2011, the NRC administered operator licensing examinations to two Senior Reactor Operator (SRO) candidates. Both candidate failed the written portion of the examinations.
REPORT DETAILS
- 1.
Examiner: Patrick J. Isaac, Chief Examiner
- 2.
Results:
RO PASS/FAIL SRO PASS/FAIL TOTAL PASS/FAIL Written N/A 0/2 0/2 Operating Tests N/A 2/0 2/0 Overall N/A 0/2 0/2
- 3.
Exit Meeting:
Jason Thompson, Rensselaer Polytechnic Institute Patrick Isaac, NRC, Examiner The NRC Examiner thanked the facility for their support in the administration of the examinations and agreed to make the following changes to the written examination:
Question A.4 -
Accept both answers c and d as correct.
Question A.12 -
Accept both answers a and b as correct Question B.20 -
Accept a as the correct answer
Question C.4 -
Accept both c and d as correct Question C.5 -
Accept b as the correct answer Question C.8 -
Deleted due to the lack of a correct answer
ENCLOSURE 2 U. S. NUCLEAR REGULATORY COMMISSION NON-POWER REACTOR INITIAL LICENSE EXAMINATION FACILITY:
RENNSELAER POLYTECHNIC INSTITUTE REACTOR TYPE:
REACTOR CRITICAL FACILITY DATE ADMINISTERED: 10/19/2010 CANDIDATE:
INSTRUCTIONS TO CANDIDATE:
Answers are to be written on the answer sheet provided. Attach the answer sheets to the examination.
Points for each question are indicated in parentheses for each question. A 70% overall is required to pass the examination. Examinations will be picked up three (3) hours after the examination starts.
CATEGORY VALUE
% OF TOTAL CANDIDATES SCORE
% OF CATEGORY VALUE CATEGORY 20.00 37.0 A. REACTOR THEORY, THERMODYNAMICS, AND FACILITY OPERATING CHARACTISTICS 20.00 37.0 B. NORMAL AND EMERGENCY OPERATING PROCEDURES AND RADIOLOGICAL CONTROLS 14.00 26.0 C. FACILITY AND RADIATION MONITORING SYSTEMS 54.00 FINAL GRADE TOTALS ALL THE WORK DONE ON THIS EXAMINATION IS MY OWN. I HAVE NEITHER GIVEN NOR RECEIVED AID.
CANDIDATE'S SIGNATURE
P a g e l 2 Section A: ReactorTheory, Thermodynamics & 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.
MULTIPLE CHOICE 001 a b c d _
002 a b c d _
003 a b c d _
004 a b c d _
005 a b c d _
006 a b c d _
007 a b c d _
008 a b c d _
009 a b c d _
010 a b c d _
011 a b c d _
012 a b c d _
013 a b c d _
014 a b c d _
015 a b c d _
016 a b c d _
017 a b c d _
018 a b c d _
019 a b c d _
020 a b c d _
(***** END OF CATEGORY A *****)
P a g e l 3 Section B Normal, Emergency and Radiological Control Procedures 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.
MULTIPLE CHOICE 001 a b c d _
002 a b c d _
003 a b c d _
004 a b c d _
005 a b c d _
006 a b c d _
007 a b c d _
008 a b c d _
009 a b c d _
010 a b c d _
011 a b c d _
012 a b c d _
013 a b c d _
014 a b c d _
015 a b c d _
016 a b c d _
017 a b c d _
018 a b c d _
019 a b c d _
020 a b c d _
(***** END OF CATEGORY B *****)
P a g e l 3 Section 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.
MULTIPLE CHOICE 001 a b c d _
002 a b c d _
003 a b c d _
004 a b c d _
005 a b c d _
006 a b c d _
007 a b c d _
008 a b c d _
009 a b c d _
010 a b c d _
011 a b c d _
012 a b c d _
013 a b c d _
014 a b c d _
015 a b c d _
(********** END OF EXAMINATION **********)
P a g e l 3 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 not received or 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.
- 6.
Fill in the date on the cover sheet of the examination (if necessary).
- 7.
Print your name in the upper right-hand corner of the first page of each section of your answer sheets.
- 8.
The point value for each question is indicated in parentheses after the question.
- 9.
Partial credit will NOT be given.
- 10.
If the intent of a question is unclear, ask questions of the examiner only.
- 11.
When you are done and have turned in your examination, leave the examination area as defined by the examiner.
