ML18248A053
| ML18248A053 | |
| Person / Time | |
|---|---|
| Site: | Reed College |
| Issue date: | 08/30/2018 |
| From: | Anthony Mendiola Research and Test Reactors Oversight Projects Branch |
| To: | Krahenbuhl M Reed College |
| Randiki C | |
| Shared Package | |
| ML18170A084 | List: |
| References | |
| 50-288/OL-18-03 | |
| Download: ML18248A053 (25) | |
Text
August 30, 2018 Dr. Melinda Krahenbuhl, Director Reed Reactor Facility 3203 SE Woodstock Blvd.
Portland, OR 97202
SUBJECT:
EXAMINATION REPORT NO. 50-288/OL-18-03, REED COLLEGE
Dear Dr. Krahenbuhl:
During the week of June 25, 2018, the U.S. Nuclear Regulatory Commission (NRC) administered an operator licensing examination at your Reed College research 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 Ms. Michele DeSouza at (301) 415-0747 or via internet e-mail Michele.DeSouza@nrc.gov.
Sincerely,
/RA/
Anthony J. Mendiola, Chief Research and Test Reactors Oversight Branch Division of Licensing Projects Office of Nuclear Reactor Regulation Docket No. 50-288
Enclosures:
- 1. Examination Report No. 50-288/OL-18-03
- 2. Written examination cc: w/o enclosures: See next page
ML18248A053 *via E-mail NRR-079 OFFICE NRR/DLP/PROB/CE* NRR/DLP/IOLB/OLA NRR/DLP/PROB/BC NAME MDeSouza CJRandiki AMendiola DATE 08/28/2018 08/29/2018 08/30/2018 Reed College Docket No. 50-288 cc:
Mayor of the City of Portland 1220 Southwest 5th Avenue Portland, OR 97204 Dr. Nigel Nicholson, Dean of Faculty Reed College 3203 SE Woodstock Boulevard Portland, OR 97202-8199 John Kroger, President Reed College 3203 SE Woodstock Boulevard Portland, OR 97202-8 Ken Niles, Assistant Director for Nuclear Safety Oregon Department of Energy 550 Capitol Street N.E., 1st Floor Salem, OR 97301 Program Director Radiation Protection Services Public Health Division Oregon Health Authority 800 NE Oregon Street, Suite 640 Portland, OR 97232-2162 Test, Research and Training Reactor Newsletter P.O. Box 118300 University of Florida Gainesville, FL 32611
U.S. NUCLEAR REGULATORY COMMISSION OPERATOR LICENSING INITIAL EXAMINATION REPORT REPORT NO.: 50-288/OL-18-03 FACILITY DOCKET NO.: 50-288 FACILITY LICENSE NO.: R-112 FACILITY: Reed Research Reactor EXAMINATION DATES: June 25-26, 2018 SUBMITTED BY: /RA/ 08/08/2018 Michele DeSouza, Chief Examiner Date
SUMMARY
During the week of June 25, 2018, the NRC administered an operator licensing retake examination to two Reactor Operator (RO) candidates. The two RO candidates passed all applicable portions of the examination.
REPORT DETAILS
- 1. Examiner: Michele DeSouza, Chief Examiner, NRC
- 2. Results:
RO PASS/FAIL SRO PASS/FAIL TOTAL PASS/FAIL Written 2/0 0/0 2/0 Operating Tests 0/0 0/0 0/0 Overall 2/0 0/0 2/0
- 3. Exit Meeting:
Michele C. DeSouza, Chief Examiner, NRC Ilana Novakoski, Operations Supervisor, Reed College Melinda Krahenbuhl, Director, Reed College Per discussion with the facility, prior to administration of the examination, adjustments were accepted. Upon completion of the examination, the NRC Examiner met with facility staff representatives to discuss the results. At the conclusion of the meeting, the NRC examiner thanked the facility for their support in the administration of the examination.
