December 19, 2008 Dr. Donald Wall, Director Nuclear ... · the individual grades to you in a...

December 19, 2008 Dr. Donald Wall, Director Nuclear Radiation Center Washington State University Pullman, WA 99164-1300 SUBJECT: INITIAL EXAMINATION REPORT NO. 50-027/OL-09-01, WASHINGTON STATE

UNIVERSITY TRIGA REACTOR Dear Dr. Wall: During the week of November 17, 2008, the NRC administered operator licensing examinations at your Washington State University TRIGA Reactor. The examinations were conducted according to NUREG-1478, "Operator Licensing Examiner Standards for Research and Test Reactors," Revision 2. Examination questions and preliminary findings were discussed with those members of your staff identified in the enclosed report at the conclusion of the examination. In accordance with Title 10 of the Code of Federal Regulations Section 2.390, a copy of this letter and the enclosures will be available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records (PARS) component of NRC's Agencywide Documents Access and Management System (ADAMS). ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html. The NRC is forwarding the individual grades to you in a separate letter which will not be released publicly. Should you have any questions concerning this examination, please contact Mr. 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. 50-027 Enclosures: 1. Initial Examination Report No. 50-027/OL-09-01 2. Written examination with facility comments incorporated cc without enclosures: See next page

December 19, 2008 Dr. Donald Wall, Director Nuclear Radiation Center Washington State University Pullman, WA 99164-1300 SUBJECT: INITIAL EXAMINATION REPORT NO. 50-027/OL-09-01, WASHINGTON STATE

UNIVERSITY TRIGA REACTOR Dear Dr. Wall: During the week of November 17, 2008, the NRC administered operator licensing examinations at your Washington State University TRIGA Reactor. The examinations were conducted according to NUREG-1478, "Operator Licensing Examiner Standards for Research and Test Reactors," Revision 2. Examination questions and preliminary findings were discussed with those members of your staff identified in the enclosed report at the conclusion of the examination. In accordance with Title 10 of the Code of Federal Regulations Section 2.390, a copy of this letter and the enclosures will be available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records (PARS) component of NRC's Agencywide Documents Access and Management System (ADAMS). ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html. The NRC is forwarding the individual grades to you in a separate letter which will not be released publicly. Should you have any questions concerning this examination, please contact Mr. 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. 50-027 Enclosures: 1. Initial Examination Report No. 50-027/OL-09-01 2. Written examination with Facility Comments Incorporated cc without enclosures: See next page DISTRIBUTION w/ encls.: PUBLIC PRTB r/f RidsNRRDPRPRTA RidsNRRDPRPRTB Facility File (CRevelle) O-12 G-15 ADAMS ACCESSION #: ML083390576 TEMPLATE #:NRR-074

OFFICE PRTB:CE IOLB:LA E PRTB:SC

NAME PDoyle pvd CRevelle car JEads jhe

DATE 12/05/08 12/12/08 12/19/08

OFFICIAL RECORD COPY

Washington State University Docket No. 50-27 cc: Dr. James T. Elliston Chair, Reactor Safeguards Committee Nuclear Radiation Center Washington State University P.O. Box 641300 Pullman, WA 99164 - 1300 Mr. Christopher Corey Hines Reactor Supervisor, Nuclear Radiation Center Washington State University P.O. Box 641300 Pullman, WA 99164 - 1300 Mr. Steve Eckberg, CHP Director, Radiation Safety Office Washington State University P.O. Box 641302 Pullman, WA 99163-1302 Director Division of Radiation Protection Department of Health 7171 Cleanwater Lane, Bldg #5 P.O. Box 47827 Olympia, WA 98504-7827 Office of the Governor Executive Policy Division State Liaisons Officer P.O. Box 43113 Olympia, WA 98504-3113 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.: 50-027/OL-09-01 FACILITY DOCKET NO.: 50-027 FACILITY LICENSE NO.: R-76 FACILITY: Washington State University TRIGA EXAMINATION DATES: November 18 – 19, 2008 SUBMITTED BY: _________/RA/______________ 12/05/08___ Paul V. Doyle Jr., Chief Examiner Date SUMMARY: During the week of November 17, 2008, the NRC administered operator licensing examinations to 3 operator licensing candidates at the Washington State University TRIGA reactor. All three license candidates passed their respective examinations. As noted below the facility submitted their comments prior to the examiner leaving the site. All comments have been reviewed and incorporated into the examination included as attachment 2 to this document. REPORT DETAILS 1. Examiners: Paul V. Doyle, Chief Examiner, NRC 2. Results:

