september 22, 2008 dr. mohammed hosni, …september 22, 2008 dr. mohammed hosni, department head...

September 22, 2008

Dr. Mohammed Hosni, Department Head Mechanical and Nuclear Engineering Kansas State University 3002 Rathbone Hall Manhattan, KS 66506 SUBJECT: RETAKE EXAMINATION REPORT NO. 50-188/OL-08-02, KANSAS STATE

UNIVERSITY TRIGA REACTOR Dear Dr. Hosni: During the week of August 18, 2008, the NRC administered an operator licensing retake examination at your Kansas State University TRIGA 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. Paul V. Doyle Jr. at (301) 415-1058 or via internet e-mail [email protected]. Sincerely, /RA/ Johnny H. Eads, Jr., Chief Research and Test Reactors Branch B Division of Policy and Rulemaking Office of Nuclear Reactor Regulation Docket No. 50-188 Enclosures: 1. Retake Examination Report No. 50-188/OL-08-02 2. Written examination with facility comments incorporated cc: Mr. Michael Whaley, Manager KSU Nuclear Reactor Facility 112 Ward Hall Kansas State University Manhattan, KS 66506-2500 cc without enclosures: See next page

September 22, 2008 Dr. Mohammed Hosni, Department Head Mechanical and Nuclear Engineering Kansas State University 3002 Rathbone Hall Manhattan, KS 66506 SUBJECT: INITIAL EXAMINATION REPORT NO. 50-188/OL-08-02, KANSAS STATE

UNIVERSITY TRIGA REACTOR Dear Dr. Hosni: During the week of August 18, 2008, the NRC administered an operator licensing retake examination at your Kansas State University TRIGA 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. Paul V. Doyle Jr. at (301) 415-1058 or via internet e-mail [email protected]. Sincerely, /RA/ Johnny Eads, Chief Research and Test Reactors Branch B Division of Policy and Rulemaking Office of Nuclear Reactor Regulation Docket No. 50-188 Enclosures: 1. Retake Examination Report No. 50-188/OL-08-02 2. Written examination with facility comments incorporated cc: Mr. Michael Whaley, Manager KSU Nuclear Reactor Facility 112 Ward Hall Kansas State University Manhattan, KS 66506-2500 cc without enclosures: See next page DISTRIBUTION: w/ enclosures DISTRIBUTION: w/o enclosures Non-public Facility File (CHart) O-13 D-07 RidsNRRDPRPRTB PRTB r/f RidsNRRDPRPRTA ADAMS ACCESSION #: ML082630134 TEMPLATE #:NRR-074

OFFICE PRTB:CE IOLB:LA PRTB:SC

NAME PDoyle pvd CHart cah JEads jhe

DATE 9/19/08 9/19/08 9/22/08

OFFICIAL RECORD COPY

Kansas State University Docket No. 50-188 cc: Office of the Governor State of Kansas Topeka, KS 66612 Thomas A. Conley, RRPJ, CHP, Section Chief, Radiation and Asbestos Control KS Dept of Health & Environment 1000 SW Jackson, Suite 320 Topeka, KS 66612-1366 Mayor of Manhattan P.O. Box 748 Manhattan, KS 66502 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.: 50-188/OL-08-02 FACILITY DOCKET NO.: 50-188 FACILITY LICENSE NO.: R-88 FACILITY: Kansas State University TRIGA Reactor EXAMINATION DATES: August 21, 2008 SUBMITTED BY: _________/RA PIsaac for/_______ 9/22/08 Paul V. Doyle Jr., Chief Examiner Date SUMMARY: The NRC prepared written examinations for three operator licensing candidates, who had failed the examination administered January, 2008. One candidate was administered a Section B only written examination. The other two candidates were administered a full three section written examination. The candidate who had took a Section B only examination passed the examination. The two candidates who took a complete written examination both failed section A of the examination. One of the candidates who took the complete examination also failed Section B of the examination and overall. REPORT DETAILS 1. Examiners:

