IR 05000186/2008002
| ML081510579 | |
| Person / Time | |
|---|---|
| Site: | University of Missouri-Columbia |
| Issue date: | 06/17/2008 |
| From: | Johnny H. Eads NRC/NRR/ADRA/DPR/PRTB |
| To: | Butler R A Univ of Missouri - Columbia |
| Young P, NRC/NRR/ADRA/DPR, 415-4094 | |
| Shared Package | |
| ml081510630 | List: |
| References | |
| 50-186/08-002 50-186/08-002 | |
| Download: ML081510579 (29) | |
Text
June 17, 2008
Mr. Ralph A. Butler, Chief Operating Officer Research Reactor Facility 1513 Research Park University of Missouri Columbia, MO 65211
SUBJECT: INITIAL EXAMINATION REPORT NO. 50-186/OL-08-02, UNIVERSITY OF MISSOURI - COLUMBIA
Dear Mr. Butler:
During the week of May 19, 2008, the NRC administered an operator licensing examination at your Missouri University Research Reactor. The examination was 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 pty@nrc.gov.
Sincerely,/RA/
Johnny Eads, Chief Research and Test Reactors Branch B Division of Policy and Rulemaking Office of Nuclear Reactor Regulation
Docket No. 50-186
Enclosures:
1. Initial Examination Report No. 50-186/OL-08-02 2. Facility Comments 3. Written examination with facility comments incorporated
cc without enclosures:
Please see next page
June 17, 2008 Mr. Ralph A. Butler, Chief Operating Officer Research Reactor Facility 1513 Research Park University of Missouri Columbia, MO 65211
SUBJECT: INITIAL EXAMINATION REPORT NO. 50-186/OL-08-02, UNIVERSITY OF MISSOURI - COLUMBIA
Dear Mr. Butler:
During the week of May 18, 2008, the NRC administered an operator licensing examination at your Missouri University Research Reactor. The examination was 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 pty@nrc.gov.
Sincerely,/RA/ Johnny Eads, Chief Research and Test Reactors Branch B Division of Policy and Rulemaking Office of Nuclear Reactor Regulation Docket No. 50-186
Enclosures:
1. Initial Examination Report No. 50-186/OL-08-02 2. Facility Comments 3. Written examination with facility comments incorporated
cc without enclosures:
Please see next page DISTRIBUTION w/ encls.: PUBLIC PRTB r/f RidsNRRDPRPRTA RidsNRRDPRPRTB Facility File (CHart) O-12 G-15 ADAMS ACCESSION #: ML 081510579 TEMPLATE #:NRR-074 OFFICE PRTB:CE IOLB:LA E PRTB:SC NAME PYoung pty CHart cah JEads jhe DATE 6/17/08 6/17/08 6/17/08 OFFICIAL RECORD COPY University of Missouri-Columbia Docket No. 50-186
cc: University of Missouri Associate Director Research Reactor Facility Columbia, MO 65201 Homeland Security Coordinator Missouri Office of Homeland Security P.O. Box 749 Jefferson City, MO 65102 Planner, Dept of Health and Senior Services Section for Environmental Public Health 930 Wildwood Drive, P.O. Box 570 Jefferson City, MO 65102-0570
Deputy Director for Policy Department of Natural Resources 1101 Riverside Drive Fourth Floor East Jefferson City, MO 65101
A-95 Coordinator Division of Planning Office of Administration P.O. Box 809, State Capitol Building Jefferson City, MO 65101 Test, Research, and Training Reactor Newsletter University of Florida 202 Nuclear Sciences Center Gainesville, FL 32611 U. S. NUCLEAR REGULATORY COMMISSION OPERATOR LICENSING INITIAL EXAMINATION REPORT
REPORT NO.: 50-186/OL-08-02,
FACILITY DOCKET NO.: 50-186
FACILITY LICENSE NO.: R-103
FACILITY: UNIVERSITY OF MISSOURI - COLUMBIA
EXAMINATION DATES: May 19 - 20, 2008
SUBMITTED BY: __________/RA/______________ __5/23/08
__ Phillip T. Young, Chief Examiner Date
SUMMARY:
During the week of May 19, 2008, the NRC administered operator licensing examinations to two Reactor Operator candidates and two Senior Operator Upgrade candidates. All four candidates passed all portions of their respective examinations.