ENCLOSURE 1
U.S. NUCLEAR REGULATORY COMMISSION NON-POWER REACTOR LICENSE EXAMINATION FACILITY: Reed Research Reactor REACTOR TYPE: TRIGA DATE ADMINISTERED: 06/25/2018 CANDIDATE: _______________________
INSTRUCTIONS TO CANDIDATE:
Answers are to be written on the Answer sheet provided. Attach all Answer sheets to the examination. Point values are indicated in parentheses for each question. A 70% in each category is required to pass the examination. Examinations will be picked up three (3) hours after the examination starts.
% OF CATEGORY % OF CANDIDATE'S CATEGORY VALUE TOTAL SCORE VALUE CATEGORY 20.00 33.3 A. REACTOR THEORY, THERMODYNAMICS AND FACILITY OPERATING CHARACTERISTICS 20.00 33.3 B. NORMAL AND EMERGENCY OPERATING PROCEDURES AND RADIOLOGICAL CONTROLS 20.00 33.3 C. FACILITY AND RADIATION MONITORING SYSTEMS 60.00 % TOTALS FINAL GRADE All work done on this examination is my own. I have neither given nor received aid.
Candidate's Signature ENCLOSURE 2
Category A - Reactor Theory, Thermodynamics, & Facility Operating Characteristics ANSWER SHEET 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 ___ (0.25 each)
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 ___
A19 a b c d ___
A20 a b c d ___
(***** END OF CATEGORY A *****)
Category B - Normal/Emergency Operating Procedures and Radiological Controls ANSWER SHEET Multiple Choice (Circle or X your choice)
If you change your Answer, write your selection in the blank.
B01 a b c d ___
B02 a b c d ___
B03 a b c d ___
B04 a___ b ___ c ___ d ___
B05 a b c d ___
B06 a b c d ___
B07 a b c d ___
B08 a b c d ___
B09 a b c d ___
B10 a b c d ___
B11 a b c d ___
B12 a b c d ___
B13 a b c d ___
B14 a b c d ___
B15 a b c d ___
B16 a b c d ___
B17 a b c d ___
B18 a b c d ___
B19 a b c d ___
B20 a b c d ___
(***** END OF CATEGORY B *****)
(********** 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
( )2 eff = 0.1sec 1 Q&= m&cP T = m&H =UAT Pmax =
(2 )
t P = P0 e S S SCR = * =1x104 sec 1 K eff eff + &
SUR = 26 .06
( ) (
CR1 1 K eff1 = CR2 1 K eff 2 ) CR1 ( 1 ) = CR2 ( 2 )
(1 ) M=
1
= 2 CR P = P0 10SUR(t )
P= P0 1 K eff CR1 1 K eff1 1 K eff
- M= SDM = =
1 K eff 2 K eff
- 0.693 K eff 2 K eff1
+ T1 =
eff + & 2 K eff1 K eff 2 K eff 1
= DR = DR0 e t 2 DR1 d1 = DR2 d 2 2
K eff 6 Ci E (n) ( 2 )2 = (1 )2 DR =
R2 Peak2 Peak1 DR - Rem, Ci - curies, E - Mev, R - feet 1 Curie = 3.7 x 1010 dis/sec 1 kg = 2.21 lb 1 Horsepower = 2.54 x 103 BTU/hr 1 Mw = 3.41 x 106 BTU/hr 1 BTU = 778 ft-lb °F = 9/5 °C + 32 1 gal (H2O) 8 lb °C = 5/9 (°F - 32) cP = 1.0 BTU/hr/lb/°F cp = 1 cal/sec/gm/°C
Category A: Reactor Theory, Thermodynamics, and Facility Operating Characteristics QUESTION A.01 [1.0 point]
What is ?
- a. The fractional change in neutron population per generation
- b. The fraction of all fission neutrons that are born as delayed neutrons
- c. The time required for the reactor to change by power by a factor of e
- d. The fraction of all delayed neutrons that reach thermal energy QUESTION A.02 [1.0 point]
Which ONE of the following is the expected stable neutron count rate given a source strength of 300 neutrons per second (N/sec) and a multiplication factor of 0.5?
