ML12324A060
| ML12324A060 | |
| Person / Time | |
|---|---|
| Site: | Rensselaer Polytechnic Institute |
| Issue date: | 11/19/2012 |
| From: | Gregory Bowman Division of Policy and Rulemaking |
| To: | Sreepada S Rensselaer Polytechnic Institute |
| Nguyen J | |
| Shared Package | |
| ML12229A246 | List: |
| References | |
| 50-255/13-001 | |
| Download: ML12324A060 (38) | |
Text
November 19, 2012 Dr. Sastry Sreepada, Director Department of Mechanical, Aerospace And Nuclear Engineering Building JEC - Room 2032 Rensselaer Polytechnic Institute 110 8th Street Troy, NY 12180-3590
SUBJECT:
EXAMINATION REPORT NO. 50-225/OL-13-01, RENSSELAER POLYTECHNIC INSTITUTE
Dear Dr. Sreepada:
During the week of November 5, 2012, the U.S. Nuclear Regulatory Commission (NRC) administered operator licensing examinations at your Rensselaer Polytechnic Institute 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 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 Mr. John T. Nguyen at (301) 415-4007 or via internet 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. 50-225
Enclosures:
- 1. Examination Report No. 50-225/OL-13-01
- 2. Corrected Written Examination cc: Mr. Jason Thompson, Rensselaer Polytechnic Institute cc w/o enclosures: See next page
Dr. Sastry Sreepada, Director November 19, 2012 Department of Mechanical, Aerospace And Nuclear Engineering Building JEC - Room 2032 Rensselaer Polytechnic Institute 110 8th Street Troy, NY 12180-3590
SUBJECT:
EXAMINATION REPORT NO. 50-225/OL-13-01 RENSSELAER POLYTECHNIC INSTITUTE
Dear Dr. Sreepada:
During the week of November 5, 2012, the U.S. Nuclear Regulatory Commission (NRC) administered operator licensing examinations at your Rensselaer Polytechnic Institute 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 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 Mr. John T. Nguyen at (301) 415-4007 or via internet 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. 50-225
Enclosures:
- 1. Examination Report No. 50-225/OL-13-01
- 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 GBowman Facility File CRevelle (O07-F8)
ADAMS ACCESSION #: ML12324A060 OFFICE PROB:CE IOLB:LA PROB:BC NAME JNguyen CRevelle GBowman DATE 11/14/2012 11/19/2012 11/19/2012 OFFICIAL RECORD COPY
Rensselaer Polytechnic Institute Docket No. 50-225 cc:
Mayor of the City of Schenectady Schenectady, NY 12305 Tim Rice 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 Mrs. Jessica Berry, RCF Supervisor NES Building, Room 1-10, MANE Department Rensselaer Polytechnic Institute 110 8th St.
Troy, NY 12180 Peter Collopy, Director EH&S Rensselaer Polytechnic Institute 21 Union Street Gurley Building 2nd Floor Troy, NY 12180 Alyse Peterson, State Liaison Officer Designee Senior Project 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 2 U. S. NUCLEAR REGULATORY COMMISSION OPERATOR LICENSING INITIAL EXAMINATION REPORT EXAMINATION REPORT NO:
50-225/OL-13-01 FACILITY:
Rensselaer Polytechnic Institute FACILITY DOCKET NO.:
50-225 FACILITY LICENSE NO.:
CX-22 SUBMITTED BY:
_______/RA/_________________ 11/14/2012 John T. Nguyen, Chief Examiner Date
SUMMARY
During the week of November 5, 2012, the NRC administered operator licensing examinations to three 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 0/0 3/0 3/0 Operating Tests 0/0 3/0 3/0 Overall 0/0 3/0 3/0
- 3.
Exit Meeting:
Jason Thompson, RPI, Reactor Supervisor John T. Nguyen, NRC, Chief Examiner The NRC examiner thanked the facility for their support in the administration of the examinations. The facility licensee had only one comment on the written examination, which has been incorporated into the examination included as Enclosure 2 to this report.