Paul V. Doyle Jr., Chief Examiner, NRC 2. Results:

RO PASS/FAIL SRO PASS/FAIL TOTAL PASS/FAIL

Written 1/3 0/0 1/3

Operating Tests 0/0 0/0 0/0

Overall 1/3 0/0 1/3

3. Exit Meeting: There was no exit meeting, as there was no facility visit. Enclosure 1

During review of the recent "U.S. Nuclear Regulatory Commission Non-Power Retake Reactor License Examination" a few observations were noted, as follows: QUESTION B.03 Which one of the following conditions is permitted during reactor operation? a. Continuous air monitor in reactor bay inoperable due to maintenance b. A pulse reactivity insertion of $3.75 c. Startup with the period scram bypassed d. Operating in steady state mode with linear power channel inoperable KEY ANSWER c. REFERENCE: Procedure No. 11, Reactor Startup with Period Scram Bypassed. COMMENT: Technical Specification 3.3 requires the "Continuous air monitor." 3.3.4 ACTION statement E allows operation for 30 days with the "Exhaust plenum monitor" operating; therefore answer "a" is also correct. QUESTION B.06 Identify each of the following reactor plant limitations as Safety Limit (SL), Limiting Safety System Setting (LSSS) or a Limiting Conditions for Operation (LCO). a. Power SHALL NOT exceed 1,250 kW(th) in STEADY STATE MODE of operation KEY ANSWER: LCO -- REFERENCE: Technical Specifications 3.6 COMMENT: Technical Specifications Section 2.1 Safety Limits are "(1) Stainless steel clad, high-hydride fuel element temerparture SHALL NOT exceed 1150C; amd (2) Steady state fuel temperature shall not exceed 750C." Technical Specifications Section 2.2, Limiting Safety System Settings (LSSS) is "(1) Power level SHALL NOT exceed 1,250 kW*th) in STEADYS STATE MODE of operation." Therefore the correct answer is "Limiting Safety System Setting (LSSS). c. Water temperature at the exit of the reactor pool SHALL NOT exceed 130F with flow through the primary cleanup loop KEY ANSWER: SL -- REFERENCE: Technical Specifications 2.2 COMMENT: Technical Specifications Section 3.8, Reactor Pool Water, 3.8.3 (1) states "Water temperature at the exit of the reactor pool SHALL NOT exceed 130F with flow through the primary loop." Therefore, the correct answer is "Limiting Condition for Operation (LCO)." d. Steady state fuel temperature shall not exceed 750C KEY ANSWER: LCO -- REFERENCE: Technical Specifications 33.8 Technical Specifications Section 2.1 Safety Limits are "(1) Stainless steel clad, high-hydride fuel element temerparture SHALL NOT exceed 1150C; amd (2) Steady state fuel temperature shall not exceed 750C." Therefore the correct answer is "Safety Limit (SL)."

QUESTION C.05 Identify the heat transfer mechanism (Radiation, Forced Convection, Natural Convection or Conduction) for each of the following: d. Transfer of heat to from cooling tower to air KEY ANSWER: FC (Forced Convection) -- REFERENCE: Standard NRC question COMMENT: As per Safety Analysis Report Section 5.3.2 (Rev 5/08), the cooling tower fans do not energize until return line temperature exceeds a setpoint. Until the reactor pool transfers enough heat from fuel to secondary cooling discharge to cause tower return line temperature to exceed the setpoint for fan operation, the heat transfer mechanism in the cooling tower is natural convection . Therefore, "Natural Convection (NC)" is also a correct answer. Thank you for your attention, P. M. Whaley Kansas State University Nuclear Reactor Facility Manager

NRC Resolutions B.03: Comment accepted as written, answer key modified to recognize ‘a’ as a second correct

answer. B.06 Comment accepted as written; answer key modified, changing answers for part c and d

to LCO and SL respetively. C.05 Comment accepted as written, answer key modified to recognize ‘NC’ as a second

correct answer.