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

Written 3/0 0/0 3/0

Operating Tests 3/0 0/0 3/0

Overall 3/0 0/0 3/0

3. Exit Meeting: Paul V. Doyle Jr., NRC, Examiner

Donald Wall, Nuclear Radiation Center, Director The chief examiner (CE) thanked the facility for their support in administering the examinations. The CE also noted that he did not observe any generic weaknesses on the part of the candidates; rather they did very well during their walkthrough examinations. Finally, the facility staff submitted their written examination comments before the examiner left the facility. ENCLOSURE 1

OPERATOR LICENSING EXAMINATION With Answer Key WASHINGTON STATE UNIVERSITY TRIGA

REACTOR NOVEMBER 18, 2008

Enclosure 2

Section A L Theory, Thermo & Facility Operating Characteristics

QUESTION A.01 [1.0 point] Following a scram, the value of the stable reactor period is: a. infinity, since neutron production has been terminated b. about 50 seconds, because the rate of negative reactivity insertion rapidly approaches zero. c. about -10 seconds, as determined by the rate of decay of the shortest lived delayed neutron

precursors. d. about -80 seconds, as determined by the rate of decay of the longest lived delayed neutron

precursors. QUESTION A.02 [1.0 point] What are the three materials that are designed as moderators/reflectors, for your reactor? a. Zirconium Hydride [ZrH2], Concrete, and Graphite b. Water, Graphite, and Zirconium Hydride [ZrH2] c. Graphite, Water, and Aluminum d. Aluminum, Concrete, and Water QUESTION A.03 [1.0 point] The reactor is subcritical with a Keff of 0.96 and 30 counts per second indicated. After a fuel element is removed the count rate drops to 10 counts per second. No other changes have occurred. What is the Keff of the core with the fuel element removed? a. 0.9733 b. 0.8800 c. 0.8400 d. 0.8000 QUESTION A.04 [1.0 point] Which ONE of the following statements correctly describes a "THERMAL NEUTRON"? a. The primary source of thermal energy increase in the reactor core during reactor operation. b. A neutron at resonant capture energy levels. c. A neutron that experiences no net change in energy after several collisions with atoms of the moderator. d. A neutron in the 3-6 megawatt energy range.


QUESTION A.05 [1.0 point] The neutron microscopic cross-section for absorption (σa) of an isotope generally Y a. increases as neutron energy increases b. decreases as neutron energy increases c. increases as target nucleus mass increases d. decreases as target nucleus mass increases QUESTION A.06 [1.0 point] You are about to perform a $1.35 pulse of the reactor. Earlier in the day you performed a $1.95 pulse which resulted in a Peak Power reading of 1800 Megawatts. Which ONE of the following is the expected Peak Power of the $1.35 pulse? a. 570 Megawatts. b. 625 Megawatts. c. 1140 Megawatts. d. 1250 Megawatts. QUESTION A.07 [2.0 points, 2'5 each] A FISSILE material is one which will fission upon the absorption of a THERMAL neutron. A FERTILE material is one which will produce a fissile material after absorption of a neutron and subsequent decay. Identify each of the isotopes listed as either FISSILE or FERTILE. a. 90Th232 b. 92U