ENCLOSURE 2 U. S. NUCLEAR REGULATORY COMMISSION NON-POWER REACTOR LICENSE EXAMINATION FACILITY:
RCF REACTOR TYPE:
Critical Experimental DATE ADMINISTERED:
11/5/2012 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 ___
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 ___
B03 a b c d ___
B04 a ___ b ___ c ___ d ___ (0.25 each)
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 ___
(***** 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 ___ (0.25 each)
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 ___ (0.25 each)
C10 a b c d ___
C11 a ___ b ___ c ___ d ___ (0.50 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) 2 1
1 2
eff eff eff eff K
K K
K
=
FACILITY COMMENT QUESTION A.4
[1.0 points]
Reactor is at full power. The operator immediately scrams all control rods into the core. This insertion will cause:
Given:
T: reactor period, *: Prompt neutron lifetime; : reactivity insertion; : beta fraction
- a.
The delayed period to be equal to 80 seconds
- b.
A number of prompt neutrons equals to a number of delayed neutrons
- c.
The immediate period to be a function of the prompt neutron lifetime (T=*/)
- d.
A sudden change of power that equals to the initial power multiplied by (1- )/ ( -)
A.4 Answer d
Reference:
Burn, R., Introduction to Nuclear Reactor Operations, © 1988, Sec 4.6, page 4-17 FACILITY COMMENT I spoke with all the candidates we think the written exam was fair. The only comment was on the theory question that asked about what would happen when negative reactivity was inserted, and the long term reactor period was 80s was an incorrect choice. I'm not sure if other facilities are specific about positive or negative, but I would ask that in the future, the answer specifically states +80s. I don't think we need to take any action for this exam.
NRC RESPONSE Facility comment accepted, the POSITIVE (+) will be added when the question is used in the future.
Section A: Reactor Theory, Thermo, and Fac. Operating Characteristics QUESTION A.1
[1.0 point]
Which ONE of the following will be the resulting stable reactor period when a $0.25 reactivity insertion is made into an exactly critical reactor core? Neglect any effects from prompt. Given
=0.0070 and =0.1 sec
- a.
15 seconds
- b.
20 seconds
- c.
25 seconds
- d.
30 seconds QUESTION A.2
[1.0 point]
Which ONE of the following is a correct statement of why delayed neutrons enhance the ability to control reactor power?
- a.
Prompt neutrons are born at lower energy levels than delayed neutrons
- b.
Prompt neutrons can cause fissions in both U-235 and U-238; whereas delayed neutrons can only cause fissions in U-235
- c.
Delayed neutrons increase the average neutron lifetime that allows a reactor to be controlled
- d.
The average number of delayed neutrons produced per fission is higher than the average number of prompt neutrons QUESTION A.3
[1.0 point]
A nuclear reactor startup is being performed by adding EQUAL amounts of positive reactivity and waiting for neutron population to stabilize. As the reactor approaches criticality, the Neutron Multiplication, Keff, will __________ after each reactivity addition; and the TIME required for the neutron population to STABILIZE will ___________ after each reactivity addition.
- a.
decrease; decrease
- b.
increase; increase
- c.
increase; decrease
- d.
remains the same; increase
Section A L Theory, Thermo & Fac. Operating Characteristics QUESTION A.4
[1.0 points]
POSITIVE (+) is added per facility comment Reactor is at full power. The operator immediately scrams all control rods into the core. This insertion will cause:
Given:
T: reactor period, *: Prompt neutron lifetime; : reactivity insertion; : beta fraction
- a.
The delayed period to be equal to POSITIVE (+) 80 seconds
- b.
A number of prompt neutrons equals to a number of delayed neutrons
- c.
The immediate period to be a function of the prompt neutron lifetime (T=*/)
- d.
A sudden change of power that equals to the initial power multiplied by (1- )/ ( -)
QUESTION A.5
[1.0 point]
Given a source strength of 100 neutrons per second (N/sec) and a multiplication factor of 0.9, which ONE of the following is the expected stable neutron count rate?
- a.