OPERATOR LICENSING RETAKE EXAMINATION ALL SECTIONS

With Answer Key KANSAS STATE UNIVERSITY Week of August 18, 2008

Section A L Theory, Thermo & Facility Operating Characteristics

QUESTION A.01 [2.0 points, ½ each] Identify whether each of the following conditions will INCREASE or DECREASE the shutdown margin of a reactor. a. Raising moderator temperature (Assume negative temperature coefficient). b. Insertion of a positive reactivity worth experiment. c. Burnout of a burnable poison. d. Fuel depletion. QUESTION A.02 [1.0 point] Reactor power increased from 1 watt to 5 kW in 186 seconds. What was the period? a. 10 secs. b. 22 secs. c. 30 secs. d. 116 secs. QUESTION A.03 [1 point] “Excess Reactivity” is … a. a measure of the additional fuel loaded to overcome fission product poisoning. b. a measure of remaining control rod worth with the reactor exactly critical. c. the combined control rod negative reactivity worth required to keep the reactor shutdown. d. the maximum reactivity by which the reactor can be shutdown with one control rod fully withdrawn. QUESTION A.04 [1.0 point] Which statement best describes Xe135 behavior immediately following a Reactor Scram? Xenon135 concentration … a. decreases due to production of I135 directly from fission stops. b. decreases due to production from decay of I135 being less than Xe135 decay rate. c. increases due to production from Te135 exceeding Xe135 decay. d. increases due to production from decay of I135 exceeding Xe135 decay.

QUESTION A.05 [1.0 point] You’ve just increased power at a research reactor. As a result fuel temperature increased from 100°C to 120°C. For this reactor the fuel temperature coefficient (αtf) is -0.01% )k/k/°C, and the average rod worth for the regulating rod is 0.05% )k/k/inch. How far and in what direction must you move the regulating rod to compensate? (Assume all other factors which could affect reactivity remain unchanged.) a. 2 inches inward b. 2 inches outward c. 4 inches inward d. 4 inches outward QUESTION A.06 [1.0 point] Which factor of the Six Factor formula is most easily varied by the reactor operator? a. Thermal Utilization Factor (f) b. Reproduction Factor (η) c. Fast Fission Factor (ε) d. Fast Non-Leakage Factor (Lf) QUESTION A.07 [2.0 points. ½ each] The listed isotopes are all potential daughter products due to the radioactive decay of 35Br87. Identify the type of decay necessary (Alpha, Beta, Gamma or Neutron emission) to produce each of the isotopes. a. 33As83 b. 35Br86 c. 35Br87 d. 36Kr87 QUESTION A.08 [1.0 point] In a reactor the thermal neutron flux (Ø) is 2.5 × 1012 fissions/cm2/second, and the macroscopic cross-section (Σf) for fission is 0.1 cm-1. The fission rate is a. 2.5 × 1011 fissions/cm/second b. 2.5 × 1013 fissions/cm/second c. 2.5 × 1011 fissions/cm3/second d. 2.5 × 1013 fissions/cm3


QUESTION A.09 [1.0 point] The primary reason a neutron source is installed in the reactor is to … a. allow for testing and irradiation of experiments when the core is shutdown. b. supply the neutrons required to start the chain reaction for subsequent reactor startups. c. provide a neutron level high enough to be monitored for a controlled reactor startup. d. increase the excess reactivity of the reactor which reduces the frequency for refueling. QUESTION A.10 [1.0 point] 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. QUESTION A.11 [1.0 point] 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. Thermal utilization factor (f). b. Resonance escape probability (p). c. Thermal non-leakage probability (‹th). d. Reproduction factor (η). QUESTION A.12 [1.0 point] An experimenter makes an error loading a rabbit sample. Injection of the sample results in a 100 millisecond period. If the scram which causes the reactor to shutdown is set at 1.5 MW and the scram delay time is 0.1 seconds, WHICH ONE of the following is the peak power of the reactor at shutdown. a. 1.5 MW b. 1.65 MW c. 4.1 MW d. 33 GW

