IR 05000184/2013001
| ML12305A213 | |
| Person / Time | |
|---|---|
| Site: | National Bureau of Standards Reactor |
| Issue date: | 11/01/2012 |
| From: | Gregory Bowman Division of Policy and Rulemaking |
| To: | O'Kelly S US Dept of Commerce, National Institute of Standards & Technology (NIST) |
| Young P | |
| Shared Package | |
| ML12241A297 | List: |
| References | |
| 50-184/OL-13-01 50-184/OL-13-01 | |
| Download: ML12305A213 (34) | |
Text
ber 1, 2012
SUBJECT:
INITIAL EXAMINATION REPORT NO. 50-184/OL-13-01, NATIONAL INSTITUTE OF STANDARDS AND TECHNOLOGY
Dear Dr. OKelly:
During the week of October 22, 2012, the NRC administered operator licensing examinations at your National Institute of Standards and Technology reactor. The examinations were conducted according to NUREG-1478, "Operator Licensing Examiner Standards for Research and Test Reactors," Revision 2. Examination questions and preliminary findings were discussed with those members of your staff identified in the enclosed report at the conclusion of the examination.
In accordance with Title 10 of the Code of Federal Regulations Section 2.390, a copy of this letter and the enclosures will be available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records (PARS) component of NRC's Agencywide Documents Access and Management System (ADAMS). ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html. The NRC is forwarding the individual grades to you in a separate letter which will not be released publicly. Should you have any questions concerning this examination, please contact Mr. Phillip T. Young at (301) 415-4094 or via internet e-mail phillip.young@nrc.gov.
Sincerely,
/RA/
Gregory T. Bowman, Chief Research and Test Reactors Oversight Branch Division of Policy and Rulemaking ber 1, 2012
SUBJECT:
INITIAL EXAMINATION REPORT NO. 50-184/OL-13-01, NATIONAL INSTITUTE OF STANDARDS AND TECHNOLOGY
Dear Dr. OKelly:
During the week of October 22, 2012, the NRC administered operator licensing examinations at your MIT reactor. The examinations were conducted according to NUREG-1478, "Operator Licensing Examiner Standards for Research and Test Reactors," Revision 2. Examination questions and preliminary findings were discussed with those members of your staff identified in the enclosed report at the conclusion of the examination.
In accordance with Title 10 of the Code of Federal Regulations Section 2.390, a copy of this letter and the enclosures will be available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records (PARS) component of NRC's Agencywide Documents Access and Management System (ADAMS). ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html. The NRC is forwarding the individual grades to you in a separate letter which will not be released publicly. Should you have any questions concerning this examination, please contact Mr. Phillip T. Young at (301) 415-4094 or via internet e-mail phillip.young@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. 50-184 Enclosures: 1. Examination Report No. 50-184/OL-12-03 2. Written examination as administeredd cc w/o enclosures: See next page DISTRIBUTION w/ encls.:
PUBLIC PROB r/f RidsNRRDPRPRTA RidsNRRDPRPRTB Facility File (CRevelle) O-7 F-08 ADAMS ACCESSION #: ML12305A213 TEMPLATE #:NRR-074 OFFICE PRTB:CE IOLB:LA PRTB:BC NAME PYoung CRevelle GBowman DATE 11/01/2012 11/01 /2012 11/01/2012 OFFICIAL RECORD COPY
National Institute of Standards and Technology Docket No. 50-184 cc:
Director, Department of State Planning 301 West Preston Street Baltimore, MD 21201 Director, Air & Radiation Management Administration Maryland Dept of the Environment 1800 Washington Blvd., Suite 710 Baltimore, MD 21230 Director, Department of Natural Resources Power Plant Siting Program Energy and Coastal Zone Administration Tawes State Office Building Annapolis, MD 21401 President Montgomery County Council 100 Maryland Avenue Rockville, MD 20850 Test, Research, and Training Reactor Newsletter University of Florida 202 Nuclear Sciences Center Gainesville, FL 32611
U. S. NUCLEAR REGULATORY COMMISSION OPERATOR LICENSING INITIAL EXAMINATION REPORT REPORT NO.: 50-184/OL-13-01 FACILITY DOCKET NO.: 50-184 FACILITY LICENSE NO.: TR-5 FACILITY: NSBR EXAMINATION DATES: October 22, 2012 SUBMITTED BY: __________________________ _________
Phillip T. Young, Chief Examiner Date SUMMARY:
During the week of October 22, 2012 the NRC administered licensing examinations to one Senior Reactor Operator-Instant (SROI) applicants. The applicant passed all portions of the examination.