- a. 150 N/sec
- b. 300 N/sec
- c. 450 N/sec
- d. 600 N/sec QUESTION A.03 [1.0 point]
Which ONE of the following conditions will DECREASE the reactor core excess?
- a. Fuel depletion
- b. Burnable poison burnout
- c. Insertion of a positive reactivity worth experiment
- d. Lowering moderator temperature (assume negative temperature coefficient)
QUESTION A.04 [1.0 point]
What are the two common FISSION PRODUCTS that have especially large neutron cross sections and play a significant role in reactor physics?
- a. Nitrogen-16 and Argon-41
- b. Argon-41 and Cobalt-60
- c. Iodine-131 and Cesium-137
- d. Xenon-135 and Samarium-149
Category A: Reactor Theory, Thermodynamics, and Facility Operating Characteristics QUESTION A.05 [1.0 point]
What is the corresponding Tmod given a moderator temperature INCREASE of 7ºF, the worth of the regulating rod is 0.001k/k/inch, and the regulating rod drives in 3.5 inches to compensate?
- a. 2 x 10-5 k/k/ºF
- b. -2 x 10-5 k/k/ºF
- c. 5 x 10-4 k/k/ºF
- d. -5 x 10-4 k/k/ºF QUESTION A.06 [1.0 point]
Which ONE of the following statements correctly describes the reason for operating a reactor with thermal neutrons instead of fast neutrons?
- a. The fission cross section of the fuel is much higher for fast neutrons than thermal energy neutrons. Since fast neutrons are easier to cause fission, a reactor cannot control with fast neutrons
- b. The neutron lifetime of thermal neutrons is longer than fast neutrons, so the fuel has enough time to capture thermal neutrons
- c. The fission cross section of the fuel is much higher for thermal energy neutrons than fast neutrons, so thermal neutrons are easier to cause fission
- d. The atomic weight of thermal neutrons is larger than fast neutrons, so thermal neutrons are easily to slow down and be captured by the fuel QUESTION A.07 [1.0 point]
Which ONE of the following describes the general shape in determining the integral rod worth of a control rod?
- a. Parabolic shaped, with the maximum at the top and bottom of the core height
- b. S-shaped, with the net change in reactivity from bottom to top
- c. Cosine shaped, with the largest change in the middle of the core height
- d. Exponentially shaped, with the maximum at the bottom of the core height
Category A: Reactor Theory, Thermodynamics, and Facility Operating Characteristics QUESTION A.08 [1.0 point]
Which ONE of the following is a correct statement of how delayed neutrons enhance the ability to control reactor power?
- a. Prompt neutrons can cause fissions in both U-235 and U-238 and delayed neutrons can only cause fissions in U-235
- b. Delayed neutrons increase the average neutron lifetime that allows a reactor to be controlled
- c. The average number of delayed neutrons produced per fission is higher than the average number of prompt neutrons
- d. Delayed neutrons are born at higher energy levels than prompt neutrons QUESTION A.09 [1.0 point]
Which factors of the six factor formula are affected by an INCREASE in core temperature and how are they affected? Lf - Fast non-leakage probability Lt - Thermal non-leakage probability
- Fast fission factor p - Resonance escape probability - Thermal fission factor f - Thermal utilization factor
- a. Lf, p, f
- b. , Lf, Lt, p
- c. , Lf, Lt, p, , f
- d. , Lf, Lt, p, , f QUESTION A.10 [1.0 point, 0.25 each]
Match the following Neutron term in Column A with the appropriate definition in Column B (each used only once)
Column A Column B
- a. Delayed Neutron 1. Neutron born directly from fission
- b. Fast Neutron 2. Neutron in equilibrium with its surroundings
- c. Thermal Neutron 3. Neutron born due to decay of a fission product
- d. Prompt Neutron 4. Neutron at an energy level greater than its surroundings
Category A: Reactor Theory, Thermodynamics, and Facility Operating Characteristics QUESTION A.11 [1.0 point]
Which ONE of the following directly produces 95% of all Xenon in a nuclear reactor?