P a g e l 4 EQUATION SHEET DR - Rem/hr, 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
(
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2 1
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=
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K M
=
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M eff
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=
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SUR P
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P P
=
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=
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=
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1 1
2 eff eff eff eff K
K K
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=
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T eff eff K
K 1
=
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DR DR
=
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2 6
R n
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DR
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Section A: Reactor Theory, Thermodynamics, and Fac. Operating CharacteristicsP a g e l 5 QUESTION A.1 [1.0 point]
Which ONE of the following isotopes has the largest microscopic cross-section for absorption for thermal neutrons?
- a. Sm149
- b. U235
- c. Xe135
- d. B10 QUESTION A.2 [1.0 point]
The graph depicted in Figure-1 for U-235 depicts
- a. neutron energy distribution in the moderator
- b. axial flux distribution in the core
- c. radial flux distribution in the core
- d. fission product yield distribution QUESTION A.3 [1.0 point]
Which factors of the six factor formula are affected by a DECREASE in core temperature and how are they affected?
- a. PFNL, PTNL,, f, p
- b., PFNL, PTNL, p,
- c., PFNL, PTNL p, f
- d., PFNL PTNL p,, f
Section A: Reactor Theory, Thermodynamics, and Fac. Operating CharacteristicsP a g e l 6 QUESTION A.4 [1.0 point]
Which of the following core arrangements (I through IV) would most likely be responsible for profile of this 1/M plot during fuel loading?
- a. I
- b. II
- c. III
- d. IV I.
II.
III.
IV.
Section A: Reactor Theory, Thermodynamics, and Fac. Operating CharacteristicsP a g e l 7
=
+
+
6 1
1 i
i i
l
QUESTION A.5 [1.0 point]
Using the Inhour Equation below, which of the following best describes the highlighted (i.e., circled) term?
- a. The time required for the reactor power to change by a factor of e
- b. The fraction of all fission neutrons that are born as delayed neutrons
- c. The fraction of all delayed neutrons which reach thermal energy
- d. The fractional change in neutron population per generation
Section A: Reactor Theory, Thermodynamics, and Fac. Operating CharacteristicsP a g e l 8 QUESTION A.6 [1.0 point]
Using the figure below, which answer provides the best description of neutron behavior within Region II of a light water reactor?
- 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. The neutrons are gaining Kinetic Energy from increased collision events with the hydrogen molecules in the moderator
- d. Neutrons of specific energy levels are more likely to be readily absorbed than neutrons at other energy levels.
QUESTION A.7 [1.0 point]
If eff =0.00765, then what would the reactivity be in k/k if $1.75 were added to a reactor core?
- a. 0.0019 k/k
- b. 0.0134 k/k
- c. 1.0134 k/k
- d. 1.737 k/k
Section A: Reactor Theory, Thermodynamics, and Fac. Operating CharacteristicsP a g e l 9 QUESTION A.8 [1.0 point]
A reactor is critical at 0.1 mW and you are proceeding to raise reactor power. If it is estimated that the doubling time is 30 seconds, what would be reactor power 1 minute later?
- a. 0.2 mW
- b. 0.4 mW
- c. 0.8 mW
- d. 1.6 mW QUESTION A.9 [1.0 point]
The figure depicts a plot of reactor period as a function of time. What best describes the behavior of REACTOR POWER between points A and B:
- a. Constant
- b. Decreasing then increasing
- c. Continually increasing
- d. Continually decreasing
Section A: Reactor Theory, Thermodynamics, and Fac. Operating CharacteristicsP a g e l 10 QUESTION A.10 [1.0 point]
A reactor that has a reactivity of -$2.39 has a count rate of 50 cps on nuclear instrumentation.
Calculate what the neutron level (i.e., count rate) should be after a reactivity insertion of $1.21 from the withdrawal of the control rods. Assume =0.0070
- a. 25 cps
- b. 50 cps
- c. 100 cps
- d. 200 cps QUESTION A.11 [1.0 point]
During the time following a reactor scram, reactor power decreases on an 80 second period, which of the following corresponds to the half-life of the longest-lived delayed neutron precursors?
- a. 80 seconds
- b. 55 seconds
- c. 40 seconds
- d. 20 seconds
Section A: Reactor Theory, Thermodynamics, and Fac. Operating CharacteristicsP a g e l 11 QUESTION A.12 [1.0 point]
The following graph depicts a typical integral rod worth curve for a reactor. If you were to place heaters in the pool and heat the moderator by 5EC, what would be the new rod position after manually adjusting control rods from an initial core position of 60% withdrawn?
Given:
Temperature Coefficient= $0.07 /°C
- a. 46% Withdrawn
- b. 55% Withdrawn
- c. 70% Withdrawn
- d. 86% Withdrawn
Section A: Reactor Theory, Thermodynamics, and Fac. Operating CharacteristicsP a g e l 12 QUESTION A.13 [1.0 point]
Which ONE of the following is a correct statement of why delayed neutrons enhance the ability to control reactor power?