REPORT DETAILS 1. Examiners: Phillip T. Young, Chief Examiner, NRC 2. Results:
RO PASS/FAIL SRO PASS/FAIL TOTAL PASS/FAIL Written 0/0 1/0 1/0 Operating Tests 0/0 1/0 1/0 Overall 0/0 1/0 1/0 3. Exit Meeting:
Phillip T. Young, Chief Examiner, NRC Thomas Myers, NIST At the conclusion of the examinations the chief examiner thanked the facility for their support during the examinations.
ENCLOSURE 1
U. S. NUCLEAR REGULATORY COMMISSION NON-POWER INITIAL REACTOR LICENSE EXAMINATION FACILITY: National Institute of Standards and Technology REACTOR TYPE: TEST DATE ADMINISTERED: 10/22/2012 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 brackets for each question. A 70% in each section is required to pass the examination. Examinations will be picked up three (3)
hours after the examination starts.
% of Category % of Candidates Category Value Total Score Value Category 20.00 33.3 A. Reactor Theory, Thermodynamics and Facility Operating Characteristics 20.00 33.3 B. Normal and Emergency Operating Procedures and Radiological Controls 20.00 33.3 C. Facility and Radiation Monitoring Systems 60.00 % TOTALS FINAL GRADE All work done on this examination is my own. I have neither given nor received aid.
______________________________________
Candidate's Signature ENCLOSURE 2
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.
13. When you have completed and turned in you examination, leave the examination area. If you are observed in this area while the examination is still in progress, your license may be denied or revoked.
EQUATION SHEETs
Q ' mcp T ' m H ' UA T (&)2 Pmax '
2(k)R R( ' 1 x 10&4 seconds eff ' 0.1 seconds &1 S S SCR ' .
& 1&K eff CR1(1&K eff ) ' CR2(1&Keff )
1 2 CR1(& 1) ' CR2(&2)
eff SUR ' 26.06
&
1&K eff M ' 0 1&K eff
1 CR 1 M ' '
1&K eff CR 2 P ' P0 10SUR(t)
t
P ' P0 e(1&)
P ' P0
&
(1&Keff)
SDM '
Section A Reactor Theory, Thermo, and Facility Characteristic
EQUATION SHEETs
R(
'
&
R( &
' %
' 2 1 keff xKeff 1 2 0.693 T1/2 '
(K eff&1)
'
Keff DR 'DR0 e &t DR ' 6CiE(n)
R2 DR 1d12 ' DR2d22 (2&)2 (1&)2
'
Peak2 Peak1
EQUATION SHEETs
DR - Rem, Ci - curies, E - Mev, R - feet 1 Curie = 3.7 x 1010 dis/sec 1 kg = 2.21 lbm
1 Horsepower = 2.54 x 10 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
Section A Reactor Theory, Thermo, and Facility Characteristic Question: A.001 [1.0 point] (1.0)
A thin foil target of 10% aluminum atoms and 90% copper atoms is placed into a thermal neutron beam. Given s = 1.49 and a = 0.23 for aluminum and s = 7.9 and a = 3.79 for copper, determine the reaction with the highest probability. A neutron a. scattering reaction with aluminum b. scattering reaction with copper c. absorption in aluminum d. absorption in copper Answer: A.001 b.
Reference: Standard NRC Reactor Theory Question Question: A.002 [1.0 point] (2.0)
A reactor scram has resulted in the instantaneous insertion of .003 K/K of negative reactivity.
Which ONE of the following is the stable negative reactor period resulting from the scram?
a. 45 seconds b. 56 seconds c. 80 seconds d. 112 seconds Answer: A.002 c Reference: Lamarsh, J.R., Introduction to Nuclear Engineering, Addison-Wesley Publishing, Reading, Massachusetts, 1983. § 7.1, p. 289 Question: A.003 [1.0 point] (3.0)
Which ONE of the following is true concerning the differences between prompt and delayed neutrons?
a. Prompt neutrons account for less than 1% of the neutron population while delayed neutrons account for approximately 99% of the neutron population.
b. Prompt neutrons are released during fast fissions while delayed neutrons are released during thermal fissions.
c. Prompt neutrons are released during the fission process while delayed neutrons are released during the decay process.
d. Prompt neutrons are the dominating factor in determining the reactor period while delayed neutrons have little effect on the reactor period.
Section A Reactor Theory, Thermo, and Facility Characteristics Answer: A.003 c.
Reference: Intro to Nuc Eng, John R. Lamarsh © 1983, § 3.7 pp. 73 - 75.
Section A Reactor Theory, Thermo, and Facility Characteristic Question: A.04 [1.0 point] (4.0)
Which condition below describes a critical reactor?
a. K = 1, K/K = 1 b. K = 1, K/K = 0 c. K = 0, K/K = 1 d. K = 0, K/K = 0 Answer: A.004 b.
Reference: Intro to Nuc Eng, John R. Lamarsh © 1983, § 7.1, p. 282.