233 c. 92U

235 d. 92U

238 e. 94Pu239 QUESTION A.08 [1.0 point] With the reactor on a constant period, which of the following changes in reactor power would take the LONGEST time? a. 5% — from 1% to 6% b. 15% — from 20% to 35% c. 20% — from 40% to 60% d. 25% — from 75% to 100%


QUESTION A.09 [1.0 point] You are assigned to check the operation of a new nuclear instrumentation channel. You know that the reactor will stabilize with a - 80 second period shortly after shutdown. To check the channel you measure the time for power to decrease by a factor of 10. This time should be approximately… a. 45 seconds (¾ minute) b. 90 seconds (1-½ minutes) c. 135 seconds (2-¼ minutes) d. 180 seconds (3 minutes)

QUESTION A.10 [2.0 points, ½ each] Match each term in column A with the correct definition in column B. Column A Column B a. Prompt Neutron 1. A neutron in equilibrium with its surroundings. b. Fast Neutron 2. A neutron born directly from fission. c. Thermal Neutron 3. A neutron born due to decay of a fission product. d. Delayed Neutron 4. A neutron at an energy level greater than its surroundings. QUESTION A.11 [1.0 point] The Reactor Operator started up the reactor, and has been at 100% power for 3 hours. The Reactor Operator notes that several small control rod withdrawals are required to maintain power at 100%. Which of the following is the reason for these rod withdrawals? a. Fuel temperatures are decreasing. b. Xenon is building in to equilibrium concentration. c. Pool water temperatures are decreasing. d. Samarium is burning out from peak to equilibrium concentration. QUESTION A.12 [1.0 point] Which ONE of the following is the PRINCIPAL source of heat in the reactor an hour after shutdown? a. Stored energy from the reactor and core materials b. Spontaneous fission within the core c. Decay of fission products d. Cosmic radiation causing fission


QUESTION A.13 [1.0 point] Which ONE of listed reactivity coefficients will be the first to act to prevent the reactor from exceeding any technical specification limits following a pulse? a. Fuel Temperature Coefficient b. Bath Temperature Coefficient c. Power Coefficient d. Void Coefficient QUESTION A.14 [1.0 point] Given a control rod worth of 0.1% ΔK/K/inch and an αT of 0.05% ΔK/K/°F. If temperature INCREASES by 9°F, how much and in what direction will the control rod move? a. 4½ inches inward b. 4½ inches outward c. 9 inches inward d. 9 inches outward QUESTION A.15 [1.0 point] Which ONE of the following is the reason that reactor indicated power (count rate) stabilizes several hours after a reactor trip? Assume all instrumentation is operable, and no reactivity changes. a. Subcritical multiplication of source neutrons. b. Continuing decay of the longest lived delayed neutron precursor. c. Neutron level dropping below detection threshold, the detector reading is due to a test signal input

from Nuclear Instrumentation. d. Gamma radiation due to decay of fission products below detection threshold, the detector reading is

due to a test signal input from Nuclear Instrumentation. QUESTION A.16 [1.0 point] A THERMAL neutron has the LEAST probability of being absorbed by which ONE of the following elements? a. 1H

2 b. 2He4 c. 5B

10 d. 54Xe135


QUESTION A.17 [1.0 point] Which statement best describes Xe135 behavior immediately following a Reactor Scram? Xenon135 concentration … a. decreases because I135 production directly from fission stops. b. decreases because its production from the decay of I135 being less than Xe135 decay rate. c. increases because its production from Te135 exceeds the Xe135 decay rate. d. increases because its production from the decay of I135 exceeds the Xe135 decay rate. QUESTION A.18 [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.