REPORT DETAILS
1. Examiners: Phillip T. Young, Chief Examiner, NRC
2. Results:
RO PASS/FAILSRO PASS/FAIL TOTAL PASS/FAIL Written 2/0 0/0 2/0 Operating Tests 2/0 2/0 4/0 Overall 2/0 2/0 4/0 3. Exit Meeting:
Phillip T. Young, NRC, Examiner Les Foyto, Reactor Manager John Fruits, Assistant Reactor Manger Operations Robert Hudson, Training Coordinator, MURR
The examiner thanked the facility for their cooperation during the exam and reminded them that they have five working days to submit comments on the written examination. There were no generic issues. ENCLOSURE 1 MURR OPERATIONS
Mr. Young, We have reviewed the written portion of the licensing examination administered at MURR on 5/20/08; and submit the following comments for your consideration:
Question B.016 Which ONE of the following is the 10CFR20 definition for "Annual Limit on Intake (ALI)"? Comment: The answer key indicates item 'B' to be the correct answer. Our review of 10CFR20 indicates the correct answer should be 'D'. Reference: 10CFR20 Section 1003 - Definitions Question C.002 Which ONE of the following is NOT a feature of the pneumatic tube system designed to limit the radiation hazard? Comment: The answer key indicates item 'D' to be the correct answer. Our review indicates the correct answer should be 'A'. Reference: Hazard Summary Report, Section 8.5 - Pneumatic Tubes SAR, Chapter 10.3.4 - Pneumatic Tube System
Question C.004 The three-way solenoid valves in the Valve Operating System can be arranged to operate and fail in different configurations. Match the valves listed as A through D with the three-way valve de-energized configuration shown as 1 through 3. Comments: The answer key indicates 'a = 3, b = 2, c = 1', to be the correct answer. Our review indicates no correct answer was available. The question states solenoid valves in the Valve Operating System fail in different configurations. This is not true, solenoid valves in the system are arranged differently for 'normal' operation, yet all the solenoid valves fail in the same configuration [the supply header closes, while the vent and operator ports open].
ENCLOSURE 2 Robert A. Hudson Training Coordinator - Reactor Operations University of Missouri Research Reactor Columbia, Mo 65211 The configurations shown on the exam illustrate 'normal' operating conditions for solenoids in the MURR Valve Operating System Lesson. All configurations shown in the references are with the solenoid valves in their "normal" operating condition NOT in the de-energized condition. No D distracter listed. Suggested changes to the question:
The three-way solenoid valves in the Valve Operating System can be arranged to operate and fail in different configurations. Match the valves listed as A through C with the three-way valve de-energized configuration shown as 1 through 3 Reference: MURR Valve Operating System Lesson MURR Print # 2324 - Valve Operation & Air System
Question C.005 Which ONE of the following DOES NOT describe a function of the Uninterruptible Power Supply? Comment: The answer key indicates item 'C' to be the correct answer. Our review of references indicates the correct answer should be 'A'. Reference: MURR Print # 522 Electrical Distribution SAR Chapter 8.0 - Electrical Power Systems - 8.1.2 Description of System In addition, the following questions are correct but we would offer a few suggestions.
Question A.004 A reactor is critical at 18.1 inches on a controlling rod. The controlling rod is withdrawn to 18.4 inches. The reactivity inserted is 0.001 ~k/k. What is the differential rod worth? Comment: Distracters A and B are identical.
Question B.003 The on-duty shift consists of you (Licensed Reactor Operator) the Lead Senior Reactor Operator (LSRO) and a Reactor Operator Trainee (Knowledgeable Person). You receive a message concerning an emergency in your family. What actions should you take before you leave? Comment: Distracter C and answer D refer to Shift Supervisors; current terminology is Lead Senior Reactor Operator (LSRO).
Please contact me if you would like additional information have any questions, Thank You Again Rob Hudson
University of Missouri - Columbia US NRC Operator License Examination Written Exam with Answer Key May 19, 2008
ENCLOSURE 3
Section A -
~ Theory, Thermo & Fac. Operating Characteristics Page 1 of 21 Question: A.001 [1.0 point] {1.0} One minute following a scram from full power, the indications on the nuclear channels are primarily due to: a. Prompt neutrons b. Delayed and photo-neutrons c. Prompt and delayed neutrons d. Prompt, delayed and photo-neutrons Answer: A.001 b. Reference: Burn, R., Introduction to Nuclear Reactor Operations, © 1988, § 6.2.1, & 6.2.2 p. 6-2.
Question: A.002 [1.0 point] {2.0} Shortly after shutting down the reactor you note that reactor period is a stable negative value. You note reactor power. Three minutes later the reactor is has the same stable negative value and reactor power has decreased by a factor of -
a. 2 b. 2.718 (e)
c. 5 d. 10 Answer: A.002 d.