Question: A.005 [1.0 point] (5.0)
The reactor is shutdown by 0.05 K/K, this would correspond to Keff of:
a. 0.9995.
b. 0.9524.
c. 0.7750.
d. 0.0500.
Answer: A.005 b.
Reference: Lamarsh, J.R., Introduction to Nuclear Engineering, Addison-Wesley Publishing, Reading, Massachusetts, 1983. § 4,1, p. 102 & § 7.1, p. 282. p=(k-1)/k; p= -0.05; -0.05k = k-1; 1 = k-(-0.05k) = k(1+0.05); k=1/1.05; k=0.9524 Question: A.006 [1.0 point] (6.0)
Which statement best describes Xe-135 behavior following a Reactor Scram?
a. Xenon concentration decreases due to production rate from fission stops.
b. Xenon concentration decreases due to production rate from I-135 decay increasing.
c. Xenon concentration increases due to production rate from Pm-149 increasing.
d. Xenon concentration increases due to I-135 decay exceeding Xe-135 decay.
Answer: A.006 d.
Reference: Standard NRC Reactor Theory Question
Section A Reactor Theory, Thermo, and Facility Characteristics Question: A.007 [1.0 point] (7.0)
An initial count rate of 100 is doubled five times during startup. Assuming an initial Keff = 0.950, what is the new Keff?
a. 0.957 b. 0.979 c. 0.988 d. 0.998 Answer: A.007 d.
Reference: CR1/CR2 = (1 - Keff2)/(1 - Keff1) 1/32 (1 - 0.95) = 1 - Keff2 1 - 0.05/32 = Keff2 Keff2 = 0.9984 Question: A.008 [1.0 point] (8.0)
Keff is K times the a. fast fission factor ()
b. reproduction factor ()
c. total non-leakage factor (f x th)
d. resonance escape probability (p)
Answer: A.0008 c.
Reference: Standard NRC Question1 Question: A.009 [1.0 point] (9.0)
Which ONE of the following is the reason for an installed neutron source within the reactor? A startup without a neutron source a. is impossible as there would be no neutrons available to start the fission process.
b. would be very slow due to the long time to build up neutron population from so low a level.
c. could result in a very short period due to the reactor going critical before neutron population can build up high enough to be read on nuclear instrumentation.
d. can be compensated for by adjusting the compensating voltage on the source range detector.
Answer: A.009 c.
Reference: Standard NRC Reactor Theory
Section A Reactor Theory, Thermo, and Facility Characteristic Section A Reactor Theory, Thermo, and Facility Characteristics Question: A.010 [1.0 point] (10.0)
Which ONE of the following describes "EXCESS REACTIVITY"?
a. Extra reactivity into the core due to the presence of the source neutrons.
b. A measure of the resultant reactivity if all of the control elements were withdrawn.
c. The combined reactivity worth of control rods and other poisons needed to keep the reactor shutdown.
d. The maximum reactivity insertion with the reactor shutdown with control rods fully inserted under peak Xenon conditions.
Answer: A.010 b.
Reference: Standard NRC Reactor Theory Question Question: A.011 [1.0 point] (11.0)
Which ONE of the following is an example of beta () decay?
87 83 a. 35Br > 33As 87 86 b. 35Br > 35Br 87 86 c. 35Br > 34Se 87 87 d. 35Br > 36Kr Answer: A.011 d.
Reference: Standard NRC Reactor Theory Question, Chart of the Nuclides Question: A.012 [1.0 point] (12.0)
If reactor power is increasing by a decade every minute, it has a period of:
a. 13 sec b. 26 sec c. 52 sec d. 65 sec Answer: A.012 b.
Reference: Glasstone, S. and Sesonske, A, Nuclear Reactor Engineering, Kreiger Publishing, Malabar, Florida, 1991, § 5.18, p. 234.
Section A Reactor Theory, Thermo, and Facility Characteristic Question: A.013 [1.0 point] (13.0)
Which ONE of the following conditions would increase shutdown margin?
a. An experiment which added positive reactivity.
b. Depletion of the burnable poison added to the uranium fuel.
c. Depletion of uranium fuel.
d. Decreasing fuel temperature.
Answer: A.013 c.
Reference: Adding negative reactivity increases the shutdown margin.
Question: A.014 [1.0 point] (14.0)
Which ONE of the following statements describes the difference between Differential (DRW)
and Integral (IRW) rod worth curves?
a. DRW relates the worth of the rod per increment of movement to rod position. IRW relates the total reactivity added by the rod to the rod position.
b. DRW relates the time rate of reactivity change to rod position. IRW relates the total reactivity in the core to the time rate of reactivity change.
c. IRW relates the worth of the rod per increment of movement to rod position. DRW relates the total reactivity added by the rod to the rod position.
d. IRW is the slope of the DRW at a given rod position Answer: A.014 a.