Section B Normal, Emergency and Radiological Control Procedures

QUESTION B.01 [1.0 point] Which ONE of the following situations would illustrate a time when the reactor is both shutdown but AND secured? a. One of the shim rod drives is removed for inspection; the rod is decoupled and is fully inserted into the core, all

other shim rods are fully inserted and the console key is in the ‘off’ position and removed. b. All shim rods are fully inserted; the console key is in the ‘off’ position and removed, while fuel is being

rearranged in the fuel storage racks. c. The shim rods are withdrawn to a subcritical position, the core is subcritical by $1.20. d. An experiment having a reactivity of 50¢ is being installed in the central thimble with all shim rods fully inserted

and the key removed. QUESTION B.02 [1.0 point] According to Technical Specification 3.10 “Nonsecured experiments shall have reactivity worths less than … a. $.25 b. $.50 c. $.75 d. $1.0 QUESTION B.03 [1.0 point] An accessible area within the facility has general radiation levels of 325 mrem/hour. What would be the EXPECTED posting for this area? a. "Caution, Airborne Radioactivity Area" b. "Caution, Radiation Area" c. "Danger, High Radiation Area" d. "Grave Danger, Very High Radiation Area" QUESTION B.04 [1.0 point] A small radioactive source is to be stored in the reactor building. The source reads 2 R/hr at 1 foot. Assuming no shielding is to be used, a Radiation Area barrier would have to be erected from the source at least a distance of approximately: a. 400 feet b. 40 feet c. 20 feet d. 10 feet


QUESTION B.05 [1.0 point] Although you are current on you 10CFR55 mandated requalification requirements, you have been unable to perform the functions of your license for the past 6 months. Per the Regulations, prior to resuming licensed activities you must perform your license functions under the direction of an RO or SRO as appropriate for a minimum of ___ hours. a. 4 b. 6 c. 12 d. 40 QUESTION B.06 [1.0 point] The reactor is xenon free, with no experiments in the core. Given the following reactivity worths, calculate the Shutdown Margin per the technical specification definition. Safety Blade #1: 2.28$ Safety Blade #2: 3.22$ Safety Blade #3: 3.31$ Safety Blade #4: 4.01$ Servo rod: 0.40$ Excess Reactivity: 3.42$ a. 9.80 b. 9.40 c 5.79 d. 5.39 QUESTION B.07 [1.0 point] 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.” Per 10CFR50.54(y), as a minimum, this action must be approved by … a. a Reactor Operator licensed at the facility. b. a Senior Reactor Operator licensed at the facility. c. the Facility Manager (or equivalent at facility). d. the U.S. Nuclear Regulatory Commission Project Manager


QUESTION B.08 [1.0 point] Which One of the following conditions is a violation of a Limiting Condition for Operation? a. Core excess reactivity is $6.00. b. During a power calibration, actual power was found to be 1.13 MW. c. Pool conductivity is 6 x 10-5 mhos/cm. d. During a pulse, a fuel element temperature reached 760°C QUESTION B.09 [1.0 point] Experiments may not be lowered down to the Radiochemistry Lab via the between floors transfer tube when the dose rate exceeds: a. 50 mR/hr. b. 75 mR/hr. c. 100 mR/hr. d. 200 mR/hr. QUESTION B.10 [1.0 point] A radioactive source generates a reading of 100 mr/hr at a distance of 10 feet. With two inches of lead shielding the reading drops to 50 mr/hr at a distance of 10 feet. If you were to add another four inches of the same type of shielding, the reading at 10 feet would drop to … a. 25 mr/hr b. 12½ mr/hr c. 6¼ mr/hr d. 3⅛ mr/hr QUESTION B.11 [2.0 points, ½ each] Identify each of the actions listed below as a Channel Check, Channel Test, or Channel Calibration. a. Verifying overlap between Nuclear Instrumentation meters. b. Replacing an RTD with a precision resistance decade box, to verify proper channel output for a given

resistance. c. Performing a calorimetric (heat balance) calculation on the primary system, then adjusting Nuclear

Instrumentation to agree. d. During shutdown you verify that the period meter reads -80 seconds.