QUESTION A.13 [1.0 point] The term "PROMPT JUMP" refers to: a. the instantaneous change in power due to raising a control rod. b. a reactor which has attained criticality on prompt neutrons alone. c. a reactor which is critical using both prompt and delayed neutrons. d. a negative reactivity insertion which is less than βeff. QUESTION A.14 [1.0 point] The delayed neutron precursor (β) for U235 is 0.0065. However, when calculating reactor parameters you use βeff with a value of ~0.0070. Why is βeff larger than β? a. Delayed neutrons are born at higher energies than prompt neutrons resulting in a greater worth for

the neutrons. b. Delayed neutrons are born at lower energies than prompt neutrons resulting in less leakage during

slowdown to thermal energies. c. The fuel also contains U238 which has a relatively large β for fast fission. d. U238 in the core becomes Pu239 (by neutron absorption), which has a higher β for fission. QUESTION A.15 [1.0 point] Which of the following atoms will cause a neutron to lose the most energy during an elastic scattering reaction? a. O16 b. C12 c. U235 d. H1 QUESTION A.16 [1.0 point] By definition, an exactly critical reactor can be made prompt critical by adding positive reactivity equal to

… a. the shutdown margin b. the Kexcess margin c. the βeff value d. 1.0 %ΔK/K.


QUESTION A.17 [1.0 point] Which ONE of the following statements is the definition of REACTIVITY? a. A measure of the core's fuel depletion. b. A measure of the core's deviation from criticality. c. Equal to 1.00 ΔK/K when the reactor is critical. d. Equal to 1.00 ΔK/K when the reactor is prompt critical. QUESTION A.18 [1.0 point] 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.

Section B Normal, Emergency and Radiological Control Procedures

QUESTION B.01 [1.0 point] The Total Effective Dose Equivalent (TEDE) is defined as the sum of the deep-dose equivalent and the committed effective dose equivalent. The deep-dose equivalent is related to: a. the dose to organs or tissues. b. the external exposure to the skin or an extremity. c. the external exposure to the lens of the eye. d. the external whole-body exposure. QUESTION B.02 [2.0 points, 0.5 each] Match the 10 CFR Part 55 requirements listed in Column A for an actively licensed operator with the correct time period from Column B. Column B answers may be used once, more than once, or not at all. Column A Column B a. License Expiration 1 year b. Medical Examination 2 years c. Requalification Written Examination 3 years d. Requalification Operating Test 6 years. QUESTION B.03 [1.0 point] Which ONE of the following conditions is permitted during reactor operation? a. Continuous air monitor in reactor bay inoperable due to maintenance. b. A pulse reactivity insertion of $3.75. c. Startup with the period scram bypassed. d. Operating in steady state mode with the linear power channel inoperable. QUESTION B.04 [1.0 point] Which ONE of the following is expressly forbidden by the Operations Manual? a. Carbon tetrachloride in the reactor bay. b. Gasoline in the reactor bay. c. Acetone in the reactor. d. Mercury-glass thermometer in the reactor pool.


QUESTION B.05 [1.0 point] The dose rate 10 feet from a point gamma source is 25 mR/hr. A person working for 1.5 hours at 3 feet from the source will receive a dose of: a. 83 mR. b. 125 mR. c. 278 mR. d. 417 mR. QUESTION B.06 [2.0 points, ½ each] 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. If all fuel elements are stainless steel clad, the reactivity worth of any individual EXPERIMENT SHALL NOT

exceed $2.00 b. Power level SHALL NOT exceed 1,250 kW(th) in STEADY STATE MODE of operation c. Water temperature at the exit of the reactor pool SHALL NOT exceed 130�F with flow through the primary

cleanup loop d. Steady state fuel temperature shall not exceed 750°C. QUESTION B.07 [1.0 point] Which ONE of the following statements describes a reactivity limitation imposed on experiments? a. The absolute reactivity worth of all experiments in the reactor shall not exceed $2.00. b. An experiment which will not cause a 20-second period can be inserted in the core when the reactor is at