- a. There are more delayed neutrons than prompt neutrons
- b. Delayed neutrons are born at higher energy levels than prompt neutrons
- c. Delayed neutrons increase the average neutron lifetime
- d. Delayed neutrons readily fission in U-238 QUESTION A.14 [1.0 point]
Gold (Au-197) foils are being irradiated in support of the annual power calibration. If a 10g foil was irradiated for 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> where upon removal its activity was 0.90 Ci, what would be the theoretical MAXIMUM activity from the Au-198 foil?
Given: Au-198 (T1/2 = 64.8 hrs)
- a. 0.90 Ci
- b. 1.80 Ci
- c. 4.95 Ci
- d. 7.47 Ci
Section A: Reactor Theory, Thermodynamics, and Fac. Operating CharacteristicsP a g e l 13 QUESTION A.15 [1.0 point]
Using the applicable portion from the chart of the nuclides, what isotope will Mn-56 decay into?
- a. Mn-55
- b. Co-60
- c. Fe-56
- d. Fe-58
Section A: Reactor Theory, Thermodynamics, and Fac. Operating CharacteristicsP a g e l 14 QUESTION A.16 [1.0 point]
What is the condition of the reactor when
= 1 1
?
- a. subcritical
- b. critical
- c. prompt critical
- d. supercritical QUESTION A.17 [1.0 point]
Inelastic scattering can be described as a process whereby a neutron collides with a nucleus and:
- a. recoils with a lower kinetic energy, with the nucleus emitting a gamma ray.
- b. recoils with the same kinetic energy it had prior to the collision.
- c. is absorbed by the nucleus, with the nucleus emitting a gamma ray.
- d. recoils with a higher kinetic energy, with the nucleus absorbing a gamma ray.
QUESTION A.18 [1.0 point]
The following graph shows the profile of reactor power when a negative reactivity insertion occurs in a critical reactor. Which of the following descriptions best describes the transition of power (indicated by the highlighted section) after the initial insertion?
- a. The negative temperature coefficient of the moderator begins to turn power due to the insertion of negative reactivity
- b. Fission product gases (i.e., xenon) began to buildup after reduced fission events during the prompt drop and stabilized reactor power
- c. The rate of change for the power decrease is being slowed by the decay from the delayed neutron precursors
- d. The prompt drop of reactor power has decreased the number of total fission events, and with total less leakage from the core, reactor power will
Section A: Reactor Theory, Thermodynamics, and Fac. Operating CharacteristicsP a g e l 15 stabilize QUESTION A.19 [1.0 point]
The following is a pictorial representation of a reactor at a critical rod height. Using the diagram, appropriately identify the terms with their associated locations.
- a. I.C, II.B., III.D
- b. I.D, II.A., III.C
- c. I.A, II.B., III.C
- d. I.C, II.D., III.B QUESTION A.20 [1.0 point]
The ratio of the number of neutrons in one generation to the number of neutrons in the previous generation defines the:
- a. effective multiplication factor.
- b. fast fission factor.
- c. neutron non-leakage factor.
- d. neutron reproduction factor.
A. Shutdown Margin B. Minimum Shutdown Margin C. Total Rod Worth D. Core Excess
Section B: Normal/Emergency Procedures & Radiological Controls P a g e l 16 QUESTION B.1 [1.0 point]
What is the Emergency Classification for a sustained fire at the RPI critical reactor facility?
- a. Personnel Emergency
- b. Unusual Event (Class I)
- c. Emergency Alert
- d. General Emergency QUESTION B.2 [1.0 point]
You are commencing a reactor startup when it is determined that a TS related piece of equipment is required for safe reactor operations. The SRO in charge does not show concern and demands that you start up in lieu of violating license conditions. Under these circumstances, which of the following documents would most likely provide guidance to you for how to notify the NRC with regards to safety concerns at the reactor facility?
- a. RPI Safety Analysis Report
- b. NRC Form 3 Notice to Employees
- c. NRC Form 396 Personal Qualification Statement--Licensee
- d. 10 CFR 20 QUESTION B.3 [1.0 point]
RPI has created a new core configuration named X. In this core configuration there are 350 fuel pins used to perform critical operation. By the technical specifications at RPI, what is the minimum number of fuel pins needed before the reactor can be considered not shutdown if the rods are not fully inserted?
- a. 140
- b. 175
- c. 210
- d. 333
Section B: Normal/Emergency Procedures & Radiological Controls P a g e l 17 QUESTION B.4 [1.0 point]
Which one of the following at the RPI Critical Facility DOES NOT require the presence of a Senior Reactor Operator (SRO)?