QUESTION B.12 [1.0 point] There are two SROs and one unlicensed RO trainee in the control room with the reactor operating. If one of the SROs becomes sick, what restrictions are placed on reactor operation? a. The trainee may operate the reactor as long as the remaining SRO remains within the confines of the Nuclear

Radiation Center. b. The trainee may operate the reactor as long as the remaining SRO directs actions from within the confines of

the control room. c. The reactor may continue to operate with the SRO on the control panel; the trainee may be "on call". d. The reactor must be shutdown, until a second licensed individual comes to the facility. QUESTION B.13 [1.0 point] Which ONE of the SCRAMS listed is NOT required for reactor operations by Technical Specifications (Table 3.1)? a. Nuclear Instrumentation Detector High Voltage Failure b. Short Period c. High Fuel Temperature d. Nuclear Instrumentation High Flux QUESTION B.14 [1.0 point] Which one of the following is the MINIMUM level of approval to permit insertion or withdrawal of a sample from the reactor during operations? a. A reactor staff member. b. The Reactor Operator. c. The on-duty Senior Reactor Operator. d. The Reactor Supervisor. QUESTION B.15 [1.0 point] Which one of the following is NOT a condition for double encapsulation of a sample? If the release of sample material into the reactor pool could cause… a. Excessive corrosion on the reactor or experimental facilities. b. Greater than $0.25 reactivity insertion. c. Violent chemical reaction. d. Excessive contamination or production of airborne radioactivity.


QUESTION B.16 [1.0 point] You initially remove a sample from the pool reading 1 R/hr at 30 cm from the source. You then replace the sample in the pool. An hour later you remove the sample and the reading is now 390 mR/hr at 30 cm. You again replace the sample back in the pool. How much longer should you wait to be able to bring out the sample without generating a high radiation area? a. ½ hour b. 1 hour c. 1½ hours d. 2 hours QUESTION B.17 [1.0 point] Which one of the following is the MINIMUM reactor period allowed by SOP for power level changes for training purposes? a. 100 seconds. b. 30 seconds. c. 10 seconds. d. 1 second. QUESTION B.18 [1.0 point] Which ONE of the listed emergency classifications is NOT applicable at Washington State University? a. Notification of Unusual Event b. General Emergency c. Safety Event – (Non-Reactor Related) d. Alert QUESTION B.19 [1.0 point] Match the annual dose limit values to the type of exposure. Type of Exposure Annual Dose Limit Value a. Extremities 1. 0.1 rem. b. Lens of the Eye 2. 5.0 rem. c. Occupational Total Effective Dose Equivalent (TEDE) 3. 15.0 rem. d. TEDE to a member of the public 4. 50.0 rem.

Section C Plant and Rad Monitoring Systems and Radiological Control Procedures

QUESTION C.01 [2.0 points, ½ each] Match the purification system conditions listed in column A with their respective causes listed in column B. Each choice is used only once. Higher than normal … Column A Column B a. Radiation Level at demineralizer. 1. Channeling in demineralizer. b. Radiation Level downstream of demineralizer. 2. Fuel element failure. c. flow rate through demineralizer. 3. High temperature in demineralizer system d. pressure upstream of demineralizer. 4. Clogged demineralizer QUESTION C.02 [2.0 points, 3 each] For the eight console alarms listed below indicate whether they will cause an alarm only or a scram. a. Continuous Air Monitor b. Low Pulse Air c. High Conductivity d. Beam Port Plugs e. Low Pool Water Level f. Loss of High Voltage to Power Channels g. Conductivity h. High Fuel Temperature QUESTION C.03 [1.0 point] Which one of the following correctly describes the operation of a Thermocouple? a. A bi-metallic strip which winds/unwinds due to different thermal expansion constants for the two metals, one

end is fixed and the other moves a lever proportional to the temperature change. b. a junction of two dissimilar metals, generating a potential (voltage) proportional to temperature changes. c. a precision wound resistor, placed in a Wheatstone bridge, the resistance of the resistor varies proportionally to

temperature changes. d. a liquid filled container which expands and contracts proportional to temperature changes, one part of which is

connected to a lever.