900 N/sec
- b.
1000 N/sec
- c.
2000 N/sec
- d.
2500 N/sec QUESTION A.6
[1.0 point]
Given a reactor period of 32 seconds, approximately how long will it take for power to triple?
- a.
22 seconds
- b.
35 seconds
- c.
46 seconds
- d.
64 seconds
Section A L Theory, Thermo & Fac. Operating Characteristics QUESTION A.7 [1.0 point]
Keff is K4 times Y
- a.
the reproduction factor ()
- b.
the resonance escape probability (p)
- c.
the fast fission factor ()
- d.
the total non-leakage probability (f H th)
QUESTION A.8
[1.0 point]
Prompt neutrons are produced by:
- a.
decay of N-16
- b.
directly from the fission
- c.
decayed fission fragments
- d.
Pair Production of high energy photon QUESTION A.9
[1.0 point]
The reactor is on a CONSTANT positive period. Which ONE of the following power changes will take the longest time to complete?
- a.
5%, from 95% to 100%
- b.
10%, from 80% to 90%
- c.
15%, from 15% to 30%
- d.
20%, from 60% to 80%
Section A L Theory, Thermo & Fac. Operating Characteristics QUESTION A.10
[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 at resonant epithermal energy levels that causes fissions to occur in U-238.
- c.
A neutron that experiences an increase in energy levels after collisions with larger atoms of the moderator.
- d.
A neutron that experiences no net change in energy after several collisions with atoms of the moderator on average.
QUESTION A.11 [1.0 point]
A reactor with Keff = 0.7 contributes 1000 neutrons in the first generation. Changing from the first generation to the SECOND generation, how many neutrons are there in the second generation?
- a.
1250
- b.
1500
- c.
1700
- d.
2000 QUESTION A.12
[1.0 point]
In a subcritical reactor, Keff is increased from 0.861 to 0.946. Which ONE of the following is the amount of reactivity that was added to the core?
- a.
0.054 delta-K/K
- b.
0.085 delta-K/K
- c.
0.104 delta-K/K
- d.
0.161 delta-K/K
Section A L Theory, Thermo & Fac. Operating Characteristics QUESTION A.13
[1.0 point]
Which ONE of the following best describes the alpha decay of a nuclide?
- a.
The atomic mass number unchanged and the number of protons decreases by 2.
- b.
The atomic mass number decrease by 2 and the number of protons decreases by 2.
- c.
The atomic mass number increases by 4 and the number of protons increases by 2.
- d.
The atomic mass number decreases by 4 and the number of protons decreases by 2.
QUESTION A.14
[1.0 point]
Delayed neutrons comprise approximately what percent of all neutrons produced in the reactor?
- a.
0.65%
- b.
1.3%
- c.
6.5%
- d.
20%
QUESTION A.15
[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 non leakage _____________.
- c.
Fast non leakage _____________.
- d.
Rod worth _____________.
Section A L Theory, Thermo & Fac. Operating Characteristics QUESTION A.16
[1.0 point]
Which ONE of the following is the most correct reason for having an installed neutron source within the core?
An installed neutron source is very important during startup because without of a neutron source...
- a.
the chain reaction in the reactor core would NOT start
- b.
the startup channel would NEVER indicate neutron population
- c.
the compensating voltage on the source range detector doesnt work
- d.
the reactor could result in a sudden increase in power if the control rods were pulled out far enough QUESTION A.17
[1.0 point]
The reactor is critical at 0.1 watt. Which ONE of the following correctly describes the reactor behavior, when a reactivity worth of 0.10 % delta K/K is IMMEDIATELY inserted to the reactor core?
- a.
Subcritical
- b.
Critical
- c.
Supercritical
- d.
Prompt critical
Section A L Theory, Thermo & Fac. Operating Characteristics QUESTION A.18
[1.0 point]
Given the following Core Reactivity Data during startup:
Control Rod Total Rod Worth
($)
Rod Worth removed at 1 watts critical ($)
Rod excess at 1 watts critical ($)
Rod #1 1.00 1.00 0.00 Rod # 2 1.10 1.00 0.10 Rod # 3 1.20 0.90 0.30 Rod # 4 1.30 1.20 0.10 Total Worth 4.60 4.10 0.50 The SHUTDOWN MARGIN defined in the RCF Technical Specifications for this core is:
- a.