- a. The relocation of an in-core experiment with worth equivalent to $1.00
- b. The manipulation of reactor console controls by a student in training
- c. Removal of the control rods for maintenance
- d. The rearrangement of two fuel assemblies QUESTION B.5 [1.0 point]
The special unit for absorbed dose Rem is defined in 10 CFR Part 20 in terms of a dose equivalent.
What does the term dose equivalent relate to?
- a. It is derived by accounting for the amount of radioactive material taken into the body of an adult worker by inhalation or ingestion in one year
- b. It is equal to the absorbed dose (rad) multiplied by the quality factor (Q) of the radiation
- c. It is the equivalent radiation required to produce 1 electrostatic unit of charge in 1 cc of dry air at Standard Temperature Pressure (STP).
- d. It is the equivalent dose one would receive during the 50-year period following intake QUESTION B.6 [1.0 point]
An example of Byproduct Material would be.
- a. Pu-239
- b. U-233
- c. U-235
- d. Au-198
Section B: Normal/Emergency Procedures & Radiological Controls P a g e l 18 QUESTION B.7 [1.0 point]
As an employee at the reactor facility, if you worked continuously in an area of radiation which read 250 mrem/hr, how long could you stay before you exceeded your yearly limit for exposure?
- a. 24 minutes
- b. 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />
- c. 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />
- d. 20 hours2.314815e-4 days <br />0.00556 hours <br />3.306878e-5 weeks <br />7.61e-6 months <br /> QUESTION B.8 [1.0 point]
How many hours per calendar quarter must you perform the functions of an RO or SRO to maintain an active RO or SRO license?
- a. 2
- b. 4
- c. 8
- d. 12 QUESTION B.9 [1.0 point]
Suppose you have 4 radioactive cookies: neutron, beta, gamma, and an alpha source cookie respectively. You can throw one away, eat one, hold one and put one in your pocket. How would you distribute the cookies in order to minimize your total exposure?
- a. Throw away the beta cookie, eat the gamma cookie, place the alpha cookie in your pocket, hold the neutron cookie in your hand.
- b. Throw away the neutron cookie, eat the beta cookie, place the gamma cookie in your pocket, hold the alpha cookie in your hand.
- c. Throw away the alpha cookie, eat the gamma cookie, place the beta cookie in your pocket, hold the neutron cookie in your hand.
- d. Throw away the neutron cookie, eat the gamma cookie, place the beta cookie in your pocket, hold the alpha cookie in your hand.
Section B: Normal/Emergency Procedures & Radiological Controls P a g e l 19 QUESTION B.10 [1.0 point]
The RCF Emergency procedures state that in the reactor room there are two Metal-X fire extinguishers.
Which of the following classes of fire would most likely be used with this type of fire extinguisher?
- a. Class A: Fires in ordinary combustibles, such as wood, paper, plastic, etc.
- b. Class B: Fires in flammable or combustible liquids, flammable gases, greases, etc.
- c. Class C: Fires in live electrical equipment.
- d. Class D: Fires involving combustible metals such as magnesium QUESTION B.11 [1.0 point]
According to the RPI Technical Specifications what are the requirements for the Licensed Senior Reactor Operator (LSO) to be Readily Available on Call while on duty?
- a. Whenever the reactor is not shutdown, the LSO on duty is not required to be in the control room, but must be at the facility,
- b. Whenever the reactor is not shutdown, the LSO on duty shall remain within a 10 mile radius
- c. Whenever the reactor is not shutdown, the LSO on duty shall remain within 15 minutes of the facility or within a 20 mile radius, whichever is closer
- d. Whenever the reactor is not shutdown, the LSO on duty shall remain within 30 minutes of the facility or a 15 mile radius, whichever is closer.
Section B: Normal/Emergency Procedures & Radiological Controls P a g e l 20 QUESTION B.12 [1.0 point]
By implementing Limiting Safety Settings, reactor protective features prevent the safety limit of
- a. Fuel temperature exceeding 2000°C
- b. Fission product release exceeding 10 CFR 20 limits
- c. Core excess reactivity exceeding $0.50
- d. Maximum power level exceeding 130 Watts QUESTION B.13 [1.0 point]
The following is an example of a portable ______________?
- a. Neutron detector
- b. Alpha detector
- c. Geiger-Mueller detector
- d. Air sampler QUESTION B.14 [1.0 point]
You are transferring fuel to the storage vault from the core. What is the maximum SPERT (F1) fuel pins which can be placed in a storage tube within the Fuel Vault?