QUESTION C.04 [1.0 point] Which ONE of the following is the main function performed by the DISCRIMINATOR circuit in the Startup Channel? a. To generate a current signal equal and of opposite polarity as the signal due to gammas generated within the

Startup Channel Detector. b. To filter out small pulses due to gamma interactions, passing only pulses due to neutron events within the

Startup Channel Detector. c. To convert the linear output of the Startup Channel Detector to a logarithmic signal for metering purposes. d. To convert the logarithmic output of the metering circuit to a δt (delta time) output for period metering purposes. QUESTION C.05 [1.0 point] Which ONE of the following describes the response of the five control blades (rods) to a reactor scram signal during NORMAL operation? a. All five control blades (rods) will scram. b. Shim blades #1, #2 and #4 will scram. Transient rod #3 and regulating blade #5 will remain as is. c. Shim blades #1, #2 and #4, and Transient rod #3 will scram. Regulating blade #5 will remain as is. d. Shim blades #1, #2 and #4 and Regulating blade #5 will scram. Transient Rod #3 will remain as is. QUESTION C.06 [1.0 point] Which one of the following describes the operation of the containment building ventilation automatic dampers on a signal which causes the system to go from normal to dilute mode? a. Dampers 1 and 4 close. Dampers 2 and 3 open. Damper 6 maintains static pressure. b. Dampers 2, 3 and 6 close. Damper 1 opens. Damper 4 maintains static pressure. c. Dampers 2 and 3 close. Dampers 1 and 4 open. Damper 6 maintains static pressure. d. All Dampers close. QUESTION C.07 [1.0 point] Which one of the following methods is used to prevent freezing in the secondary system during cold weather? a. A heater in the secondary sump, controlled from by the control room operator. b. A heater in the secondary sump, automatically controlled by a thermostat. c. Addition of chemicals to reduce the freezing temperature of the secondary coolant. d. At low temperatures an auxiliary operator is sent to heat the cooling fans with a heat gun (i.e. a hair dryer).


QUESTION C.08 [1.0 point] WHICH ONE of the following detectors is used primarily to measure N16 release to the environment? a. NONE, N16 has too short a half-life to require environmental monitoring. b. Continuous Air Monitor c. Exhaust Gas Monitor d. Bridge Area Monitor QUESTION C.09 [1.0 point] During which ONE of the following conditions is the Absolute filter in the ventilation system in use? a. Automatic and Isolation Modes b. Automatic and Dilute Modes c. Automatic Mode only d. Dilution Mode only QUESTION C.10 [1.0 point] Which ONE of the following is the purpose of the diffuser pump? a. Increase heat transfer rate due to increased mixing in the pool. b. Decrease the activation rate of O16 to N16 due to reduced time in core. c. Increase transport time for N16 to reach surface of pool. d. Break up of O16 bubbles in pool, thereby decreasing production of N16. QUESTION C.11 [1.0 point] Which ONE of the following is the neutron source use for reactor startup? a. 241Am–9Be (Americium Beryllium) b. 239Pu–9Be (Plutonium Beryllium) c. 210Po–9Be (Polonium Beryllium) d. 123Sb–9Be (Antimony Beryllium)


QUESTION C.12 [1.0 point] You are withdrawing Control Blade #2 per SOP-4, Appendix A, part D, Withdrawal sequence for pulsing operation. A trainee inadvertently deenergizes the solenoid between the accumulator tank and the transient rod cylinder. Which ONE of the following describes the effect on the transient rod (#3)? a. Move out to its maximum upper limit. b. Drop via gravity into the core. c. Remain at its present position (fully in). d. Move out to its maximum upper limit, and then scram after 15 seconds. QUESTION C.13 [1.0 point] Which ONE (1) of the following Modes of the operation of the reactor ventilation system provides approximately 4500 CFM of treated external air into the pool area? a. Auto mode b. Emergency mode c. Isolation mode d. Dilution Mode QUESTION C.14 [1.0 point] What is one of the purposes for the neutron count interlock? a. To preclude the reactor from going super critical before the instrumentation starts to detect the neutron level in