- a. Fission of U-235
- b. Fission of U-238
- c. Beta decay of Cs-135
- d. Decay of I-135 QUESTION A.12 [1.0 point]
Which ONE of the following is the MAJOR source of heat released after shutdown?
- a. Production of prompt gamma rays
- b. Spontaneous fission of U238
- c. Decay of fission products
- d. Production of delayed neutrons QUESTION A.13 [1.0 point]
A subcritical reactor, keff is increased from 0.924 to 0.987. Which ONE of the following is the amount of reactivity that was added to the core?
- a. 0.034 k/k
- b. 0.069 k/k
- c. 5.53%k/k
- d. 6.53%k/k QUESTION A.14 [1.0 point]
Reactor is critical. What would be the corresponding keff when removing 5% k/k from its criticality?
- a. 0.922
- b. 0.943
- c. 0.952
- d. 0.973
Category A: Reactor Theory, Thermodynamics, and Facility Operating Characteristics QUESTION A.15 [1.0 point]
Which ONE of the following power changes will take the LONGEST time to complete? Assume the reactor is on a CONSTANT positive period.
- a. From 1 W to 5 W
- b. From 10 W to 30 W
- c. From 10 kW to 20 kW
- d. From 100 kW to 150 kW QUESTION A.16 [1.0 point]
Which ONE of the following conditions would INCREASE the shutdown margin of a reactor?
- a. Inserting an experiment adding positive reactivity
- b. Depletion of Uranium fuel
- c. Depletion of a burnable poison
- d. Lowering moderator temperature if the moderator temperature coefficient is negative QUESTION A.17 [1.0 point]
Which ONE of the following best describes the difference between reflectors and moderators?
- a. Reflectors decrease thermal leakage while moderators decrease fast leakage
- b. Reflectors thermalize neutrons while moderators decrease core leakage
- c. Reflectors decrease core leakage while moderators thermalize neutrons
- d. Reflectors shield against neutrons while moderators decrease core leakage QUESTION A.18 [1.0 point]
How high will the reactor power get given the following: the lowest of the reactor high power scram set points is 120%, the scram delay time is 0.5 seconds, the reactor is operating at 100%
power prior to the scram, and the reactor period is positive 20 second?
- a. 113%
- b. 119%
- c. 123%
- d. 125%
Category A: Reactor Theory, Thermodynamics, and Facility Operating Characteristics QUESTION A.19 [1.0 point]
The following shows part of a decay chain for the radioactive element Pb-190:
82Pb 190 83Bi 192 This decay chain is an example of _______ decay.
- a. Alpha
- b. Beta
- c. Gamma
- d. Neutron QUESTION A.20 [1.0 point]
What is the condition of the reactor when k = ? (Note: not eff)
- a. Subcritical
- b. Critical
- c. Super critical
- d. Prompt critical
(***** END OF CATEGORY A *****)
Category B: Normal/Emergency Operating Procedures and Radiological Controls QUESTION B.01 [1.0 point]
Which ONE of the following reactor primary coolant conditions is a violation of Reed Technical Specifications?
- a. Primary coolant conductivity is 4 µS/cm averaged over a month
- b. Pool level is 6 meters above the upper core plate
- c. Primary coolant outlet temperature is 60oC
- d. Primary coolant radioactivity measured quarterly QUESTION B.02 [1.0 point]
In accordance with Reed emergency plan exposure guidelines, which ONE of the following is the exposure and intake limit for life saving and corrective action that mitigates the consequences of the emergency event?
- a. 25 Rem
- b. 30 Rem
- c. 45 Rem
- d. 50 Rem QUESTION B.03 [1.0 point]
Which ONE of the following is the 10CFR20 definition for Derived Air Concentration-hour?