$0.5
- b.
$2.8
- c.
$3.6
- d.
$4.1
(***** END OF CATEGORY A *****)
Section B Normal/Emergency Procedures and Radiological Controls QUESTION B.1 [1.0 point]
Per RCF Technical Specifications, for movable experiments with an absolute worth greater than
______, the maximum reactivity change for withdrawal and insertion shall be _____.
- a.
$0.60, 0.50 $/sec
- b.
$0.35, 0.20 $/sec
- c.
$0.60, 0.10 $/sec
- d.
$0.35, 0.50 $/sec QUESTION B.2 [1.0 point]
Reactor Operator works a standard forty (40) hour work week. His duties require him to work in a high radiation area for (4) hours a day. The dose rate in the area is 100 mR/hour. Which ONE of the following is the MAXIMUM number of days Reactor Operator may perform his duties WITHOUT exceeding 10 CFR 20 limits?
- a.
5 days
- b.
10 days
- c.
12 days
- d.
13 days QUESTION B.3
[1.0 point]
According to emergency classification guide, the event associated with the contaminated moderator is defined as:
- a.
Operational Event
- b.
Personnel Emergency
- c.
Emergency Alert
- d.
Site Area Emergency
Section B Normal/Emergency Procedures and Radiological Controls QUESTION B.4 [1.0 point, 0.25 each]
Match the terms in column A with their respective definitions in column B.
Column A Column B
- a.
Radioactivity
- 1.
To remove a facility or site safely from service and reduce residual radioactivity to a level that permits in 10 CFR 52.
- b.
Contamination
- 2.
An impurity pollutes or adulterates another substance. The transferable radioactive materials are the sources of ionizing radiations.
- c.
Dose
- 3.
The quantity of radiation absorbed per unit mass by the body or by any portion of the body.
- d.
Decommission
- 4.
That property of a substance which causes it to emit ionizing radiation. This property is the spontaneous transmutation of the atoms of the substance.
QUESTION B.5
[1.0 point]
What is the HALF LIFE of the isotope contained in a sample which produces the following count rates?
Time (Minutes)
Counts per Minute (cpm)
Initial count 900 30 740 60 615 90 512 180 294
- a.
551 minutes
- b.
312 minutes
- c.
111 minutes
- d.
88 minutes
Section B Normal/Emergency Procedures and Radiological Controls QUESTION B.6 [1.0 point]
Per RCF Emergency Plan, what is the maximum allowable dose which the RCF Emergency Management can authorize for a volunteer to receive to save a life of someone injured?
- a.
5.0 Rem
- b.
12.5 Rem
- c.
25.0 Rem
- d.
50.0 Rem QUESTION B.7 [1.0 point]
A radiation survey of an area reveals a general radiation reading of 1 mrem/hr. However, there is a small section of pipe which reads 20 mrem/hr at one (1) meter. Assuming that the pipe is a point source, which ONE of the following defines the posting requirements for the area in accordance with 10CFR Part 20?
- a.
Restricted Area
- b.
Radiation Area
- c.
- d.
Very High Radiation Area QUESTION B.8 [1.0 point]
Which ONE of the following materials shall NOT be irradiated at the RCF reactor core?
- a.
Corrosive material
- b.
Explosive material
- c.
Gaseous material
- d.
Any movable experiment
Section B Normal/Emergency Procedures and Radiological Controls QUESTION B.9 [1.0 point]
A sheet of two-inch lead reduces the gamma exposure in a beam of radiation from 800 mR/hr to 400 mR/hr. If you add additional 2 sheets (total of six inches of lead) what will be the new radiation level? (Assume all reading is the same distance from the source.)
- a.
50 mR/hr
- b.
100 mR/hr
- c.