the core. b. To provide a reference point where all instruments undergo a check before the reactor is brought to a critical

position. c. To allow for all experiments to be installed before the reactor is critical. d. To ensure a sufficient neutron count to start the chain reaction. QUESTION C.15 [1.0 point] Which ONE of the following neutron flux monitoring channels provides a signal indicating the period of the reactor? a. Linear Power Channel b. Count Rate Channel c. Log Power Channel d. Percent Power Channel


QUESTION C.16 [1.0 point] Which one of the following parameters provides the first and primary indication of a fuel element cladding failure? a. Increase counts on the Ar41 monitor. b. Increasing pool water conductivity. c. Increasing counts on the Continuous Air Monitoring d. Increasing N16 counts. QUESTION C.17 [1.0 point] The quick disconnect pin of a shim rod has been inadvertently removed and not replaced. When the operator attempts to raise the blade out of the core: a. the blade in light will go out, however the position indication will not function normally. b. the blade in light will go out and the position indication will appear to function properly. c. the blade in light will stay on and the position indication will not function normally. d. the blade in light will stay on, however the position indication will appear to function normally. QUESTION C.18 [1.0 point] The instrumented fuel elements are … a. 30/20 LEU fuel elements containing a neutron flux wire detector b. standard LEU fuel elements containing a neutron flux wire detector c. 30/20 LEU fuel elements containing a “K” type thermocouple d. standard LEU fuel elements containing a “K” type thermocouple.


A.01 d REF: DOE Fundamentals Handbook, Nuclear Physics and Reactor Theory, Volume A.02 b REF: DOE Fundamentals Handbook, Nuclear Physics and Reactor Theory, Volume A.03 b. CR1/CR2 = [1 - Keff2]/[1 - Keff1] 30/10 = [1 - Keff]/[1 - 0.96] 1 - Keff = 3 x 0.04 = 0.12 Keff = 0.88 REF: DOE Fundamentals Handbook, Nuclear Physics and Reactor Theory, Volume A.04 c REF: DOE Fundamentals Handbook, Nuclear Physics and Reactor Theory, Volume A.05 b REF: DOE Fundamentals Handbook, Nuclear Physics and Reactor Theory, Volume A.6 c P1/ρ1

2 = P2/ρ22 P2 = 1800 Mwatt × (1.55)2]/(1.95)2 = 1137 Mwatt

Ref: DOE Fundamentals Handbook, Nuclear Physics and Reactor Theory, Volume A.07 a, fer, b, fiss; c, fiss; d, fer; e, fiss answers added per facility comment. New question answer omitted. REF: DOE Fundamentals Handbook, Nuclear Physics and Reactor Theory, Volume A.08 a. REF: P = P0 e

t/τ ln(P/P0) = t/τ Since you are looking for which would take the longest time it is obvious to the most casual of observers that the ratio P/P0 must be the largest.

A.09 d REF: P/P0 = e-T/τ ln(0.1) = - T(time)/τ(-80sec) Time = ln (0.1) × -80 sec = 184 seconds ≈ 3 minutes A.10 a, 2; b, 4; c, 1; d, 3 REF: Burn, R., Introduction to Nuclear Reactor Operations, 8 1988, '' 3.2.2, p. 3 7 A.11 a b Answer changed per facility comment (typo) REF: Standard NRC Question1 A.12 c 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: inchKKFK

KF

−Δ°−

Δ×°

001.0

0005.09

= 4.5 inches REF: DOE Fundamentals Handbook, Nuclear Physics and Reactor Theory, Volume A.15 a REF: DOE Fundamentals Handbook, Nuclear Physics and Reactor Theory, Volume A.16 b REF: DOE Fundamentals Handbook, Nuclear Physics and Reactor Theory, Volume A.17 d REF: DOE Fundamentals Handbook, Nuclear Physics and Reactor Theory, Volume A.18 a REF: DOE Fundamentals Handbook, Nuclear Physics and Reactor Theory, Volume