power. c. When determining the absolute reactivity worth of an experiment, the reactivity effects associated with the

moderator temperature are to be considered. d. No experiment shall be inserted or removed unless all control blades are fully inserted. QUESTION B.08 [1.0 point] According to Experiment No. 1, "Isotope Production," removal of any material from a region of significant neutron flux must be done in the presence of: a. the Reactor Supervisor. b. a Senior Reactor Operator. c. a representative of the University Radiation Safety Office. d. a person approved by the Reactor Supervisor who is trained in the safe handling of radioactive materials.


QUESTION B.09 [1.0 point] In accordance with the Technical Specifications, which Reactor Safety System scrams are required to be operable in BOTH the Steady-State and Pulse modes? a. Fuel temperature scram b. Linear channel high power scram c. Manual scram d. Period scram. QUESTION B.10 [1.0 point] A survey instrument with a window probe is used to measure the beta-gamma dose rate from an irradiated experiment. The dose rate is 100 mrem/hour with the window open and 60 mrem/hour with the window closed. The gamma dose rate is: a. 100 mrem/hour. b. 60 mrem/hour. c. 40 mrem/hour. d. 160 mrem/hour. QUESTION B.11 [1.0 point] In the event of a reportable occurrence, the reactor shall be shutdown and not restarted until authorized by the: a. Reactor Manager b. Reactor Safeguards Committee c. Head, Department of Nuclear and Mechanical Engineering d. U.S. NRC QUESTION B.12 [1.0 point] According to procedure "Experiment 42- Operation of Sample Rapid Transfer System (Rabbit)" which ONE of the following actions should the reactor operator take if an irradiated rabbit sample becomes stuck? a. Notify the reactor supervisor then purge the rabbit system by firing helium into the reactor bay from NAAL. b. Notify the reactor supervisor then reduce reactor power to less than 500W and check gamma radiation levels in

the reactor bay terminal. c. Scram the reactor and notify the reactor supervisor. d. Align the switching coupling in the reactor bay with the reactor bay terminal and notify the reactor supervisor.


QUESTION B.13 [2.0 points, ½ each] The ventilation system is inoperable. Identify whether each of the listed evolutions is allowed, or not allowed per technical specifications. a. Operation of the reactor at 100% steady-state conditions, no experiments in the core. b. Insertion of a $1.00 pulse from a subcritical power level. c. Moving a new (unirradiated) fuel element in the reactor bay. d. Operation of the reactor at 50% steady-state conditions with an experiment which generates Xe135. QUESTION B.14 [1.0 point] Which ONE of the following requires the direct supervision (i.e., presence) of an SRO? a. Control rod calibrations. b. Control rod drop time measurement. c. Pulsing the reactor. d. Discharging radioactive material to sanitary sewer QUESTION B.15 [1.0 point] Following neutron radiography, one must not reenter the reactor bay until: a. The beam port radiation monitor reads less than 10 mR/hr b. Reactor power is reduced to below 5 kW c. The beam port radiation monitor reads less than 100 mR/hr d. Reactor power is reduced to below 5 watts QUESTION B.16 [1.0 point] The Continuous Air Monitor (CAM) is set to alarm at the Maximum allowed Effluent Concentration of: a. Te131 b. I131 c. Xe131 d. Cs131


QUESTION B.17 [1.0 point] A "high radiation area" is: a. an area where airborne radioactive materials, composed wholly or partly of licensed material, exist in

concentrations are In excess of the derived air concentrations (DACs) specified in appendix B, or an individual present in the area without respiratory protective equipment could exceed, during the hours an individual is present in a week, an intake of 0.6 percent of the annual limit on intake (ALI) or 12 DAC-hours.

b. an area accessible to individuals, in which radiation levels could result in an individual receiving a dose

equivalent in excess of 0.005 rem (0.05 mSv) in 1 hour at 30 centimeters from the radiation source or from any surface that the radiation penetrates.

c. an area, accessible to individuals, in which radiation levels from radiation sources external to the body could

result in an individual receiving a dose equivalent in excess of 0.1 rem (1 mSv) in 1 hour at 30 centimeters from the radiation source or 30 centimeters from any surface that the radiation penetrates.

d. an area, access to which is limited by the licensee for the purpose of protecting individuals against undue risks

from exposure to radiation and radioactive materials.