175 mR/hr
- d.
200 mR/hr QUESTION B.10
[1.0 point]
Which ONE of following types of radiation is the HIGHEST Quality Factor specified in 10 CFR 20?
- a.
alpha
- b.
beta
- c.
gamma
- d.
neutron (unknown energy)
QUESTION B.11
[1.0 point]
The reactor power shall NOT exceed the maximum power level of 100 watts. This is an example of:
- a.
Safety Limit (SL)
- b.
Limiting Safety System Setting (LSSS)
- c.
Limiting Conditions for Operation (LCO)
- d.
Surveillance Requirement (SR)
Section B Normal/Emergency Procedures and Radiological Controls QUESTION B.12 [1.0 point]
According to the Pre-Startup Procedures, which ONE of the following is the material used as a source check for the area gamma monitors?
- a.
- b.
Pu-240
- c.
- d.
N-16 QUESTION B.13 [1.0 point]
During a reactor operation, a senior reactor operator (SRO) on-call becomes ill and is taken to the hospital. Only a senior reactor operator and a knowledgeable trainee remain in the facility.
Per RCF Technical Specifications, reactor operation:
- a.
must be discontinued because reactor operation needs an SRO on-call in the control room.
- b.
must be discontinued because reactor operation needs at least two SRO in the control room.
- c.
may continue if the trainee knows how to activate the manual scram and initiate emergency procedures.
- d.
may continue if the SRO can find any SRO to be served as SRO on-call.
QUESTION B.14
[1.0 point]
Which ONE of the following requires NRC approval for changes?
- a.
Technical Specifications b
RCF Emergency Procedure c
RCF Pre-Startup Procedures d
Requalification Operator Licensing Examination
Section B Normal/Emergency Procedures and Radiological Controls QUESTION B.15 [1.0 point]
The MAXIMUM scram time for each control rod from its fully withdrawn position to its fully inserted position shall be _______ milliseconds.
- a.
450
- b.
550
- c.
900
- d.
1100 QUESTION B.16 [1.0 point]
Which ONE of the following is the large contributor to Ar-41 production?
- a.
Neutron interaction with the hydrogen in the reactor tank water
- b.
Gamma interaction with the oxygen in the reactor tank water
- c.
Beta interaction with the Nitrogen in the reactor tank water
- d.
Neutron interaction with dissolved air in the reactor tank water QUESTION B.17 [1.0 point]
You are transferring fuel to the storage vault from the core. The maximum number of the SPERT fuel pins that you allow to handle at one time is:
- a.
1
- b.
2
- c.
3
- d.
4
Section B Normal/Emergency Procedures and Radiological Controls QUESTION B.18 [1.0 point]
In the event of an accident involving personnel injury and potential radiological contamination, which ONE of the following is the correct treatment facility by the RCF Emergency Plan used?
- a.
Albany Medical Center, Albany, NY
- b.
Samaritan Hospital, Troy, NY
- c.
Ellis Hospital, Schenectady, NY
- d.
Glenridge Hospital, Glenview, NY
(***** END OF CATEGORY B *****)
Section C Facility and Radiation Monitoring Systems QUESTION C.1 [1.0 point]
Which ONE of the following is the MAIN reason why you dont want to open the air tank pet cock too fast or too far during the pre-startup?
- a.
Reactor scram
- b.
Harmful due to noise levels
- c.
Air compressor power turns OFF
- d.
The compressor tank of water stops draining QUESTION C.2 [1.0 point, 0.25 each]
Attached is the Figure 5.1: RCF Piping Diagram. Match the indicated valve number listed in column A with their intended function listed in column B. (Item in column B is to be used more than once or not at all.)
Column A Column B
- a.
Valve # 5
- 1.
Normally CLOSE/ Remote Fail OPEN
- b.
Valve # 2
- 2.
Normally OPEN/ Remote Fail CLOSE
- c.
Valve # 4
- 3.
Normally CLOSE/ Remote Fail CLOSE
- d.
Valve # 6
- 4.
Normally CLOSE/ Hand valve
- 5.