Reference: DOE Fundamentals Handbook, Nuclear Physics and Reactor Theory, Volume 2, Module 4, Reactor Theory (Reactor Operations), Enabling Objective 2.6 P = P 0 e t/, where t = 180 seconds and = -80 seconds, P/P 0 = e-180/80 = 0.1054
Section A -
~ Theory, Thermo & Fac. Operating Characteristics Page 2 of 21 Question: A.003 [2.0 points, 0.4 each] {4.0} Indicate whether each of the following reactivity coefficients are Positive or Negative for the indicated locations.
a. Void Coefficient of the Flux Trap b. Void Coefficient of the Core c. Temperature Coefficient of the Core d. Temperature Coefficient of the Pool e. Temperature Coefficient of the Flux Trap Answer: C.003 a. = pos; b. = neg; c. = neg; d. = pos; e. = pos Reference: MURR Hazards Summary Report, p. 4-14.,SOP/VIII-7 Critical Parameters List Question: A.004 [1.0 point] {5.0} A reactor is critical at 18.1 inches on a controlling rod. The controlling rod is withdrawn to 18.4 inches. The reactivity inserted is 0.001 K/K. What is the differential rod worth a. 0.001 K/K/inch at 18.25 inches b. 0.001 K/K/inch at 18.4 25 inches {typographical error corrected, facility comment}
c. 0.003 K/K/inch at 18.4 inches d. 0.003 K/K/inch at 18.25 inches Answer: A.004 d. Reference: DOE Fundamentals Handbook, Nuclear Physics and Reactor Theory Question: A.005 [1.0 point] {6.0} Which one of the following is the correct reason that delayed neutrons allow human control of the reactor? a. Delayed neutrons increase the mean neutron lifetime. b. More delayed neutrons are produced than prompt neutrons.
c. Delayed neutrons take longer to thermalize than prompt neutrons.
d. Delayed neutrons are born at higher energies than prompt neutrons.
Answer: A.005 a. Reference: DOE Fundamentals Handbook, Nuclear Physics and Reactor Theory
Section A -
~ Theory, Thermo & Fac. Operating Characteristics Page 3 of 21 Question: A.006 [1.0 point] {7.0} Moderating efficiency takes into account how well an isotope will slow down a neutron, combined with its absorption cross-section. We know that 1 H 1 is best suited for slowing down a neutron. Which ONE of the listed isotopes will have the best overall moderating efficiency?
a. 1 H 2 b. 1 H 3 c. 6 H 12 d. 92 H 238 Answer: A.006 a. Reference: DOE Fundamentals Handbook, Volume 1, Module 2, p. 27.
Question: A.007 [1.0 point] {8.0} Several processes occur that may increase or decrease the available number of neutrons. SELECT from the following the six-factor formula term that describes an INCREASE in the number of neutrons during the cycle.
a. Resonance escape probability (p). b. Fast non-leakage probability (~
f). c. Thermal utilization factor (f). d. Fast Fission factor ().
Answer: A.007 d. Reference: DOE Fundamentals Handbook, Volume 2, Module 3, pp. 3-8 Question: A.008 [1.0 point] {9.0} Which ONE of the following reactions correctly describes Beta
- (-) decay? a. 35 Br 87 ~ 33 As 83 b. 35 Br 87 ~ 35 Br 86 c. 35 Br 87 ~ 34 Se 86 d. 35 Br 87 ~ 36 Kr 87 Answer: A.008 d. Reference: DOE Fundamentals Handbook, Volume 1, Module 1, pp 24 - 25.
Section A -
~ Theory, Thermo & Fac. Operating Characteristics Page 4 of 21 Question: A.009 [1.0 point] {10.0} A reactor is subcritical by 5% delta k/k with a count rate of 100 cps on the startup channel. Rods are withdrawn until the count rate is 1000 cps. Which ONE of the following is the condition of the reactor following the rod withdrawal?
a. Critical with k eff = 1.000. b. Subcritical with k eff = 0.995. c. Subcritical with k eff = 0.950. d. Supercritical with k eff = 1.005.
Answer: A.009 b. Reference: DOE Fundamentals Handbook, Module 4, Subcritical Multiplication, page 6. CR 1 (1-K 1) = CR 2 (1-K 2); = (K -1)/K; -0.05 = (K - 1)/K; K = 0.952. 100(1 - 0.952) = 1000(1 - K 2); K 2 = 0.995.
Question: A.010 [1.0 point] {11.0} Which ONE of the following conditions will INCREASE the shutdown margin of a reactor. a. Lowering moderator temperature (Assume negative temperature coefficient).
b. Insertion of a positive reactivity worth experiment.
c. Burnout of a burnable poison.
d. Fuel depletion.
Answer: A.010 d. Reference: DOE Fundamentals Handbook, Volume 2, Module 4, Reactor Theory (Reactor Operations), Enabling Objective 3.6
Question: A.011 [1.0 point] {12.0} You perform two startups with exactly the same conditions (temperature, xenon, samarium, rod speed, etc.).
For the first startup you proceed directly to criticality. For the second startup, you stop after pulling the rods in gang to 10 inches, to speak on the phone for 10 minutes. Which ONE of the following best describes the rod height and power at criticality for the second startup relative to the first startup?
a. Rod height will be lower, Power will be the same. b. Rod height will be higher, Power will be the same. c. Rod height will be the same, Power will be higher.
d. Rod height will be the same, Power will be the same.