- a. 5
- b. 15
- c. 24
- d. 30
Section B: Normal/Emergency Procedures & Radiological Controls P a g e l 21 QUESTION B.15 [1.0 point]
For a known core arrangement, the addition, movement, or removal of fuel will be limited to..
- a. 1/2 the difference between the current number of fuel pins and the linearly extrapolated critical number from the 1/M plot or 50 fuel pins, whichever is smaller
- b. $0.10 of reactivity or 4 fuel pins, whichever is greater
- c. $0.20 of reactivity or 4 fuel pins, whichever is smaller
- d. $0.30 of reactivity or 2 fuel pins, whichever is smaller QUESTION B.16 [1.0 point]
What is the dose rate after shielding a Cs-137 source that emits 1 MeV photons if the unshielded dose rate is 100 mrem/hr and the source is shielded by 1/2 inch lead? Given:
Density: 11.35 g/cm3 Mass Attenuation Coefficient: 0.0708 cm2/g
- a. 13.3 mrem/hr
- b. 36.2 mrem/hr
- c. 50.0 mrem/hr
- d. 91.4 mrem/hr
Section B: Normal/Emergency Procedures & Radiological Controls P a g e l 22 QUESTION B.17 [1.0 point]
You are performing a periodic radiation survey when you find a streaming source of radiation which the detector display reads 50 mr/hr on contact from a cabinet that is not posted for radiological safety. How would this area be posted in accordance with the requirements of 10 CFR 20?
- a. High Radiation Area @ 30 cm from the source
- b. High Radiation Area on contact w/ the cabinet
- c. Radiation Area @ 30 cm from the source
- d. Radiation Area on contact w/ the cabinet QUESTION B.18 [1.0 point]
In the event of a suspected fuel leak from a SPERT fuel element, which of the following nuclides would most likely be found in an Air Particulate Sample?
- a. Cs-138
- b. Rn-226
- c. Xe-133
- d. Co-60 QUESTION B.19 [1.0 point]
In an emergency involving the release of radioactive material, what is the emergency limit, according to the RPI E-Plan, for the dose to whole body for an adult?
- a. 5 Rem
- b. 10 Rem
- c. 12.5 Rem
- d. 25 Rem
Section B: Normal/Emergency Procedures & Radiological Controls P a g e l 23 QUESTION B.20 [1.0 point]
In the event of an accident involving personnel injury and potential radiological contamination, which of the following is the correct treatment facility by the RPI RCF E-Plan used?
- a. Ellis Hospital, Schenectady, NY
- b. Samaritan Hospital, Troy, NY
- c. Albany Medical Center, Albany, NY
- d. Glenridge Hospital, Glenview, NY
Section C: Facility and Radiation Monitoring Systems P a g e l 24 QUESTION C.1 [1.0 point]
Which one of the following systems has bypass provisions?
- a. Linear Power High Neutron Level Scram
- b. Water Dump Valve Scram
- c. Air particulate monitoring system in the ventilation stack
- d. Water fill interlock with water in reactor tank 10+/-1 above core top grid QUESTION C.2 [1.0 point]
Fuel pellet expansion in the SPERT fuel pins is most likely accommodated by __________.
- a. the stainless steel cladding
- b. the small dowel on the lower end cap which inserts into the lower grid plate
- d. the He fill gas around the fuel pellets QUESTION C.3 [1.0 point]
Which of the following would you most likely find in the control rod baskets?
- a. Lead cement which supports the absorber section
- b. A reflector section made of graphite
- c. An absorber section made of boron
- d. An aluminum oxide (Al2O3) insulator
Section C: Facility and Radiation Monitoring Systems P a g e l 25 QUESTION C.4 [1.0 point]
The following reaction (10B +
0 1
3 7 + ) can best be found in the ____________
- a. Control Room Radiation Monitor
- b. The gas gap of a SPERT fuel pin
- c. Intermediate Range Nuclear Instrumentation
- d. Source Range Nuclear Instrumentation QUESTION C.5 [1.0 point]
Which of the following is the RPI RCF TS temperature minimum limit for the reactor tank water?
- a. 40°F
- b. 50°F
- c. 80°F
- d. 100°F
Section C: Facility and Radiation Monitoring Systems P a g e l 26 QUESTION C.6 [1.0 point]
You are conducting a reactor startup and begin to pull rods. When doing so you observe that there is no outward rod motion. Which of the following is most likely the cause for the inability to move rods outward?
- a. Reactor water tank temperature is below the minimum setpoint value
- b. Startup Channel A count rate reads 1 cps
- c. Reactor period is 20 seconds
- d. Reactor water fill pump is on QUESTION C.7 [1.0 point]
By RPI RCF TS, which of the following is considered the auxiliary reactor scram?