Section C Plant and Rad Monitoring Systems

QUESTION C.01 [2.0 points, ½ each] Match the purification system functions in column A with the purification component listed in column B. (Note items from column B may be used more than once, or not at all.) Column A Column B a. remove floating dust, bug larvae, etc. 1. Demineralizer (Ion Exchanger ) b. remove dissolved impurities 2. Skimmer c. remove suspended solids 3. Filter d. maintain pH QUESTION C.02 [1.0 point] Water returning to the pool from the primary system is ejected through an angled nozzle, which causes a swirling motion in the pool. Which ONE of the following is the PRIMARY purpose for this design? a. To increase the heat transfer rate due to increased convective flow. b. To decrease the activation rate of O16 to N16 due to a decrease in time within the core. c. To increase the transport time for N16 to reach the surface of the pool. d. To break up O16 bubbles in the pool thereby decreasing the production of N16. QUESTION C.03 [1.0 point] Which ONE of the following is the gas used in the pneumatic tube system? a. Air b. CO2 c. N2 d. He QUESTION C.04 [1.0 point] Which ONE of the following Nuclear Instrumentation Channels also supplies Period Indication? a. Startup Channel b. Nuclear Log Wide Range Channel (NLWR-1000) c. Nuclear Multi-Range Power Channel (NMP-1000) d. Nuclear Power Pulse Channel (NPP-1000)


QUESTION C.05 [2.0 points, ½ each] Identify the heat transfer mechanism (Radiation, Forced Convection, Natural Convection or Conduction) for each of

the following: a. Cooling the Core b. Cooling the Pool c. Transfer of heat across the tubes of the heat exchanger. d. Transfer of heat to from cooling tower to air QUESTION C.06 [1.0 point] Using the drawing of a pneumatic tube system provided, identify the valve lineup which will result in sending a "rabbit" INTO the core. OPEN SHUT a. A & B C & D b. C & D A & B c. A & C B & D d. B & C A & D QUESTION C.07 [1.0 point] Which ONE of the following is the actual method used to generate the rod position indication, for the standard control rods on the control panel? a. Voltage changes generated by the movement of a lead screw between two coils of a transformer. b. A ten-turn potentiometer linked to the rod drive motor c. A series of several reed switches which as the rod moves up close to generate a current proportional to rod

position. d. A servo motor connected to the UP and DN buttons which when either button is depressed generates a signal

proportional to rod speed. QUESTION C.08 [1.0 point] Which ONE of the following is the neutron source utilized in the reactor? a. 241Am — 9Be b. 239Pu — 9Be c. 210Po — 9Be d. 124Sb — 9Be


QUESTION C.09 [1.0 point] An approved alternative to discharging water from the reactor bay sump to sewerage is to instead pump it to … a. the primary purification system upstream of the filters. b. the bulk water tank c. the primary makeup storage tank d. the secondary storage tank. QUESTION C.10 [1.0 point] Which ONE of the following methods is the normal procedure for preventing basin water in the cooling tower from freezing when temperature is at or below -10°F? (Assume primary is below 100°F.) a. The three way valve repositions to bypass all secondary flow around the cooling tower. b. The fans are intermittently operated in reverse. c. Heaters built into water sump energize. d. A steam connection from University facilities automatically opens. QUESTION C.11 [1.0 point] The compressed air system supplies which ONE of the following? a. Secondary water control system b. Rabbit system c. Automatic fire control system d. Shim rod drive system QUESTION C.12 [1.0 point] During a survey of the demineralizer ½ hour after shutdown, you note that the dose rate has increased by a factor of 10 over the previous day's reading. Is this normal or abnormal, and why? a. Normal, due to N16 in the coolant. b. Abnormal, due to the concentration of H3 in the demineralizer. c. Abnormal, due to fission products in the demineralizer. d. Normal, due to Ar41 entrained in the coolant system.