Answer: A.011 c. Reference: DOE Fundamentals Handbook, Volume 2, Module 4, Reactor Theory (Reactor Operations), Enabling Objective 1.1.
Section A -
~ Theory, Thermo & Fac. Operating Characteristics Page 5 of 21 Question: A.012 [1.0 point] {13.0} The reactor had been running for 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> straight at 10 megawatts when it was shutdown for maintenance. The maintenance took six hours, and you have just restarted the reactor and raised power to 10 megawatts and placed the reactor in auto control. Which ONE of the following is the expected response of the regulating rod for the next half hour? (Assume no fuel replacement during shutdown.)
a. Drive in b. Drive out c. Not move d. Drive out then back in
Answer: A.012 a. Reference: DOE Fundamentals Handbook, Volume 2, Module 3, Reactor Theory (Nuclear Parameters), Enabling Objective 4.5.
Question: A.013 [1.0 point] {14.0} "CORE EXCESS" is - 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 rods and other poisons were removed.
c. the combined reactivity worth of control rods and chemical poison 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.013 b. Reference: DOE Fundamentals Handbook Question: A.014 [1.0 point] {15.0} Which ONE of the following statements concerning reactor poisons is NOT true? a. During reactor operation, Xenon concentration is dependent on reactor power level.
b. Following shutdown, Samarium concentration will increase to some value then stabilize.
c. During reactor operation, Samarium concentration is independent of reactor power level. d. Following shutdown, Xenon concentration will initially increase to some value then decrease exponentially.
Answer: A.014 c. Reference: DOE Fundamentals Handbook
Section A -
~ Theory, Thermo & Fac. Operating Characteristics Page 6 of 21 Question: A.015 [1.0 point] {16.0} You are the reactor operator controlling the reactor in manual. An experimenter is preparing to inject an experiment worth - 1%K/K into the reactor. What type of reactor period do you expect to see?
(* = 1 x 10
-4; eff = 0.1; eff = 0.00738 K/K) a. 2 sec. b. 10 sec. c. 20 sec d. 40 sec Answer: A.015 c. Reference: DOE Fundamentals Handbook, Question: A.016 [1.0 point] {17.0} The reactor is critical at a watt with the regulating blade at position X. You withdraw the reg rod to increase power to 500 watts. To stabilize power at this level you must insert the reg rod to -
a. a position lower than X. b. position X.
c. a position slightly higher than X.
d. all the way into the core.
Answer: A.016 b. Reference: DOE Fundamentals Handbook
Question: A.017 [1.0 point] {18.0} An Integral Rod Worth (IRW) curve is ________________, while a Differential Rod Worth (DRW)
curve is __________.
a. the total reactivity worth added by the rod at any point of withdrawal; the reactivity change per unit movement of the rod at the point of withdrawal.
b. at its maximum value when the rod is approximately half-way out of the core; at its maximum value when the rod is fully withdrawn from the core.
c. the slope of the DRW curve at any point of withdrawal; the area under the IRW curve at any point of withdrawal.
d. the reactivity change per unit movement of the rod at any point of withdrawal; the total reactivity worth of the rod at any point of withdrawal.
Answer: A.017 a. Reference: DOE Fundamentals Handbook, Module 3, Control Rods, page 51.
Section A -
~ Theory, Thermo & Fac. Operating Characteristics Page 7 of 21 Question: A.018 [1.0 point] {19.0} During a reactor startup, the count rate is increasing linearly on a logarithmic scale, with no rod motion. This means that:
a. the reactor is subcritical and the count rate increase is due to the buildup of delayed neutron precursors.
b. the reactor is subcritical and the count rate increase is due to source neutrons.
c. the reactor is critical and the count rate increase is due to source neutrons.
d. the reactor is supercritical.
Answer: A.018 d. Reference: DOE Fundamentals Handbook, Module 4, Reactor Kinetics, page 14.
Question: A.019 [1.0 point] {20.0} Regulating rod worth for a reactor is 0.001 K/K/inch. Moderator temperature INCREASES by 9 F, and the regulating rod moves 41/2 inches inward to compensate. The moderator temperature coefficient Tmod is - a. +5 x 10
-4 K/K/
F b. -5 x 10
-4 K/K/
F c. +2 x 10
-5 K/K/
F d. -2 x 10
-5 K/K/
F Answer: A.019 a.