Reference: Lamarsh, Introduction to Nuclear Engineering, 1975, Page 270 Question: A.015 [1.0 point] (15.0)
The fuel temperature coefficient of reactivity is -1.25x10-4 K/K/°C. When a control rod with an average rod worth of 0.1 % K/K/inch is withdrawn 10 inches, reactor power increases and becomes stable at a higher level. At this point, the fuel temperature has:
a. increased by 80°C b. decreased by 80°C c. increased by 8°C d. decreased by 8°C Answer: A.015 a.
Reference: Lamarsh, Introduction to Nuclear Engineering, 2nd Edition, Page 306 Reactivity added by control rod = +(0.001 k/k/inch)(10 inches) = 0.01 k/k.
Section A Reactor Theory, Thermo, and Facility Characteristics Fuel temperature change = -Reactivity added by rod / fuel temperature coefficient Fuel temperature change = (-0.01 k/k) / (-1.25x10-4 k/k/ C) = 80 C.
Section A Reactor Theory, Thermo, and Facility Characteristic Question: A.016 [1.0 point] (16.0)
Which one of the following characteristics of a material would result in the most efficient thermalization of neutrons?
a. LOW atomic mass number and HIGH scattering cross section.
b. HIGH atomic mass number and LOW scattering cross section.
c. LOW neutron absorption and LOW scattering cross section.
d. LOW neutron absorption and HIGH atomic mass number.
Answer: A.016 a.
Reference: Intro to Nuc Eng, John R. Lamarsh © 1983, § 3.5, pp. 59-60.
Question: A.017 [1.0 point] (17.0)
Which factor in the six factor formula is represented by the ratio:
number of neutrons that reach thermal energy number of neutrons that start to slow down a. fast non-leakage probability (Lf)
b. resonance escape probability (p)
c. reproduction factor ()
d. thermal utilization factor (f)
Answer: A.017 b.
Reference: Intro to Nuc Eng, John R. Lamarsh © 1983, § 6.5 p. 239.
Question: A.018 [1.0 point] (18.0)
In a reactor at full power, the thermal neutron flux ( ) is 2.5 x 1012 neutrons/cm2/sec., and the macroscopic fission cross-section f is 0.1 cm-1. The fission rate is:
a. 2.5 x 1011 fissions/cm/sec.
b. 2.5 x 1013 fissions/cm/sec.
c. 2.5 x 1011 fissions/cm3/sec.
d. 2.5 x 1013 fissions/cm3/sec.
Answer: A. 18 c.
Reference: Standard EQB question. R = f = (2.5 x 1012) x 0.1 = 2.5 x 1011
Section A Reactor Theory, Thermo, and Facility Characteristics Question: A.019 [1.0 point] (19.0)
The term "Prompt Critical" refers to:
a. the instantaneous jump in power due to a rod withdrawal b. a reactor which is supercritical using only prompt neutrons c. a reactor which is critical using both prompt and delayed neutrons d. a reactivity insertion which is less than eff Answer: A.019 b.
Reference: Lamarsh, Introduction to Nuclear Engineering, 1975, Page 250 Question: A.020 [1.0 point] (20.0)
Which ONE of the following describes the difference between reflectors and moderators?
a. Reflectors decrease core leakage while moderators thermalize neutrons b. Reflectors shield against neutrons while moderators decrease core leakage c. Reflectors decrease thermal leakage while moderators decrease fast leakage d. Reflectors thermalize neutrons while moderators decrease core leakage Answer: A.020 a.
Reference: Lamarsh, Introduction to Nuclear Engineering, 1975, Pages 57, 214
Section B Normal/Emergency Procedures & Radiological Controls Question: B.001 [1.0 point, 0.25 each] (1.0)
Identify each of the following Technical Specification Requirements as being either a Limiting Safety System Setting (LSSS) or a Limiting Condition for Operation (LCO).
a. Minimum Coolant Flow (outer plenum) 235 gpm/MW b. reactivity insertion rate for all four shim safety arms, does not exceed 5.0 x 10-4 /sec.
c. D2 concentration in the helium sweep system of greater than 4%.
d. Maximum Reactor power 130%
Answer: B.001 a. = LSSS; b. = LCO; c. = LCO; d. = LSSS Reference: Tech Specs, 2.2 1st and 4th spec, 3.2.1. (3) spec and 3.3.1. (2) spec.
Question: B.002 [1.0 point, 0.333 each] (2.0)
Match each of the Technical Specification Limits in column A with its corresponding value in column B.
(Each limit has only one answer, values in Column B may be used more once, more than once or not at all.)