QUESTION C.13 [1.0 point] Per technical specifications which ONE of the following safety system functions must be operable for both steady-state and pulsing operations? a. Reactor Power Level Scram b. Pulse Rod Interlock c. Manual Scram Bar d. Control Rod (standard) Position Interlock QUESTION C.14 [1.0 point] The cooling tower fan speed (off, low speed, high speed) is controlled by: a. the temperature of secondary water entering the cooling tower. b. the temperature of primary water entering the heat exchanger. c. the temperature of secondary water leaving the cooling tower. d. the temperature of primary water leaving the heat exchanger. QUESTION C.15 [1.0 point] The North-East Beam Port core-end terminates at: a. The outer surface of the reflector container b. The inner surface of the reflector container c. The center of the core d. The top of the Lazy Susan QUESTION C.16 [1.0 point] Which ONE of the Nuclear Instrumentation channels/circuits listed below does NOT provide an input to the Regulating Rod Automatic Control circuit? a. Nuclear Multi-Range Power Channel (NMP-1000) b. Nuclear Power Pulse Channel (NPP-1000) c. Nuclear Log Wide Range Channel (NLWR-1000) d. Percent Demand Potentiometer


QUESTION C.17 [1.0 point] The purpose of the graphite slugs located at the top and bottom of each fuel rod is to … a. absorb neutrons, thereby reducing neutron embrittlement of the upper and lower guide plates. b. absorb neutrons, thereby reducing neutron leakage from the core. c. reflect neutrons, thereby reducing neutron leakage from the core. d. couple neutrons from the core to the nuclear instrumentation, decreasing shadowing effects. QUESTION C.18 [1.0 point] Which ONE of the following parameters is NOT measured in the Primary Cooling/Purification System Loops? a. Temperature b. Flow Rate c. Conductivity d. pH


A.01 a, INCREASE; b, DECREASE; c, DECREASE; d, INCREASE REF: DOE Fundamentals Handbook, Volume 2, Module 4, Reactor Theory (Reactor Operations), Enabling

Objective 3.6 A.02 b P = P0 e

t/T ln(P/P0) = t/T T = t/(ln(P/P0)) T = (186 sec)/(ln 5000) = 21.8 seconds REF: A.03 b. REF: DOE Fundamentals Handbook, Nuclear Physics and Reactor Theory, Volume A.04 d REF: DOE Fundamentals Handbook, Nuclear Physics and Reactor Theory, Volume A.05 d -0.0001)k/k/°C H +20°C = -0.002)k/k. To compensate you must add +0.002)k/k. (0.002)k/k) ) (0.0005%)k/k/inch) = 4 inches in the positive (outward) direction.

REF: DOE Fundamentals Handbook, Nuclear Physics and Reactor Theory, Volume A.06 a REF: DOE Fundamentals Handbook, Nuclear Physics and Reactor Theory, Volume A.07 a, α, b, n; c, (; d, β- REF: DOE Fundamentals Handbook, Nuclear Physics and Reactor Theory, Volume A.08 c Fission rate = thermal flux (Ø) H macroscopic cross-section (Σf) = 2.5 × 1012 H 0.1 cm-1 = 2.5 × 1011 fissions/cm3/second REF: DOE Fundamentals Handbook, Nuclear Physics and Reactor Theory, Volume A.09 c REF: DOE Fundamentals Handbook, Nuclear Physics and Reactor Theory, Volume A.10 a REF: DOE Fundamentals Handbook, Nuclear Physics and Reactor Theory, Volume A.11 d REF: DOE Fundamentals Handbook, Nuclear Physics and Reactor Theory, Volume A.12 P = P0 e