Reference: DOE Fundamentals Handbook, Nuclear Physics and Reactor Theory. 0.001 K/K/inch x 4.5 inch ÷ 9 F = 0.001 ÷ 2 = 0.0005 = 5 x 10
-4 K/K/
F
Section B - Normal/Emergency Procedures & Radiological Controls Page 8 of 21 Question: B.001 [1.0 point, 0.25 each] {1.0} Match the type of radiation in column A with its associated Quality Factor (10CFR20) from column B. Column A Column B a. alpha 1 b. beta 2 c. gamma 5 d. neutron (unknown energy) 10 20
Answer: B.001 a. = 20; b. = 1; c. = 1; d. = 10 Reference: NRC Generic Section B Bank {10CFR20.100x}
Question: B.002 [2.0 points, point each] {3.0} 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. Minimum Shutdown Margin 1. 0.0980 K b. Each secured Removable Experiment 2. 0.0200 K c. Core Excess Reactivity 3. 0.0060 K d. Absolute Value of all experiments in Center test hole 4. 0.0025 K e. Movable parts of any individual experiments 5. 0.0010 K f. Each Unsecured Experiment Answer: B.002 a. = 2; b. = 3; c. = 1; d. = 3; e. = 5; f. = 4 Reference: Technical Specifications § 3.1 Reactivity Specifications e, f, g, h, i, and j.
Section B - Normal/Emergency Procedures & Radiological Controls Page 9 of 21 Question: B.003 [1.0 point] {4.0} The on-duty shift consists of you (Licensed Reactor Operator) the Lead Senior Reactor Operator (LSRO) and a Reactor Operator Trainee (Knowledgeable Person). You receive a message concerning an emergency in your family. What actions should you take before you leave?
a. Shutdown the reactor in accordance with ______.
b. Wait for another Reactor Operator to arrive before you leave.
c. Turn over the watch to the trainee, who may operate the reactor under the direction of the LSRO Shift Supervisor. {question updated per facility comment}
d. Turn over the watch to the LSRO Shift Supervisor who may operate the reactor with the trainee present in the control room. {question updated per facility comment}
Answer: B.003 d. Reference: AP-RO-110, Conduct of Operations § 6.5,3,d, p. 10.
Question: B.004 [1.0 point] {5.0} The reflector high and low differential pressure scram: a. provides a backup to the pool coolant low flow scram.
b. provides a backup to the primary low pressure scram.
c. provides a backup to the primary coolant low flow scram.
d. assures adequate cooling of the fuel and flux trap region.
Answer: B.004 a. Reference: MURR Technical Specifications, Section 3.3.a bases.
Question: B.005 [1.0 point] {6.0} According to the Technical Specifications, which ONE of the following conditions is NOT permissible when the reactor is operating?
a. Above 100 kW, the maximum distance between the highest and lowest shim blade = 1 inch. b. Emergency generator is out of service for one hour for maintenance.
c. A fueled experiment containing 300 millicuries of I 135. d. Core excess reactivity = 0.006 k/k. Answer: B.005 b. Reference: MURR Technical Specifications, Section 3.10.a.
Section B - Normal/Emergency Procedures & Radiological Controls Page 10 of 21 Question: B.006 [1.0 point] {7.0} Which ONE of the following operations requires the direct supervision (i.e., presence) of a Senior Reactor Operator?
a. Start up pool coolant system. b. Stack monitor operational test.
c. Start up primary coolant system.
d. Adjustment of nuclear instrumentation.
Answer: B.006 d. Reference: OP-RO-340
Question: B.007 [1.0 point] {8.0} Which ONE of the following is NOT a requirement of OP-RO-531 Primary and Pool Sample Station?
a. The primary must be sampled daily for H 3. b. Do not operate if I 131 concentration exceeds 5 x 10
-3 µCi/ml c. HP coverage is required if abnormal fission product activity is present.
d. If the primary system fuel failure detector is out of service the primary must be sampled every 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
Answer: B.007 a.
Reference: OP-RO-531, Primary and Pool Sample Station
Question: B.008 [1.0 point] {9.0} 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) states that the minimum level of staff which may authorize this action is -
a. NRC Manager. b. any Reactor Operator licensed at facility.
c. any Senior Reactor Operator licensed at facility. d. Facility Manager (or equivalent name at facility).
Answer: B.008 c.
Reference: NRC Generic Section B Bank {10CFR50.54(y)}
Section B - Normal/Emergency Procedures & Radiological Controls Page 11 of 21 Question: B.009 [1.0 point] {10.0} An experimenter wishes to irradiate three specimens with reactivity worths of 0.0005 k/k, 0.0013 k/k and 0.0027 k/k. Can these specimens be placed in the reactor as UNSECURED experiments and why (why not).
a. Yes, each specimen is less than 0.006 k/k. b. No, one of the specimens is greater than 0.0025 k/k. c. Yes, the sum of the three specimens is less than 0.025 k/k. d. No, the sum of the three specimens is greater than 0.01 k/k. Answer: B.009 b. Reference: Technical Specifications, §§ 3.1(g)-(k).