Column A Column B a. Absolute worth of any individual experiment 15%
b. Maximum Core Excess Reactivity 4.0%
c. The sum of the absolute Value of all experiments 2.6%
1.0%
0.5%
Answer: B.002 a. = 0.5% ; b. = 15% ; c. = 2.6%
Reference: Technical Specifications § 3.1.2 (1) and 3.8.1 (1) and 3.8.1 (2)
Question: B.003 [1.0 point] (3.0)
A radiation survey instrument was used to measure an irradiated experiment. The results were 100 mrem/hr with the window open and 60 mrem/hr with the window closed. What was the beta dose?
a. 40 mrem/hr b. 60 mrem/hr c. 100 mrem/hr d. 140 mrem/hr Answer: B.003 a.
Reference: Instrument reads only dose with window closed. Instrument reads both and dose with window open. Therefore, dose is window open dose less window closed dose.
Section B Normal/Emergency Procedures & Radiological Controls Question: B.004 [1.0 point] (4.0)
Which ONE of the following statements correctly defines the term "Channel Test?"
a. The introduction of a signal into a channel and observation of the proper channel response.
b. The qualitative verification of acceptable performance by observation of channel behavior.
c. An arrangement of sensors, components and modules as required to provide a single trip or other output signal relating to a reactor or system operating parameter.
d. The adjustment of a channel such that its output corresponds with acceptable accuracy to known values of the parameter which the channel measures.
Answer: B.004 a.
Reference: TS, § 1.3.2.3 Question: B.005 [1.0 point, 0.25 each] (5.0)
Match the allowable voluntary radiation exposure limit authorized during an emergency listed in column B with the correct condition from column A.
Column A Column B a. Lifesaving; without approval of Emergency Director 5 REM b. Other Serious Events; without approval of Emergency Director 10 REM c. Lifesaving; with approval of Emergency Director 25 REM d. Other Serious Events; with approval of Emergency Director 50 REM 100 REM Answer B.005 a. = 25; b. = 5; c. = 100; d. = 25 Reference: Emergency Instruction 3.6, Essential Personnel Evacuation, IV. Voluntary Exposure Limits
Section B Normal/Emergency Procedures & Radiological Controls Question: B.006 [1.0 point] (6.0)
Per 10CFR55.53, an SRO who has not maintained active status must have an authorized representative of the facility licensee certify the following:
a. a minimum of six hours of shift functions under the direction of an operator or senior operator as appropriate and in the position to which the individual will be assigned has been completed.
b. a minimum of four hours of shift functions under the direction of an operator or senior operator as appropriate and in the position to which the individual will be assigned has been completed.
c. a minimum of six hours of shift functions under the direction of an operator or senior operator as appropriate and in the position to which the individual will be assigned has been completed and, that in part, the individual is current in all of the facility requalification program requirements.
d. a minimum of four hours of shift functions under the direction of an operator or senior operator as appropriate and in the position to which the individual will be assigned has been completed and, that in part, the individual has completed a requalification program written examination and operating test within the current calendar quarter.
Answer: B.006 c.
Reference: 10CFR55.53 and 10CFR55.59 Question: B.007 [1.0 point] (7.0)
During shipment of spent fuel, the truck door was closed whenever time was spent loading baskets in the pool. The truck door was closed to......
a. safeguard the fuel.
b. establish confinement integrity.
c. limit the spread of contamination.
d. prevent an unauthorized entry point.
Answer: B.007 b.
Reference: TS, § 3.4.2 NBSR Reactor Operations Training Guide 8.1 Reactor Building And Confinement System
Section B Normal/Emergency Procedures & Radiological Controls Question: B.008 [1.0 point] (8.0)
A gamma source reads 125 mR/hr @ 1 foot. How far from the source must you post a barrier for a radiation area?
a. 35 feet b. 25 feet c. 15 feet d. 5 feet Answer: B.008 d.
Reference: Af = A0 (d0/df)2 => df2 = A0/Af x d02 = 125/5 x 12 = 25 d0 =5 Question: B.009 [1.0 point] (9.0)
Which ONE of the following is the LOWEST level of NIST management who may authorize reactor startup (to previous shim position) following a scram, where the cause of the scram remains unknown?
a. Reactor Operator b. Senior Reactor Operator c. Reactor Supervisor d. Deputy Chief Engineer Answer: B.009 b.
Reference: O.I. 1.1B (Checklist B) step I.B.
Question: B.010 [1.0 point] (10.0)
According to Emergency Instructions, which one of the following lists the two individuals (by title) who may serve as Emergency Director until relieved by higher authority?
a. Reactor Supervisor, or in his absence the Reactor Operator on the console b. Reactor Supervisor, or in his absence the Senior Reactor Operator.
c. Deputy Chief Engineer, or in his absence the Reactor Supervisor d. Deputy Chief Engineer, or in his absence the Senior Reactor Operator Answer: B.010 a.
Reference: E.I. Figure 6.1 NBSR Emergency And Support Organizations
Section B Normal/Emergency Procedures & Radiological Controls Question: B.011 [1.0 point, 0.25 point each] (11.0)
For Research and Test reactors we primarily worry about two isotopes N16 and Ar41. Identify the approximate half-life and gamma energy for each. (Each item has only one answer.)