- a. Turning the reactor key to the off position
- b. Intentionally opening the reactor door
- c. The moderator-reflector water dump
- d. Opening the breaker which disconnects the electrical power of the facility from the reactor QUESTION C.8 [1.0 point]
Deleted You are performing a reactor startup. Reactor power is increasing with Linear Power Channel 1 and 2 selected in the 0.1 W range. A student starts to ask you questions with regards to an experiment and you forget to switch both to the next highest range..At what power level would you most likely expect a reactor scram to occur in this condition?
- a. 0.09 W
- b. 0.9 W
- c. 100 W
- d. 135 W
Section C: Facility and Radiation Monitoring Systems P a g e l 27 QUESTION C.9 [1.0 point]
What is the maximum fill capacity of the reactor water tank?
- a. 1000 gallons
- b. 2000 gallons
- c. 3500 gallons
- d. 5000 gallons QUESTION C.10 [1.0 point]
According to RPI RCF TS, why is the minimum number of control rods set at 4?
- a. Controls thermal power from exceeding 100 W
- b. Prevents conditions which would cause fuel element failure in SPERT fuel
- c. Reduces the effect of flux tilting due to uneven power distribution
- d. Ensures there is adequate shutdown margin, even for a stuck rod condition QUESTION C.11 [1.0 point]
What is the setpoint for the control room radiation monitor alarm?
- a. 5 mr/hr
- b. 10 mr/hr c
40 mr/hr
- d. 100 mr/hr
Section C: Facility and Radiation Monitoring Systems P a g e l 28 QUESTION C.12 [1.0 point]
At the RPI CRF when the reactor is in the Standard configuration, you would expect _____ fuel pins in an octagonal array.
- a. 332
- b. 330
- c. 325
- d. 319 QUESTION C.13 [1.0 point]
What is the Maximum Hypothetical Accident at the RPI CRF?
- a. Fuel temperature exceeding 2000°F
- b. The compromise of fuel cladding integrity resulting in fission product release > 10 CFR 20 limits
- c. An unsecured experiment causing $0.60 of reactivity to be instantaneously inserted while the reactor is operating at maximum power
- d. The loss of coolant from the reactor tank and leaking outside of confinement space QUESTION C.14 [1.0 point]
What is the value for the maximum axial position when withdrawing control rods ?
- a. 32 inches
- b. 36 inches
- c. 38 inches
- d. 42 inches
Section C: Facility and Radiation Monitoring Systems P a g e l 29 QUESTION C.15 [1.0 point]
What is the scram setpoint for reactor period?
- a. 2 seconds
- b. 5 seconds
- c. 15 seconds
- d. 90% of on the highest scale of either of the two Linear Power Channels (LP1, LP2)
Section C: Plant and Rad Monitoring Systems Page 30 Section A: Reactor Theory, Thermodynamics, and Facility Operating Characteristics Question:
A.1 Answer: c Sm149 (41,000 b); U235 (687 b); Xe135 (2.65 x 106 b); B10 (3840 b)
Reference:
Lamarsh, J. Introduction to Nuclear Engineering p. 738 A.2 Answer: d
Reference:
DOE Manual Vol. 1, pg. 57, NEEP 234 Reactor Physics Part I, pg.2 A.3 Answer: a
Reference:
As reactor core temperature increases, the moderator to fuel ratio will decrease due to the decrease in density of the water. Therefore, due to this fact:
Lf (Fast Non-Leakage Factor): is the probability that neutrons will not leak out while still fast.
Therefore, with more moderator in the core, the probability that they will not leak out increases.
p(Resonance Escape Probability): is the probability that a neutron will be reduced to thermal energy levels without being absorbed by U-238. Due to the decrease in temperature and Doppler Broadening effects, the probability of escape increase.
f (Thermal Utilization Factor): is the ratio of absorption in fuel to the amount absorbed in the core (e.g., fuel, moderator, control rods, etc.). When the temperature decreases, the water moderator contracts, and a significant amount of it will accumulate in the reactor core. This means that Nm, the number of moderator atoms per cm3, will be increased, making it more likely for a neutron to be absorbed by a moderator atom. This increase in Nm results in an decrease in thermal utilization as moderator temperature decrease because a neutron now has a better chance of hitting a moderator atom.
DOE Manual Vol 2, Section 1.0 Additionally, Starting with a very hard spectrum (the extreme left of figure 3), softening the neutron spectrum as a result of an increase in H/U will impact the six-factor formula as follows.
- 1. Changes in thermal will be negligible.