Normally OPEN/ Hand valve QUESTION C.3 [1.0 point]
When a failure of fuel pins occurs, the Continuous Air Monitor (CAM) alarms due to the release of:
- a.
- b.
Ar-41
- c.
Na-24
- d.
Xe-135
Section C Facility and Radiation Monitoring Systems QUESTION C.4
[1.0 point]
Per Surveillance Procedures-Section C, the reactor operator will use ____ foils for the absolute power measurement.
- a.
- b.
- c.
- d.
aluminum QUESTION C.5
[1.0 point]
Which ONE of the following is the neutron startup source currently used at the RCF reactor?
- a.
Americium-Beryllium (Am-Be)
- b.
Plutonium-Beryllium (Pu-Be)
- c.
Radon-Beryllium (Ra-Be)
- d.
Uranium-Beryllium (U-Be)
QUESTION C.6 [1.0 point]
A signal for the Period < 5 Sec scram comes from the:
- a.
Startup Channel A (SUA)
- b.
Linear Power Channel 1 (LP1)
- c.
Linear Power Channel 2 (LP2)
- d.
Log Power Channel (PP2)
Section C Facility and Radiation Monitoring Systems QUESTION C.7 [1.0 point]
During a normal operation, which ONE of the following conditions will scram the reactor?
- a.
Reactor period exceeds 15 seconds
- b.
Neutron flux is less than 2 cps
- c.
Reactor door is opened
- d.
Line voltage to recorder is less than 100 V QUESTION C.8 [1.0 point]
Which ONE of the following is the best description on how the Uncompensated Ion Chamber (UIC) operates?
Material used in UIC Interact with Results
- a.
Pu-239 +
neutron B-10 + alpha -> N-14 + gamma
- b.
B-10 +
neutron B-11 -> Li-7 + alpha
- c.
U-235 +
neutron Fission fragments + gamma
- d.
Am-239 +
neutron Be-9 + gamma -> Li-8 + beta QUESTION C.9 [1.0 point, 0.25 each]
Match the readings listed in column A with their respective responses listed in column B Assume the reactor is in operation. (Items in column B is to be used more than once or not at all.)
Column A Column B
- a.
Linear Power # 1 = 210%
- 1.
Normal Operation
- b.
Water Dump Bypass
- 2.
Control rod withdrawal prohibit
- c.
Voltage to Recorders = 90 V
- 3.
Reactor scram
- d.
Count rate < 2 cps
Section C Facility and Radiation Monitoring Systems QUESTION C.10 [1.0 point]
Following a loss of building electrical power, the solenoid suppling air to the dump valve:
- a.
will de-energize, causing the dump valve fails OPEN and moderator drained from the reactor tank
- b.
will energize, causing the dump valve fails OPEN and moderator drained from the reactor tank
- c.
will de-energize, causing the dump valve fails CLOSE and moderator kept in the reactor tank
- d.
will energize, causing the dump valve fails CLOSE and moderator kept in the reactor tank QUESTION C.11 [2.0 points, 0.5 each]
Match the reactor locations listed in column A with their respective alarm setpoints listed in column B. (Item in column B is to be used only once)
Column A Column B
- a.
Control room
- 1. 10 mr/hr
- b.
Equipment hallway
- 2. 20 mr/hr
- c.
Reactor room
- 3. 40 mr/hr
- d.
Reactor deck
- 4. 100 mr/hr QUESTION C.12
[1.0 point]
Which ONE of the following best describes the reason for the high sensitivity of Geiger-Mueller tube detector?
- a.
BF3 fill gas
- b.
Coating with U-235
- c.
Lower voltage applied to the detector helps to amplify all incident events.
- d.
Any incident radiation event causing primary ionization results in ionization of entire detector.