- a. Product of concentration of radioactive material in air and time of exposure in hours, Committed Effective Dose Equivalent of 5 Rems
- b. Effluent concentration of a radionuclide in air which, if inhaled continuously over a year, would result in a Total Effective Dose Equivalent of 50 mrem for noble gases
- c. Projected Committed Effective Dose Equivalent commitment to individuals that warrants protective action following a release of radioactive material
- d. Concentration of a radionuclide in air which, if inhaled by an adult worker for a year, results in a Total Effective Dose Equivalent of 100 mrem
Category B: Normal/Emergency Operating Procedures and Radiological Controls QUESTION B.04 [1.0 point, 0.25 each]
Match the emergency situation listed in Column A with the classification level listed in Column B. (Answers may be used more than once or not at all)
Column A Column B
- a. Tornado 1. Alert
- b. Security event with 15mrem at the site boundary 2. Unusual Event
- c. Reactor facility fire extinguished in 10 minutes 3. No Classification
- d. Security breach of the reactor facility QUESTION B.05 [1.0 point]
Per Reed Technical Specifications, what is the MINIMUM shutdown margin required with the reactor in reference core condition, the most reactive rod fully withdrawn, and experiments in their most reactive state?
- a. $0.50
- b. $1.00
- c. $2.50
- d. $3.00 QUESTION B.06 [1.0 point]
According to the Reed Emergency Plan, who is the on-site Health Physicist during non-emergency situations?
- a. Reed, Training Supervisor
- b. Reactor Operations Manager
- c. Senior Reactor Operator
- d. Reactor Operator QUESTION B.07 [1.0 point]
A radioactive source has a current activity of 3 Curies. The activity 30 years ago was 300 Curies. What is the half-life of the radioactive source?
- a. 4.5 years
- b. 10.5 years
- c. 15 years
- d. 20 years
Category B: Normal/Emergency Operating Procedures and Radiological Controls QUESTION B.08 [1.0 point]
How many hours (MINIMUM) are Test and Research Reactors licensed operators required to perform the functions of a licensed operator to resume activities if a licensee has not been actively performing the functions of a reactor operator or senior reactor operator?
- a. 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />
- b. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />
- c. 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />
- d. 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> QUESTION B.09 [1.0 point, 0.25 each]
Identify each of the following surveillances as a channel check (CHECK), a channel test (TEST),
or a channel calibration (CAL). Write the correct answer on your answer sheet next to the space given for each example listed below.
- a. During performance of the daily checklist, you compare the readings of radiation area monitor one and radiation monitor two
- b. During performance of the daily checklist, you press the scram button to verify a scram on the safety system channel
- c. Adjustment of the wide range monitor channel in accordance with recent data collected during a reactor power calibration
- d. You expose a 2 mCi check source to the continuous air monitor detector to verify that its output is operable QUESTION B.10 [1.0 point]
Reed Technical Specification requires the worth of all single unsecured experiments shall be <
_________ and the worth of all experiments shall be < _________.
- a. $0.25 and $0.50
- b. $0.50 and $1.00
- c. $1.00 and $2.00
- d. No limit and $1.00
Category B: Normal/Emergency Operating Procedures and Radiological Controls QUESTION B.11 [1.0 point]
Which ONE of the following meets the MINIMUM staffing requirement when the reactor is NOT shutdown?
- b. 1 SRO in the control room and Reactor Operations Manager on call
- c. 1 RO in the control room, Reactor Operations Manager on call
- d. 1 SRO in the control room and a second person to summon help QUESTION B.12 [1.0 point]
Calculate an individuals total whole body dose given the individual received the following doses: 20 mrad of alpha, 10 mrad of gamma, and 5 mrad of neutron (unknown energy)
- a. 35 mrem
- b. 415 mrem
- c. 435 mrem
- d. 460 mrem QUESTION B.13 [1.0 point]
A radiation field is 330 mR/hr at 4 feet. What is your dose rate at 2 feet away from the source?