Question: B.010 [1.0 point] {11.0} When pumping the Liquid Waste tanks to the sanitary sewer, the maximum accumulated activity for nuclides other than H 3 is 2 millicuries for the Lead Senior Reactor Operator to authorize the procedure. The maximum accumulated activity for H 3 is - a. 1 millicuries b. 5 millicuries c. 10 millicuries d. 20 millicuries Answer: B.010 c.
Reference: OP-RO-741, Waste Tank System Operation
Question: B.011 [1.0 point] {12.0} A survey instrument with a window probe was used to measure an irradiated experiment. The results were 100 millirem/hr window open and 60 millirem/hr window closed. What was the gamma dose? a. 40 millirem/hr b. 60 millirem/hr c. 100 millirem/hr d. 160 millirem/hr Answer: B.011 b. Reference: NRC Generic Section B Bank {Instrument reads only gamma with window closed therefore reading with window closed is gamma dose.}
Section B - Normal/Emergency Procedures & Radiological Controls Page 12 of 21 Question: B.012 [1.0 point] {13.0} When placing the Rod Control Mode in "Auto", why should the Wide Range Monitor Level indication be greater than 2% above the "Power level Set"? Ensure that the-
a. Period is longer than 35 seconds. b. Reactor Power Calculator is operating and indicating properly.
c. Area Radiation Monitor reads will not exceed acceptable levels.
d. First automatic movement of the Regulating Blade is in the inward direction.
Answer: B.012 d. Reference: OP-RO-210
Question: B.013 [1.0 point] {14.0} Unless extended in writing, a Radiation Work Permits expire in: a. 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> b. 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> c. 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> d. one week
Answer: B.013 b. Reference: AP-HP-105 Question: B.014 [2.0 points, 1/2 each] {16.0} Identify each of the following reactor plant limitations as a Safety Limit (SL), Limiting Safety System Setting (LSSS) or a Limiting Condition for Operation (LCO). (Choices may be used more than once or not at all.)
a. Primary Coolant Pressure (minimum) 75 psia b. 1" (maximum) distance between highest and lowest shim arms above 100 Kilowatts
c. 1625 gpm (minimum) either loop.
d. A minimum of one decade of overlap shall exist between adjacent ranges of nuclear instrument channels.
Answer: B.014 a. = LS; b. = LC; c. = LS; d. = LC Reference: Technical Specifications
Section B - Normal/Emergency Procedures & Radiological Controls Page 13 of 21 Question: B.015 [1.0 point] {17.0} Two point sources have the same Curie strength. Source A's gammas have an energy of 1 Mev, while Source B's gammas have an energy of 2 Mev. You obtain a measurement from the same GM tube 10 feet from each source. Concerning the two measurements, which ONE of the following statements is true?
a. The measured dose rate from Source B is four times that of Source A. b. The measured dose rate from Source B is twice that of Source A.
c. The measured dose rate from Source B. is half that of Source A.
d. Both measurements are the same.
Answer: B.015 d.
Reference: NRC Generic Section B Bank {GM tubes cannot distinguish between energies.}
Question: B.016 [1.0 point] {18.0} Which ONE of the following is the 10CFR20 definitions for "Annual Limit on Intake (ALI)"?
a. Projected dose commitment values to individuals, that warrant protective action following a release of radioactive material.
b. The concentration of a radionuclide in air which, if inhaled by an adult worker for a year, would result in a total effective dose equivalent of 100 millirem.
c. The effluent concentration of a radionuclide in air which, if inhaled continuously over a year, would result in a total effective dose equivalent of 50 millirem for noble gases.
d. 10CFR20 derived limit, based on 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.
Answer: B.016 d.
b. {typographical error correct, facility comment} Reference: NRC Generic Section B Bank {10CFR20.1003 Definitions}
Question: B.017 [1.0 point] {19.0} When placing Fire Protection Systems in online, failure to wait for air systems to reach normal operating pressure before proceeding could result in..
a. Sprinklers may activate b. Sprinkler head damage c. Inoperability of detection capability d. Hydrant or Post Indicator Valve (PIV) damage Answer: B.017 a.
Reference: OP-OR-555 Section B - Normal/Emergency Procedures & Radiological Controls Page 14 of 21 Question: B.018 [1.0 point] {20.0} An experiment is removed from the reactor and is determined to have a radiation level of 10 Rem/hr at 15 feet from the experiment. Forty Five (45) minutes later the radiation level is 7.2 Rem/hr at 15 feet. Which one of the following is the length of time the experiment must decay before the radiation level at one (1) foot is less than 100 mrem/hr?
a. 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> b. 5.26 hours3.009259e-4 days <br />0.00722 hours <br />4.298942e-5 weeks <br />9.893e-6 months <br /> c. 18.6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> d. 40.6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> Answer: B.018 d.