B.01 b REF: Technical Specifications § 1 Definitions 1.1 Reactor Operating Conditions B.02 d REF: Technical Specification § 3.10 B.03 c REF: Standard NRC question B.04 c

REF: ftXftXXDRDRX

XDR

XDR 204001

52000 222

22

12

1222

1

222

1 ==×===

B.05 b REF: 10CFR55.53.f(1), also WSU Requalification Plan § 4.c. B.06 d REF: SOP #5, § N, Shutdown Margin B.07 b REF: 10CFR50.54(y) B.08 c REF: WSU TS §§ 3.1, 3.3, 3.4 and 3.13 B.09 c Answer originally omitted. REF: SOP-2 § B.10 B.10 b REF: 2” = one-half thichness (T½). Using 3 half-thickness will drop the dose by a factor of (½)3 = ⅛. 100/8 = 12.5 B.11 a, check; b, test; c, calibration; d, check REF: WSU Technical Specifications, § 1.0 Definitions, p. 4 B.12 b REF: SOP-4, §§ A(2), (3) & (4), page 1. B.13 b REF: RO Training Manual, Unit 11, Scram Circuitry Figure, and Technical Specifications, Table 3.1. B.14 b. REF: WSU NRC SOP #1, Page 8 & 9, Section F. B.15 b. REF: WSU NRC SOP #1, Page 10, Section I. B.16 c REF: It = I0 e

-λt 390 mR/hr ÷ 1000 mR/hr = e-λ1hr ln(0.39) = -λ * 1 hr. λ = 0.9416 hour-1 SOLVING for additional time: If = It e

-λt 100mR/hr = 390 mR/hr e-0.9416 (time) ln (0.25) = -0.9163 * time time = 1.4454


B.17 c. REF: WSU NRC SOP #4, Pages 5, 6 & 7, Sections C.1.e, C.3.b, & D.1.h, and SOP # 16, Page 2, Section C.8. B.18 b REF: Emergency Plan, § 4.0 Emergency Classification System B.19 a, 4; b, 3; c, 2; d, 1 REF: WSU Radiation Protection Program § D


C.01 a, 2; b, 3; c, 1; d, 4 Ref: Standard NRC cleanup loop question. C.02 a, Alarm; b, Alarm; c, Alarm; d, Alarm; e, Alarm; f, Scram; g, Alarm; h, Scram REF: Old NRC exam questions combined and rewritten. C.03 b REF: Standard NRC question C.04 b REF: Standard NRC Question C.05 c REF: New SAR Section 7 C.06 a REF: SOP 5, p. 13. C.07 b REF: WSU, SAR, page 4-30 second paragraph. C.08 a REF: Standard NRC Question C.09 d REF: WSU, SAR, § 3, Figures 3.2.1 (new) & 3.2.1a. C.10 c REF: Standard NRC question. SOP-4, § B.c.b p. 4. C.11 d REF: Unit 11, Table: WSU TRIGA Reactor Characteristics C.12 c REF: FSAR § 4.7, pages 4-19 & 4-21, also SOP-4, Appendix A page 12. C.13 a REF: Emergency plan, Section 8.2 & Pool Room Ventilation System drawing, Fig. 8.2-1 C.14 a REF: SAR, Section 7.3.1 C.15 c REF: SAR, Section 7.3.2 & Figure 7-5 C.16 c REF: Emergency Plan, Fuel Element Failure C.17 d REF: Rewrite of very old NRC Examination Question C.18 c REF: Rewrite of very old NRC Examination Question

December 19, 2008 Dr. Donald Wall, Director Nuclear ... · the individual grades to you in a...

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