Isotope Radiological Parameters a. Ar41 half-life 1) 1.8 sec 2) 1.8 min 3) 1.8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> 4) 1.8 day b. Ar41 gamma energy 1) 10 KeV 2) 100 KeV 3) 1 MeV 4) 10 MeV
c. N half-life 1) 7 sec 2) 7 min 3) 7 hour8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> 4) 7 day
d. N gamma energy 1) 6 kev 2) 60 keV 3) 600 keV 4) 6 Mev Answer: B.011 a. = 3; b. = 3; c. = 1; d. = 4 Reference: Standard NRC Rad Question Question: B.012 [1.0 point] (12.0)
You use a Geiger-Müller detector at the same distance from two point sources having the same curie strength. Source As gammas have an energy of 1.0 MeV, while Source Bs gammas have an energy of 2.0 MeV. Which ONE of the following would you expect for the readings due to each source?
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. Both readings are the same.
d. The reading from source B is half that of source A.
Answer: B.012 c.
Reference: Geiger-Müller detector output is independent of incident energy.
Question: B.013 [1.0 point] (13.0)
According to the Administrative Rules, the MINIMUM number of nuclear instruments required for refueling is a. one on-scale instrument with trip safety function b. two on-scale instruments with trip safety function c. one on-scale instrument d. two on-scale instruments Answer: B.013 d.
Reference: Administrative Rule 3.0, § III.A, also Administrative Rule 6.0 § I.B.
Section B Normal/Emergency Procedures & Radiological Controls Question: B.014 [1.0 point] (14.0)
Which ONE of the following is the definition for Annual Limit on Intake (ALI)? A 10CFR20 derived limit based on a. the concentration of a radio-nuclide in air which, if inhaled by an adult worker for a year, results in a total effective dose equivalent of 100 millirem.
b. a Committed Effective Dose Equivalent of 5 Rems whole body or 50 Rems to any individual organ, for the amount of radioactive material inhaled or ingested in a year by an adult worker.
c. the effluent concentration of a radio-nuclide in air which, if inhaled continuously over a year, would result in a total effective dose equivalent of 50 millirem for noble gases.
d. projected dose commitment values to individuals, that warrant protective action following a release of radioactive material.
Answer: B.014 b.
Reference: 10CFR20 Question: B.015 [1.0 point] (15.0)
Which ONE of the following correctly completes the sentence. While the reactor is OPERATING, the process test switch may be placed in the "2 of 2" position a. for not longer than 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> to allow the checking of a channel's operability.
b. indefinitely if power is reduced below 10 MW before changing the selector's position.
c. up to a maximum of 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> if no experiments are inserted into the reactor.
d. while maintaining a steady power level but must be returned to the "1 of 2" position prior to changing power.
Answer: B.015 a.
Reference: Operation Instructions Manual, O.I. 5.7. "Operation of the Process Instrumentation Safety System", Page 2 of 3 Question: B.016 [1.0 point] (16.0)
While operating one of the shim arms falls to its lower stop. Per Annunciator Procedure 0.4 Stuck or Faulty Operation of Shim Arms you should a. maintain the reactor as is (subcritical) until Reactor Supervisor directs corrective action.
b. continue to operate if able to latch and shim out the fallen shim arm.
c. continue to operate using the remaining shim arms to stay critical.
d. shutdown the reactor.
Answer: B.016 d.
Reference: Annunciator Procedures, A.P. 0.4.
Section B Normal/Emergency Procedures & Radiological Controls Question: B.017 [1.0 point] (17.0)
The fission products monitor located in the helium sweep gas will give an indication of a . ?
a. A pin-hole breach in the cladding.
b. Activation of argon in air from the reactor.
c. Disassociation of water and nitrogen 16 production.
d. Activation of aluminum from reactor and primary piping materials.
Answer: B.017 a.
Reference: TS 3.7.1 Monitoring Systems and Effluent Limits Question: B.018 [1.0 point] (18.0)
10CFR50.54(x) states: A licensee may take reasonable action that departs from a license condition or a technical specification (contained in a license issued under this part) in an emergency when this action is immediately needed to protect the public health and safety and no action consistent with license conditions and technical specifications that can provide adequate or equivalent protection is immediately apparent. 10CFR50.54(y) state that this may be authorized by a senior operator. Per the note in the front of the Operating Instructions, the minimum level of management who may authorize a deviation from the Operating Instructions is a. a licensed SRO b. the Reactor Supervisor c. the Chief of Reactor Operations d. the highest level of management available at the time.
Answer: B.018 d.
Reference: Note in the front of the Operating Instructions Question: B.019 [1.0 point] (19.0)
The total exposure from effluents from the reactor facility to a person at the site boundary shall not exceed a. 100 mrem per 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period b. 100 mrem per calendar year c. 500 mrem per 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period d. 500 mrem per calendar year Answer: B.019 b.