Reference: NRC Generic Section B Bank
Section C - Facility and Radiation Monitoring Systems Page 15 of 21 Question: C.001 [1.0 point] {1.0} Which Area Radiation Monitors below can cause a Reactor Isolation? a. Bridge, Bridge ALARA, Air Plenum 1, Air Plenum 2.
b. Bridge, Bridge ALARA, Fission Product Monitor, Air Plenum 1.
c. Fission Product Monitor, Air Plenum 1, Air Plenum 2, Bridge ALARA.
d. Beamport Floor North Wall, Beamport Floor West Wall, Beamport Floor South Wall, Bridge.
Answer: C.001 a. Reference: MURR Area Radiation Monitor System Lesson Question: C.002 [1.0 point] {2.0} Which ONE of the following is NOT a feature of the pneumatic tube system designed to limit the radiation hazard?
a. Double encapsulation of samples. b. Speed at which the sample container is transported through the system.
c. Facility exhaust fans operation prevent stagnant air in the vicinity of the rabbit system.
d. A time delay starts the east p-tube blower approximately 15 seconds after the west p- tube blower.
Answer: C.002 a.
d. {typographical error correct, facility comment} Reference: SAR, Chapter 10 - Experimental Facilities and Utilization - 10.3.4 Pneumatic Tube System
Question: C.003 [1.0 point] {3.0} Containment building isolation is accomplished by closing two butterfly valves, 16A and 16B, in the main exhaust line. Which ONE of the following describes the operation of these valves?
Valve 16A Valve 16B a. air open, air close air open, spring close. b. air open, spring close air open, air close. c. motor-operated (open and close) air open, air close.
d. air open, spring close motor-operated (open and close)
Answer: C.03 b.
Reference: SAR Chapter 6 - Engineered Safety Features - 6.2.3.8 Hot Exhaust Line
Section C - Facility and Radiation Monitoring Systems Page 16 of 21 Question C.004 deleted from this examination and corrected per facility comment for use on future examinations.
Question: C.004 [1.0 points, each] {4.0} The three-way solenoid valves in the Valve Operating System can be arranged to operate and fail in different configurations. Match the valves listed as A through C D with the three-way valve de-energized configuration shown as 1 through 3.
a. Pressurizer Isolation - 527C b. Primary Demineralizer Inlet - 527E and Outlet - 527F c. Anti-Siphon Isolations - 543A & B 1. 2. 3. Answer: C.004 a. = 3; b. = 2; c. = 1 Reference: MURR Valve Operating System Lesson
Section C - Facility and Radiation Monitoring Systems Page 17 of 21 Question: C.005 [1.0 point] {5.0} Which ONE of the following DOES NOT describe a function of the Uninterruptible Power Supply? a. supply power to the Emergency Distribution Center (CTR-1).
b. supply power to the Area Radiation Monitoring System (ARMS) to ensure radiation levels are known.
c. reduce spurious (false) reactor scrams caused by voltage fluctuations or a momentary interruption in electrical power.
d. ensures that the reactor control console and instrument panel indications are maintained during the transition period from the time of a loss of normal electrical power to the time the diesel generator supplies the load.
Answer: C.005 a.
c. {typographical error corrected, facility comment} Reference: SAR Chapter 8.0 - Electrical Power Systems - 8.1.2 Description of System
Question: C.006 [1.0 point] {6.0) What type of sensor is used to detect the position of the "rabbit" in the core? a. photo-electric cell b. magnetic switch c. micro switch d. reed switch
Answer: C.006 a. Reference: SAR, Chapter 10 - Experimental Facilities and Utilization - 10.3.4 Pneumatic Tube System Question: C.007 [1.0 point] {7.0} A Facility Evacuation can be manually initiated from the control console and: a. the reactor bridge.
b. equipment room 278.
c. the front lobby.
d. equipment room 114.
Answer: C.007 c. Reference: CP-6 Building Evacuation/Isolation Scram
Section C - Facility and Radiation Monitoring Systems Page 18 of 21 Question: C.008 [1.0 point] {8.0} Which ONE of the following is the reason for the 100 gallon holdup tank in the purification system? This tank
a. is part of the regeneration system. b. allows N 16 gamma activity to decay off. c. contains spent resin from the demineralizer units.
d. provides water hammer protection for the purification system.
Answer: C.008 b.
Reference: SAR, Chapter 5 Reactor Coolant Systems - 5.7.2 Primary Coolant Demineralizer Loop Hold- Up Tank Question: C.009 [1.0 point] {9.0} Which ONE of the following conditions is required for proper operation of the Antisiphon system? a. System pressure must be greater than 10 psig. b. System pressure must be greater than 27 psig.
c. System water level must be more than 10 inches above the antisiphon valves.
d. System water level must be more than 6 inches above the antisiphon valves.