Section C Facility and Radiation Monitoring Systems QUESTION C.13
[1.0 point]
During Pre-Startup, you expose a known check source to the area gamma monitors to verify whether it is operable. This action is considered to be:
- a.
a channel test
- b.
a channel check
- c.
a channel calibration
- d.
a channel verification QUESTION C.14 [1.0 point]
Fuel pellet radial expansion in the SPERT fuel pins is most likely accommodated by
- a.
the He fill gas around the fuel pellets
- b.
the BF3 fill gas around the fuel pellets
- c.
the chromium nickel spring in the upper plenum region
- d.
the small dowel on the lower end cap which inserts into the lower grid plate QUESTION C.15 [1.0 point]
Which ONE of the following describes the ventilation system for the reactor room?
- a.
It uses natural circulation with a single vent to the outside stack
- b.
It shares a forced fan vent with the control room with back draft dampers to prevent cross-contamination
- c.
It uses natural circulation sharing a vent with the control room that is isolated on measured HIGH Ar-41.
- d.
It uses a single vent with natural circulation during normal operation with a forced fan starting on measured HIGH Ar-41.
Section C Facility and Radiation Monitoring Systems QUESTION C.16 [1 point]
WHICH ONE of the following is true statement regarding detector requirement to measure N16 release to the environment?
- a.
Continuous Air Monitor (CAM)
- b.
Area Gamma Monitor at the Control Room
- c.
Area Gamma Monitor at the Reactor Deck
- d.
NONE, N16 has too short a half-life to require environmental monitoring.
QUESTION C.17 [1.0 point]
Maximum control rod motion is limited to:
- a.
22 inches, the length of the active absorber in the control rod
- b.
36 inches, the effective height of the core
- c.
42 inches, the nominal length of a fuel pin
- d.
64 inches, the height of water in the tank.
(***** END OF CATEGORY C *****)
(***** END OF EXAMINATION *****)
Section A L Theory, Thermo & Fac. Operating Characteristics A.1 Answer:
d
=$*
=$0.25*0.007 =0.00175 k T = (-)/
T = (0.0070 - 0.00175)/0.1 x 0.00175 = 30 seconds A.2 Answer:
c
Reference:
Burn, R., Introduction of Nuclear Reactor Operations, © 1982, Section 3.3.7, page 3-37 A.3 Answer b
Reference:
NRC Standard Question A.4 Answer d
Reference:
Burn, R., Introduction to Nuclear Reactor Operations, © 1988, Sec 4.6, page 4-17 A.5 Answer:
b
Reference:
CR = S/(1-K) CR = 100/(1 -.9) = 1000 A.6 Answer:
b
Reference:
P=Poet/ 3=1* et/32 t = 32 sec*ln(3) = 35.2 sec A.7 Answer:
d
Reference:
DOE Handbook Vol 2, L Theory (Nuclear Parameters), E.O. 1.1 a&b, pg. 9 A.8 Answer:
b
Reference:
Burn, R., Introduction to Nuclear Reactor Operations, © 1982, Sec 3.2.
A.9 Answer:
c
Reference:
Time is related to ratio of final power to initial power. 2:1 is the largest ratio.
A.10 Answer:
d
Reference:
NRC Standard Question A.11 Answer:
c
Reference:
Burn, R., Introduction to Nuclear Reactor Operations, © 1982, § 5.3, p. 5.6 2-nd generation=n + K*n=1000+700=1700 neutrons
Section A L Theory, Thermo & Fac. Operating Characteristics A.12 Answer:
c
Reference:
Burn, R., Introduction to Nuclear Reactor Operations, © 1982, Sec 3.3.3, page 3-21.