- a. 499 mR/hr
- b. 580 mR/hr
- c. 660 mR/hr
- d. 1320 mR/hr QUESTION B.14 [1.0 point]
Which ONE of the following experiments is NOT required to be doubly encapsulated?
- a. Liquid fissionable materials
- b. Compounds highly reactive with water
- c. Explosive materials
- d. Materials corrosive to reactor components
Category B: Normal/Emergency Operating Procedures and Radiological Controls QUESTION B.15 [1.0 point]
Where are the emergency first aid and medical supply kits NOT located?
- a. Directors office
- b. Evacuation corridor
- c. Psychology exit corridor
- d. Reactor bay emergency exit QUESTION B.16 [1.0 point, 0.25 each]
Match the appropriate 10CFR part in Column A with the requirements in Column B.
Column A Column B
- a. 10CFR19 1. Technical information including the proposed maximum power level
- b. 10CFR20 2. Individual radiation exposure data
- c. 10CFR50 3. Postings of notices to workers
- d. 10CFR55 4. Medical examination by a physician every two years QUESTION B.17 [1.0 point]
Which ONE of the following meets the required MINIMUM radiation monitoring channels for reactor operation?
- d. Environmental dosimeters are not required, 1 RAM, and 1substituted CAM QUESTION B.18 [1.0 point, 0.33 each]
Match the following limitations in Column A with its specification in Column B (Assume natural convection; Answers may be used more than once or not at all)
Column A Column B
- a. Safety Limit 1. Shutdown Margin $0.50
- b. Limiting Safety System Setting 2. Maximum fuel temperature 1000oC
- c. Limiting Condition for Operation 3. Maximum 300 kW
Category B: Normal/Emergency Operating Procedures and Radiological Controls QUESTION B.19 [1.0 point] (Question deleted, no correct answer listed).
A 25 curie source emits a 1.332MeV gamma and a 1.117 gamma 100% of the time. The source will be placed in the reactor storage room. How far from the source should a high radiation area sign be posted?
- a. Not required
- b. 10 feet
- c. 15 feet
- d. 25 feet QUESTION B. 20 [1.0 point]
Which ONE of the following surveillance checks shall be tested at least quarterly?
- a. Pool water radioactivity
- b. Scram times
- c. Rod withdrawal and insertion speeds
- d. Reactivity worth of control devices
(***** End of Category B *****)
((***** END OF EXAM *****))
Category A: Reactor Theory, Thermodynamics, and Facility Operating Characteristics A.01 Answer: b
Reference:
DOE Fundamentals Handbook Nuclear Physics and Reactor Theory, Volume 2, Module 4 A.02 Answer: d
Reference:
CR=S/(1-k)300/(1-0.5) = 600 N/sec A.03 Answer: a
Reference:
NRC standard question A.04 Answer: d
Reference:
Burn, Introduction to Nuclear Reactor Operations, Section 8.1, Page 8-1 A.05 Answer: c
Reference:
Burn, Introduction to Nuclear Reactor Operations, Section 7 0.001k/k (7ºF/3.5inches) = 0.001/2 = 0.0005 =5 x 10-4 k/k/ºF A.06 Answer: c
Reference:
Burn, Introduction to Nuclear Reactor Operations, Figure 2.6, Page 2-39 A.07 Answer: b
Reference:
Reed Training Manual, Chapter 10.3, Figure 10.6 A.08 Answer: b
Reference:
Burn, Introduction to Nuclear Reactor Operations, Section 3.3.2, Page 3-7 A.09 Answer: a