Answer: C.009 b. Reference: MURR Anti-Siphon System Lesson Plan Question: C.010 [1.5 points, 0.25 each] {10.5} Match each of the beamports in column A with the correct characteristics in Column B Column A Column B Beamport Characteristic a. A 1. 6" radial (6R)
b. B 2. 6" radial - tangential (6RT)
c. C 3. 4" radial (4R) d. D 4. 4" radial - tangential (4RT) e. E f. F Answer: C.010 a. = 3; b. = 1; c. = 2; d. = 4; e. = 1; f. = 3 Reference: SAR, Chapter 10 - Experimental Facilities and Utilization - Table 10-1 Section C - Facility and Radiation Monitoring Systems Page 19 of 21 Question: C.011 [1.0 point] {11.5} Which ONE of the following alarms on the control panel is NOT associated with the startup interlock?
a. Jumper Board in Use b. Thermal Column Door Open c. Nuclear Instrument Anomaly d. Source range level indication >20 cps or intermediate range level recorder indication >2 x 10
-5% power Answer: C.011 a. Reference: SAR, Chapter 7 -Instrumentation and Control Systems; 7.5.3.1 Rod Withdrawal Prohibit Question: C.012 [1.5 points, 0.1875 each] {13.0} Match the channel in column A with the correct detector in column B. Column A Column B a. Fission Product Monitor 1. Geiger Müeller b. Secondary Coolant Monitor 2. Scintillation Detector c. Stack Gas Monitor 3. GeLi Detector d. Stack Particulate Monitor 4. BF 3 Ion Chamber Detector e. Stack Iodine Monitor f. Bridge ARMS g. Exhaust Plenum 1 h. Room 114 ARMS Answer: C.012 a. = 2; b. = 2; c. = 2; d. = 2; e. = 2; f. = 1; g. = 1; h. = 4 Reference: SAR, Chapter 7 -Instrumentation and Control Systems; Figure 7.11 Area Radiation Monitoring System pages 7-63/64
Section C - Facility and Radiation Monitoring Systems Page 20 of 21 Question: C.013 [1.0 point] {14.0} Just prior to withdrawing control rods with all process control systems on line, the Master Control Switch (1S1) is taken from the ON position to the OFF position. Which ONE of the following conditions will result?
a. All systems will shut down. b. All systems will remain running, but without automatic operation.
c. All systems will remain running with all automatic functions operable. d. The system is mechanically interlocked and you cannot move 1S1 to the off position with all systems running.
Answer: C.013 c. Reference: SAR, Chapter 7 -Instrumentation and Control Systems; 7.5.3 Manual Control.
Question: C.014 [1.0 point] {15.0} The purpose of the thermal column is to - a. enhance natural convection flow.
b. provide thermal neutron flux for experiments. c. enhance heat transfer characteristics of the core. d. provide a thermal temperature rise for experiments.
Answer: C.014 b. Reference: SAR, Chapter 10 - EXPERIMENTAL FACILITIES AND UTILIZATION Question: C.015 [1.0 point] {16.0} The normal path for adding water to the pool is by way of gravity drain from either demineralized water tank to -
a. a diffuser header located about a foot below the normal fill line. b. a garden hose located at the top of the reactor pool.
c. the suction of the pool coolant system pump.
d. the suction of the pool skimmer pump.
Answer: C.015 d.
Reference: OP-RO-465, § 6.1
Section C - Facility and Radiation Monitoring Systems Page 21 of 21 Question: C.016 [1.0 point] {17.0} The reactor is in the automatic mode of operation. Which ONE of the following conditions will NOT cause control to shift back to manual?
a. Regulating rod control switch (1S5) actuated. b. Regulating rod inserted to the 10% withdrawn position.
c. Regulating blade position is greater than 60% withdrawn.
d. Wide Range Monitor selector switch is in the 5 kW black scale position.
Answer: C.016 c.
Reference: SAR, Chapter 7 -Instrumentation and Control Systems; 7.5.4 Automatic Control Question: C.017 [2.0 points, 1/2 point each] {19.0} For each of the Rod Run-In Functions listed below, fill in the minimum number of instrument channels required by Technical Specifications for Reactor Operation in Mode 1.
Column A Rod Run-In Minimum Number of Channels a. High Reactor Power 1 b. Reactor Period 2 c. Rod not in contact with magnet 3 d. Vent Tank Low Level 4 Answer: C.017 a. = 3; b. = 2; c. = 4; d. = 1 Reference: Technical Specification 3.4. Reactor Instrumentation
Question: C.018 [1.0 point, each] {20.0} Match the appropriate response condition (a through c) with the correct back light color (1 through 4).
a. Scram 1. Red b. Rod run-in 2. Yellow c. Alarm 3. White 4. Blue
Answer: C.018 a. = 1; b. = 4; c. = 3 Reference: SAR, Chapter 7 -Instrumentation and Control Systems - 7.3.1 Annunciator