(0.946-0.861)/(0.946*0.861) =0.104 delta-K/K A.13 Answer d
Reference:
Chart of the Nuclides A.14 Answer:
a
Reference:
DOE Fundamentals Handbook, Nuclear Physics and Reactor Theory, Volume 2 A.15 Answer:
a, Increase b, Decrease c, Decrease d, Increase
Reference:
Burn, R., Introduction of Nuclear Reactor Operations, © 1988, Sec 3.3.2 A.16 Answer:
d
Reference:
NRC Standard Question A.17 Answer:
c
Reference:
Burn, R., Introduction of Nuclear Reactor Operations, © 1988, Sec 4.2 0.1 % delta-K/K =0.001 delta-K/K <0.007, so reactor is supercritical A.18 Answer:
b
Reference:
Tech Spec SDM = 3rod worth removed at critical - most reactivity control rod worth= $4.1 -$1.3 = $2.8 or Tech Spec SDM = total rod worth -(3rod excesses + most reactivity control rod worth)= $4.6 -
($0.5+$1.3) = $2.8 2
1 1
2 eff eff eff eff K
K K
K
=
Section B Normal/Emergency Procedures and Radiological Controls B.1 Answer:
b
Reference:
TS 2.8 B.2 Answer:
c
Reference:
10CFR20.1201(a)(1) [5000 mr x 1 hr x day = 12.5 days 100 mr 4 hr B.3 Answer:
c
Reference:
Emergency Plan, Section 4.2 B.4 Answer:
a(4) b(2) c(3) d(1)
Reference:
10 CFR 20 B.5 Answer:
- c.
Reference:
A = Aoe -t 294 = 900e-180, 180 = -ln 0.327,
= 0.00623 min-1 t1/2 = 0.693 /, = 0.693 / 0.00623 min-1,
= 111 minutes B.6 Answer:
b
Reference:
RCF Emergency Plan 7 B.7 Answer:
c
Reference:
20 mrem/hr at 1 meter (100 cm.) = 222 mrem/hr at 30 cm.
B.8 Answer:
b
Reference:
TS 3.8 B.9 Answer:
b
Reference:
2 inches equal a half-thickness. Adding 4 inches (in total of six inches) results in a total of three half-thicknesses. (800) x (1/2)3 = 800*0.125 = 100 mR/hr B.10 Answer:
a
Reference:
10CFR20.1004 B.11 Answer:
b
Reference:
Technical Specifications, Section 2.2 B.12 Answer:
c
Reference:
Pre-Startup Procedures,Section I
Section B Normal/Emergency Procedures and Radiological Controls B.13 Answer:
d
Reference:
TS 6.1 B.14 Answer:
a
Reference:
10 CFR 50.59 and 10 CFR 50.90 B.15 Answer:
c
Reference:
TS 3.2.3 B.16 Answer:
d
Reference:
NRC Standard Question B.17 Answer:
b
Reference:
RCF Operating Procedures, G Fuel Handling, Version 2.1, September 2011 B.18 Answer:
c
Reference:
RCF Emergency Plan, Rev. 3, dated August 2004, p.8
Section C Facility and Radiation Monitoring Systems C.1 Answer:
b
Reference:
RCF Pre-Startup Procedures, Section B, page 3 C.2 Answer:
a,1 b,5 c,2 d,4
Reference:
RCF SAR, Section 4.3 and Section 5.1 C.3 Answer:
d
Reference:
NRC Standard Question C.4 Answer:
c
Reference:
RCF Surveillance Procedures-Section C, page 5 C.5 Answer:
b
Reference:
RCF SAR 4.2.4, page 4-14 C.6 Answer:
d
Reference:
RCF SAR 7.2.3, page 7-2 C.7 Answer:
c
Reference:
RCF Pre-Startup Procedures, Section C, page 3 C.8 Answer:
b
Reference:
RCF Manual of Experiments, Section 1.2, page 3 C.9 Answer:
a,3 b,1 c,2 d,2
Reference:
TS 3.2 C.10 Answer:
a
Reference:
RCF SAR, Section 8.1, page 8-1 C.11 Answer:
a,1 b,3 c,2 d,4
Reference:
RCF Pre-Startup Procedures,Section I, page 8 C.12 Answer:
d
Reference:
RCF Manual of Experiments, Section 1.2, page 1 C.13 Answer:
a
Reference:
Section C Facility and Radiation Monitoring Systems C.14 Answer:
a
Reference:
RCF SAR, Section 4.2, C.15 Answer:
a
Reference:
SAR, Section 9.1 C.16 Answer:
d
Reference:
b
Reference:
Section C Facility and Radiation Monitoring Systems