- 2. Changes in the thermal utilization factor are dependent on the product of the fuel and moderator microscopic cross sections and their number densities (or, their macroscopic cross section). As H/U increases the number density of fuel is lowered and the number density of moderator is increased. Both the fuel and moderator microscopic absorption cross sections will increase as the system thermalizes. Therefore, the thermal utilization factor will always decrease.
- 3. The resonance escape probability will increase with decreasing fuel number density because of the corresponding reduction in the resonance absorber, 238U.
- 4. The fast fission factor will decrease because fewer fast neutrons will impact the fuel.
Section C: Plant and Rad Monitoring Systems Page 31
)
(
0
=
t e
P t
P 2
=
DT e
.)
2 ln(
DT
=
- 5. The thermal non-leakage probability will increase because of the decrease in thermal diffusion length.
- 6. The fast non-leakage probability will increase because fast neutron age is lowered with increased moderation.
RPI Reactor Critical Facility A Manual of Experiments, MANE-4440: Critical Reactor Laboratory dated 2010, p.25 A.4 Answer: c, d
Reference:
RPI Reactor Critical Facility A Manual of Experiments, MANE-4440: Critical Reactor Laboratory dated 2010 A.5 Answer: a Reference.
RPI Reactor Critical Facility A Manual of Experiments, MANE-4440: Critical Reactor Laboratory dated 2010, p.13 A.6 Answer: d.
Reference:
Resonance Escape Region DOE Manual Vol 1, Section 2, and NEEP 234 Reactor Physics III pg. 2 A.7 Answer: b
Reference:
NEEP 234 Reactor Physics II pg. 2 A.8 Answer: b
Reference:
T= 30 sec/ ln(2)= 43.28 sec
() = (0.1)
. = 0.4 mW
Section C: Plant and Rad Monitoring Systems Page 32 A.9 Answer: d Ref: From point A to B, reactor period is negative, and since Pf=Poe T t
, power will continue to decrease.
DOE Manual Vol. 1, Section 2 A.10 Answer: c Ref: This question can be answered in two ways. One way is through the equations as shown below, or two, use a rule of thumb that if the reactor moves halfway from its subcritical state towards criticality, the count rate will double.
1 2
2 1
1 1
k k
CR CR
=
2 CR =
1 CR 2
1 1
1 k
k
=50 cps
992
.0 1
984
.0 1
=100
- Where,
($)=/
p1=(0.0070)x(-$2.39)= -0.01673, p2= (0.0070)x($1.21)= 0.00850= 821 pcm--> -0.00823 1
1 1
1 p
k
=
=
01673
.0 1
1
+
= 0.984 2
2 1
1 p
k
=
=
00823
.0 1
1
+
=0.9918 DOE Manual Vol. 2, Section 1 A.11 Answer: b
Reference:
Group 1 is the longest-lived delayed neutron precursor for thermal fission in U-235, with a half-life of 55.72 sec.
Lamarsh, J. Introduction to Nuclear Engineering p. 88 A.12 Answer: a, b
Reference:
At 60% withdrawn, the reactivity in the core is $1.50.or 150 cents The reactivity added by a 5°C temp rise= 5°C($0.07/°C)= 35 cents Using the integral rod worth curve 60% (150 cents), the new rod height at 150 - 35=115 cents (50% withdrawn).
DOE Manual Vol. 2 Section 3
Section C: Plant and Rad Monitoring Systems Page 33 A.13 Answer: c
Reference:
DOE Manual, Section 3 A.14 Answer: d
Reference:
Af= 0.90 Ci Ao= ???
=0.693/64.8 hr Insert and rearrange to solve.
Lamarsh, J. 2001. Introduction to Nuclear Engineering 3rd Ed.. P. 23-25 A.15 Answer: c
Reference:
Mn-56 is beta decay, which is the conversion of a neutron into a proton and electron.
Baum, E., Knox, H., and Miller, T. 2002. Nuclides and Isotopes 16th Ed. p. 28 A.16 Answer: c
Reference:
The multiplication factor (k) is proportional to the total number of neutrons, prompt and delayed, emitted per fission. However, since only the fraction (1-) of the fission neutrons are prompt, the fraction of prompt neutrons from with regards to the multiplication factor is (1-
)k. Therefore, when (1-)k=1, the reactor is critical on prompt neutrons alone, and the reactor is said to be prompt critical. If you rearrange (1-)k=1 it will read
= 1 1
k Lamarsh, J. 2001. Introduction to Nuclear Engineering 3rd Ed.. pp.340-341 A.17 Answer: a
Reference:
DOE Handbook Vol I, pg. 45 A.18 Answer: c.
Reference:
DOE Handbook Vol II, pg. 14..