t/τ, P = 1.5 Mwatt × e0.1/0.1 = 1.5 × e = 4.08 REF: DOE Fundamentals Handbook, Nuclear Physics and Reactor Theory, Volume A.13 a REF: DOE Fundamentals Handbook, Nuclear Physics and Reactor Theory, Volume A.14 b REF: DOE Fundamentals Handbook, Nuclear Physics and Reactor Theory, Volume A.15 d REF: DOE Fundamentals Handbook, Nuclear Physics and Reactor Theory, Volume A.16 c REF: DOE Fundamentals Handbook, Nuclear Physics and Reactor Theory, Volume A.17 b REF: DOE Fundamentals Handbook, Nuclear Physics and Reactor Theory, Volume A.18 a. REF: DOE Fundamentals Handbook, Module 3, Control Rods, page 51.


B.01 d REF: Training Manual, Part B1, Definitions. B.02 a, 6; b, 2; c, 2; d, 1 REF: 10CFR55.53 B.03 c ‘or a’ 2nd correct answer added per facility comment. REF: Procedure No. 11 Reactor Start-up with Period SCRAM Bypassed. (January 2005 NRC exam) B.04 d REF: Operations manual August, 2007, supplied for (January 2008 NRC exam) B.05 d 1st solve for dose rate at 3 feet: (DR10 feet)/102 = (DR3 feet)/3

2 DR3 feet = 25 mR/hr (100/9) = 277.778. In 1.5 hours the worker will get 277.778 H 1.5 = 416.667

REF: Standard NRC Question B.06 a, LCO; b, LSSS; c, SLLCO; d, LCOSL Answer key changed per facility comment. REF: Technical Specifications 3.6, 2.2, 2.1 and 3.8 B.07 a. REF: Technical Specifications, Section I.3. B.08 d. REF: Experiment No. 1, page 4. B.09 c REF: Technical Specifications, Table I. (Note question rewritten to recognize newly approved Technical

specifications) B.10 b REF: Standard NRC Radiation Health Physics Question B.11 b REF: Rewrite of facility supplied question. B.12 c REF: Experiment 42 B.13 a, Allowed; b, Not allowed; c, Allowed; d, Not allowed REF: Technical Specification 3.5. Gaseous Effluent Control B.14 c REF: Facility supplied question. B.15 d REF: Facility supplied question B.16 b REF: Rewrite of facility supplied question. B.17 c REF: Facility supplied question


C.01 a, 2; b, 1; c, 3; d, 1 Ref: Standard NRC purification system question. C.02 c REF: SAR § 5.6 Nitrogen 16 Control System C.03 d REF: SAR § 9.7.3(d) Pneumatic Transfer System (Rabbit) C.04 b REF: SAR § 7.3.1 also Figure 7.5. C.05 a, NC; b, FC; c, Con; d, FC or NC, 2nd correct answer added per facility comment. REF: Standard NRC question C.06 d REF: Standard NRC question C.07 b REF: SAR § 7.3.4(a) Standard Control Rod Drives 1st &, 2nd & 3rd sentences. C.08 a REF: SAR § 4.2.4 Neutron Startup Source C.09 d REF: Procedure No. 24 Sump Water Discharge System C.10 a REF: SAR § 5.3.2 Secondary Cooling Automatic Control System. C.11 a REF: Facility supplied question C.12 c REF: The demineralizer removes ionic impurities. N16, has much too short a half-life, H3 emits much too weak a beta to be detected, and

Ar41 is a noble gas, it will NOT concentrate in the demineralizer. C.13 c REF: Technical Specification 3.4 Safety and Control Rod Operability C.14 c. REF: KSU Training Manual, "General Characteristics," Coolant System. C.15 b REF: Facility Supplied Question modified to meet NRC requirements. C.16 b REF: Procedure No. 23 Automatic Flux Control System C.17 c REF: SAR § 4.2.1 , Reactor Fuel, Figure 4.3. C.18 d REF: SAR § 5.1 Summary Description, Figure 5.1