Reference: TS 3.7.2 Effluents
Section B Normal/Emergency Procedures & Radiological Controls Question: B.020 [1.0 point] (20.0)
During Reactor Startup, per SOP 0.1, the minimum allowable period allowed is a. 10 seconds b. 20 seconds c. 30 seconds d. 56 seconds Answer: B.020 b.
Reference: Standard Operating Instructions O.I.1.1, Reactor Startup: § II.C.
Section C Facility and Radiation Monitoring Systems Question: C.001 [1.0 point] (1.0)
Which ONE of the following is the material used as a neutron poison in the Regulating Rod?
a. Erbium b. Cadmium c. Aluminum d. Boron Answer: C.001 c.
Reference: NBSR Reactor Operations Training Guide, § 1.1.5 2nd ¶.
Question: C.002 [1.0 point, 0.25 points each] (2.0)
Identify the valves listed below as either Motor Operated (MO)or Air Operated (AO).
a. DWV-1 Inner Plenum Flow Control (D2O Main Cooling System)
b. DWV-2 Outer Plenum Flow Control (D2O Main Cooling System)
c. DWV-40 D2O supply to Emergency Tank (D2O Auxiliary System)
d. DWV-19 Isolation between Core and Main Pump Piping (D2O Main Cooling System)
Answer: C.002 a. = MO; b. = MO; c. = AO; d. = MO Reference: NBSR Operations Training Guide, § 2.2.4 and Drawing 2.1 Question: C.003 [1.0 point] (3.0)
Question deleted from examination - changes to facility resulted in no correct answer to the question.
WHICH ONE of the following correctly describes the lineup of Secondary Valves 1, 2 and 3?
a. SCV 1 & 2 supply suction to pumps 4, 5 and 6, SCV 3 supplies suction to pumps 1, 2 and 3.
b. SCV 2 & 3 supply suction to pumps 4, 5 and 6, SCV 1 supplies suction to pumps 1, 2 and 3.
c. SCV 1 & 2 supply suction to pumps 1, 2 and 3, SCV 3 supplies suction to pumps 4, 5 and 6.
d. SCV 2 & 3 supply suction to pumps 4, 5 and 6, SCV 1 supplies suction to pumps 1, 2 and 3.
Answer: C.003 a.
Reference: NBSR Operations Training Guide, Figure 3.1.
Section C Facility and Radiation Monitoring Systems Question: C.004 [1.0 point] (4.0)
During a reactor startup, the 123 Strainer Inlet Isolation valve SCV-200 is inadvertently left closed. As the startup progresses, the reactor receives a rundown signal, the signal was due to a. low secondary flow b. low thermal shield flow c. high inlet temperature d. high outlet temperature Answer: C.004 d.
Reference: NIST SAR Sections 5.2.2.7.1 Strainer & 5.2.4.1 Removal of Heat from the Fuel Question: C.005 [1.0 point] (5.0)
Which ONE of the following correctly describes where Critical Panel 1 (CP-1) receives power from?
a. Directly from MCCA-7 b. Directly from the 20 kVA uninterruptible power supplies (UPS)
c. Directly from either Scott Transformer T9 or T10.
d. Directly from the battery Answer: C.005 c.
Reference: NBSR Reactor Operations Training Guide, § 5.0 NBSR Electrical Systems Question: C.006 [1.0 point] (6.0)
Reactor level is increasing above 168 inches. Which ONE of the following is the AUTOMATIC reactor scram which will occur?
a. High reactor D2O level.
b. High flux on NC-6, NC-7 or NC-8.
c. Low reactor D2O level.
d. High Reactor T Answer: C.006 c.
Reference: Annunicator Procedure AN.3.1 Hi Reactor D2O level
Section C Facility and Radiation Monitoring Systems Question: C.007 [1.0 point] (7.0)
Which ONE of the following is the actual method that negative building pressure is maintained following a containment building isolation and normal ventilation shutdown due to high radiation? (Assume AC power is available, no operator action, and the containment building pressure is being maintained by the emergency exhaust system.)
a. automatic fan cycling on and off to maintain a pressure of -0.25".
b. manual fan cycling on and off to maintain a pressure of -0.25".
c. automatic fan cycling on and off to maintain a pressure of -0.1".
d. manual fan cycling on and off to maintain a pressure of -0.1".
Answer: C.007 a.
Reference: NBSR Training Guide, § 4.10.3, Ventilation System Under accident conditions.