= (1 )
Section C: Plant and Rad Monitoring Systems Page 34 A.19 Answer: b
Reference:
DOE Manual Handbook Vol II, pg. 28 A.20 Answer: a
Reference:
DOE Manual Handbook Vol I
Section C: Plant and Rad Monitoring Systems Page 35 Section B: Normal Emergency Procedures & Radiological Controls Question:
B.1 Answer: c
Reference:
RPI E-Plan, Rev. 3, dated August 2004, p.5 B.2 Answer: b
Reference:
NRC Form 3. http://www.nrc.gov/reading-rm/doc-collections/forms/form3_us.pdf B.3 Answer: c
Reference:
RPI TS Version 2.1, September 2004, p.2 B.4 Answer: b
Reference:
Under 10 CFR Part 55, The regulations in this part do not require a license for an individual who-Under the direction and in the presence of a licensed operator or senior operator, manipulates the controls of a research or training reactor as part of the individuals training as a student 10 CFR Part 55.13 B.5 Answer: b
Reference:
10 CFR Part 20.1003 B.6 Answer: d.
Reference:
Byproduct material is radioactive material made radioactive by the process of using special nuclear material 10 CFR Part 20.1003 B.7 Answer d.
Reference:
5000 mrem/250 mr/hr= 20 hours2.314815e-4 days <br />0.00556 hours <br />3.306878e-5 weeks <br />7.61e-6 months <br /> B.8 Answer: b
Reference:
B.9 Answer: d RPI Reactor Critical Facility A Manual of Experiments, MANE-4440: Critical Reactor Laboratory dated 2010, pp. 42-46
Section C: Plant and Rad Monitoring Systems Page 36 B.10 Answer: d
Reference:
RPI Emergency Procedures 6.2.6 http://www.monroeextinguisher.com/catalog.asp?prodid=504347 and http://www.bc.edu/offices/facilities/meta-elements/pdf/fireExtinguisherTraining.pdf B.11 Answer: d
Reference:
RPI TS 1.0, September 2004 B.12 Answer: a
Reference:
RPI TS 3.0, September 2004 B.13 Answer: a
Reference:
http://www.deqtech.com/Ludlum_Medical_Physics/Products/m2241-4.htm B.14 Answer: b
Reference:
RCF Operating Procedures, G Fuel Handling, Version 2.1, September 2006 B.15 Answer: c
Reference:
RCF Operating Procedures, G Fuel Handling, Version 2.1, September 2006 B.16 Answer: b
Reference:
and
Solving for µ= x = (0.0708 cm2/g from table) x (11.35 g/cm3) = 0.8 cm-1 x = 0.5 inches x 2.54 cm/in = 1.27 cm
= 100/(.)(.)= 36.2 mrem/hr Lamarsh, J. Introduction to Nuclear Engineering p. 549 B.17 Answer: c
Reference:
B.18 Answer: a
Reference:
Emergency Preparedness Plan for the Maryland University Training Reactor, dated 12/99 p. 4-2 and MUTR SAR
Section C: Plant and Rad Monitoring Systems Page 37 B.19 Answer: c
Reference:
RPI E-Plan, Rev. 3, dated August 2004, p.7 B.20 Answer: a
Reference:
RPI E-Plan, Rev. 3, dated August 2004, p.8
Section C: Plant and Rad Monitoring Systems Page 38 Section C: Facility and Radiation Monitoring Systems Question:
C.1 Answer: b
Reference:
RPI TS 3.0, September 2004 C.2 Answer: d
Reference:
RPI SAR, Section 4.2, November 2002 C.3 Answer: c
Reference:
RPI SAR, Section 4.2.2, November 2002 C.4 Answer: c, d
Reference:
RPI SAR, Section 7.4 and 7.7, November 2002 C.5 Answer: b
Reference:
RPI SAR, Section 3.1, November 2002 and RPI TS 3.2, September 2004 C.6 Answer: d
Reference:
RPI SAR, Figure 7.2, November 2002 C.7 Answer: c
Reference:
RPI TS 3.1.5, September 2004 C.8 Deleted Answer: a
Reference:
RPI SAR, 13.1.2, November 2002 C.9 Answer: b
Reference:
RPI RCF Operating Procedures Section 12.G, Version 2.1, September 2006 C.10 Answer: d
Reference:
RPI TS 3.2, September 2004 C.11 Answer: b
Reference:
Section C: Plant and Rad Monitoring Systems Page 39 C.12 Answer: a
Reference:
RPI SAR, Section 4.5.1, November 2002 C.13 Answer: c
Reference:
RPI SAR, Section 13.1.1, November 2002 C.14 Answer: b
Reference:
RPI SAR, Section 4.2.2, November 2002 C.15 Answer: b