Reference:
DOE Fundamentals Handbook Nuclear Physics and Reactor Theory, Volume 2, Module 1 A.10 Answer: a(3), b(4), c(2), d(1)
Reference:
DOE Fundamentals Handbook Nuclear Physics and Reactor Theory, Volume 1, Module 2, Pages 29-37 A.11 Answer: d
Reference:
DOE Fundamentals Handbook Nuclear Physics and Reactor Theory, Volume 2, Module 3, Page 35 A.12 Answer: c
Reference:
Burn, Introduction to Nuclear Reactor Operations, Section 4.10.14, Page 4-33
Category A: Reactor Theory, Thermodynamics, and Facility Operating Characteristics A.13 Answer: b
Reference:
Burn, Introduction to Nuclear Reactor Operations, Section 3.3.4, Page 3-20&21
=(keff2-keff1)/(keff1*keff2) = (0.987-0.924)/(0.987*0.924) = 0.0690k/k or 6.9%k/k A.14 Answer: c
Reference:
=(k-1)/k-0.051=k-(-0.05k)=k(1+0.05)k=1/1.05 =0.952 A.15 Answer: a
Reference:
P=Poet/Tt=T*ln(P/Po) assume constant period=1 The smallest ratio of P/Po is the shortest time to complete A.16 Answer: b
Reference:
Burn, Introduction to Nuclear Reactor Operations, Section 6.2.3 A.17 Answer: c
Reference:
Burn, Introduction to Nuclear Reactor Operations, Section 5.4 A.18 Answer: c
Reference:
P/Po = 120%, T = 20 seconds, t = 0.5, P/Po = 120 e^0.5/20 = 123%
A.19 Answer: b
Reference:
Chart of the Nuclides A.20 Answer: d
Reference:
LaMarsh, Introduction to Nuclear Engineering, Page 340-341 (1- )k=1 manipulated reads k=1/(1- )
Category B: Normal/Emergency Operating Procedures and Radiological Controls B.1 Answer: c
Reference:
Reed Technical Specification 3.3 B.2 Answer: a
Reference:
Reed, Emergency Plan 3.5 B.3 Answer: a
Reference:
10CFR20.1003 B.4 Answer: a(2),b(2),c(3),d(1)
Reference:
Reed Emergency Plan 4.1 & 4.2 B.5 Answer: a
Reference:
Reed TS 3.1.2 B.6 Answer: b
Reference:
Reed Emergency Plan 3.1.3 B.7 Answer: a
Reference:
T A = A*e -t 3Ci = 300Ci* e -(t) Note: = -ln2/t1/2 Ln(3/300) = -ln2/X yr*(30 years) --> -4.605/-1.021 solve for t: 4.51 years B.8 Answer: b
Reference:
B.9 Answer: a (check), b (test), c (cal) , d (test)
Reference:
Reed Technical Specifications 1, definitions B.10 Answer: c
Reference:
10 CFR 20.1201 B.11 Answer: a
Reference:
Reed Technical Specifications 6.1.3 B.12 Answer: d
Reference:
20mrad Alpha x 20 = 400mrem, 10mrad Gamma x 1 = 10mrem, 5mrad neutron x 10 = 50mrem 400mrem + 10mrem + 50mrem = 460mrem
Category B: Normal/Emergency Operating Procedures and Radiological Controls B.13 Answer: d
Reference:
I1D12=I2D22 330mR/hr@(4ft)2=I2@(2ft)2 1320mR/hr B.14 Answer: c
Reference:
Reed Technical Specifications 3.6.2 B.15 Answer: a
Reference:
Reed Emergency Plan 8.2 B.16 Answer: a (3), b(2), c(1), d(4)
Reference:
10CFR19.11, 10CFR20.1501(2)(i), 10CFR50.34(1)(ii)(A), 10CFR55.21 B.17 Answer: b
Reference:
Reed Technical Specifications 3.5.1, Table 5 B.18 Answer: a(2),b(3),c(1)
Reference:
Technical Specifications 2.1 2.2 3.1.2 B.19 Answer: d (Question deleted, no correct answer listed)
Reference:
I=6CEn=R/hr@ft.6 x 25Ci x [(1.332Mev x 100%)+(1.117x100%)] = 367.65 R/hr@ (1ft)2 = 367.65R/hr = 0.1 R/hr@ D2 = 367.65 R/hr = 19.166 ft.
B.20 Answer: a
Reference:
Reed Technical Specifications 4.2 & 4.3