Question: C.008 [1.0 point, 0.25 each] (8.0)
Match the Storage Pool cooling system components with their primary responsibiities.
a. Suspended Solids 1. Pre and Post Filters b. Dissolved Solids 2. Ultraviolet Treatment Unit c. Kill Biological Impurities 3. Collection Basin d. Floating Detritus (Mosquito Larvae, dust etc.) 4. HOH Ion Exchanger Answer: C.008 a. = 1; b. = 4; c. = 2; d. = 3 Reference: NBSR Training Guide, figure 4.10.
Question: C.009 [1.0 point] (9.0)
What type of detector does the T channel use?
a. Ion chamber b. Geiger Counter c. Scintillation Detector d. Proportional Counter Answer: C.009 a.
Reference: NBSR Training Guide, § 6.4.7.
Section C Facility and Radiation Monitoring Systems Question: C.010 [1.0 point] (10.0)
In order to detect neutrons the Nuclear Instrumentation ion chambers are coated with 96% enriched a. Be10 b. Be11 c. B10 d. B11 Answer: C.010 c.
Reference: NBSR Training Guide, § 6.2.3 and 6.2.4.
Question: C.011 [1.0 point, 1/4 point each] (11.0)
Using the simplified diagram of the pneumatic tube (rabbit) system provided, identify the position of valves A through D as either OPEN or CLOSED, on a sample INSERTION.
a. A b. B c. C d. D Answer: C.011 a. = Closed; b. = Open; c. = Open; d. = Closed Reference: NBSR Reactor Operations Training Guide, Figure 8.3 Question: C.012 [1.0 point] (12.0)
Which ONE of the following is the gas used to move the samples in the Rabbit systems?
a. He b. Air c. CO2 d. N2 Answer: C.012 c.
Reference: NBSR Operations Training Guide, § 8.2.5
Section C Facility and Radiation Monitoring Systems Question: C.013 [1.0 point] (13.0)
Which ONE of the following is the purpose of the Bismuth shield within the Thermal Column? Reduce
_____ within the graphite region of the thermal column.
a. gamma radiation intensity b. Intermediate neutron flux c. Fast neutron flux d. Thermal neutron flux Answer: C.013 a.
Reference: NBSR Operations Training Guide, § 8.2.4.
Question: C.014 [1.0 point] (14.0)
Which ONE of the following core components bear all impact loads associated with the safety- shims?
a. Thermal Shield b. Upper grid plate c. Biological Shield d. Lower grid plate Answer: C.014 c.
Reference: NBSR Operations Training Guide, § 1.3.5 Question: C.015 [1.0 point] (15.0)
Question deleted from examination - changes to facility resulted in no correct answer to the question.
If a Secondary cooling pump trips off due to an overload, prior to restarting you must a. place the control room switch to off to reset the pump electrically.
b. place the control room switch to the on position (the pump resets itself electrically).
c. have an auxiliary operator push a reset button on the controller locally at the pump.
d. have an auxiliary operator take the local, auto switch to local to reset the pump, then return the switch to auto.
Answer: C.015 a.
Reference: NBSR Training Manual, § 3.2.1.
Section C Facility and Radiation Monitoring Systems Question: C.016 [1.0 point] (16.0)
How long is the D2O system designed to provide cooling on a once-through basis?
a. 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> b. 1.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> c. 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> d. 2.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> Answer: C.016 d.
Reference: TS 3.3.2 Emergency Core Cooling Question: C.017 [1.0 point] (17.0)
How much negative reactivity does the moderator dump provide?
a. The most reactive shim arms fully withdrawn.
b. Two shims arms fully withdrawn.
c. Three shims arms fully withdrawn and the regulating rod fully withdrawn.
d. All four shims arms fully withdrawn.
Answer: C.017 d.
Reference: TS 3.3.3 Moderator Dump System Question: C.018 [1.0 point] (18.0)
The emergency exhaust system is designed to pass reactor building effluents through high-efficiency particulate filters capable of removing particles of ____ m or greater with an efficiency of at least 99%
and the charcoal filters are capable of removing greater than ____ of the Iodine from the air.
a. 0.3 m 99%
b. 0.1 m 98%
c. 0.2 m 95%
d. 0.5 m 96%
Answer: C.018 a.
Reference: TS 3.5 Ventilation System
Section C Facility and Radiation Monitoring Systems Question: C.019 [1.0 point] (19.0)
The purpose of the fuel element latching bar is to prevent an element from lifting out of the lower grid plate resulting in a. A reduction in flow to the element.
b. Changes in the neutron flux to experiments.
c. Restrictions that could prevent a shim arm from operating.
d. Changes to the radial and axial flux pattern that could damage the fuel.
Answer: C.019 a.
Reference: TS 3.9.2 Fuel Handling Question: C.020 [1.0 point] (20.0)
With tritium concentrations of greater than 4 Ci/l, how often is the primary water required to be sampled?
a. Annually b. Semi-annually c. Quarterly d. Monthly Answer: C.020 c.
Reference: TS 4.7 Radiation Monitoring System and Effluents