ML061710574
| ML061710574 | |
| Person / Time | |
|---|---|
| Site: | 05000134 |
| Issue date: | 06/28/2006 |
| From: | Johnny Eads NRC/NRR/ADRA/DPR/PRTB |
| To: | Laflamme S Worcester Polytechnic Institute |
| Doyle P, NRC/NRR/DPR/PRT, 415-1058 | |
| Shared Package | |
| ML060170447 | List: |
| References | |
| 50-134/06-01 50-134/06-01 | |
| Download: ML061710574 (37) | |
Text
June 28, 2006Mr. Stephen LaFlamme, DirectorNuclear Reactor Facility Worcester Polytechnic Institute 100 Institute Road.
Worcester, MA 01609-2280
SUBJECT:
INITIAL EXAMINATION REPORT NO. 50-134/OL-06-01, WORCESTERPOLYTECHNIC INSTITUTE
Dear Mr. LaFlamme:
During the week of April 24, 2006, the NRC administered an operator licensing examination atyour Worcester Polytechnic Institute Reactor. The examination was conducted according to NUREG-1478, "Non-Power Reactor Operator Licensing Examiner Standards," Revision 1. 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 10 CFR 2.390 of the Commission's regulations, a copy of this letter and theenclosures will be available electronically for public inspection in the NRC Public DocumentRoom or from the Publicly Available Records (PARS) component of NRC's AgencywideDocuments Access and Management System (ADAMS). ADAMS is accessible from the NRC Web site at (the Public Electronic Reading Room) http://www.nrc.gov/reading-rm/adams.html. The NRC is forwarding the individual grades to you in a separate letter which will not bereleased 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 pvd@nrc.gov. Sincerely, /RA/
Johnny Eads, ChiefResearch and Test Reactors Branch B Division of Policy and Rulemaking Office of Nuclear Reactor RegulationDocket No. 50-134
Enclosures:
- 1. Initial Examination Report No. 50-134/OL-06-012. Examination and answer keycc w/encls:Please see next page June 28, 2006Mr. Stephen LaFlamme, Director Nuclear Reactor Facility Worcester Polytechnic Institute 100 Institute Road.
Worcester, MA 01609-2280
SUBJECT:
INITIAL EXAMINATION REPORT NO. 50-134/OL-06-01, WORCESTERPOLYTECHNIC INSTITUTE
Dear Mr. LaFlamme:
During the week of April 24, 2006, the NRC administered an operator licensing examination atyour Worcester Polytechnic Institute Reactor. The examination was conducted according to NUREG-1478, "Non-Power Reactor Operator Licensing Examiner Standards," Revision 1. 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 10 CFR 2.390 of the Commission's regulations, a copy of this letter and theenclosures will be available electronically for public inspection in the NRC Public DocumentRoom or from the Publicly Available Records (PARS) component of NRC's AgencywideDocuments Access and Management System (ADAMS). ADAMS is accessible from the NRC Web site at (the Public Electronic Reading Room) http://www.nrc.gov/reading-rm/adams.html. The NRC is forwarding the individual grades to you in a separate letter which will not bereleased 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 pvd@nrc.gov. Sincerely, /RA/
Johnny Eads, ChiefResearch and Test Reactors Branch B Division of Policy and Rulemaking Office of Nuclear Reactor RegulationDocket No. 50-134
Enclosures:
- 1. Initial Examination Report No. 50-134/OL-06-012. Examination and answer keycc w/encls:Please see next pageDISTRIBUTION w/ encls.:PUBLIC PRTB r/fJEads PIsaacFacility File (EBarnhill) O-6 F-2ADAMS ACCESSION #: ML061710574TEMPLATE #:NRR-074OFFICEPRTB:CE IOLB:LAPRTB:BCNAMEPDoyle*EBarnhill:tls*JEads:tls*DATE06 /14/2006 06/28/2006 06/28/2006OFFICIAL RECORD COPY
Worcester Polytechnic InstituteDocket No. 50-134 cc:
City ManagerCity Hall 455 Main Street, Room 309 Worcester, MA 01608Office of the Attorney GeneralEnvironmental Protection Division
19 th FloorOne Ashburton Place Boston, MA 02180Department of Environmental Quality Engineering 100 Cambridge Street Boston, MA 02180Dr. John F. CarneyProvost and VP Academic Affairs Boynton Hall, 2 nd Floor100 Institute Road Worcester Polytechnic Institute Worcester, MA 01609Gretar Tryggvason, Professor and HeadDepartment of Mechanical Engineering Worcester Polytechnic Institute 100 Institute Road Worcester, MA 01609-2280Dr. William VernetsonTRTR Newsletter Director, Nuclear Facilities University of Florida 202 Nuclear Science Bldg.
Gainesville, FL 32611-8300 U. S. NUCLEAR REGULATORY COMMISSIONOPERATOR LICENSING INITIAL EXAMINATION REPORTREPORT NO.:50-134/OL-04-01FACILITY DOCKET NO.:50-134 FACILITY LICENSE NO.:R-61 FACILITY:Worcester Polytechnic Institute EXAMINATION DATES:April 24 through 27, 2006 SUBMITTED BY:____________________________________________Paul V. Doyle Jr., Chief ExaminerDate
SUMMARY
During the week of April 24, 2006, the NRC administered examinations to 6 Reactor Operator(RO) and one Senior Reactor Operator Upgrade (SRO-U) operator licensing candidates. One RO candidate failed sections A and B of the Written examination and the operating test, and one RO candidate failed section A of the written only. The other four RO candidates and the SRO-U candidate passed all portions of their examinations.REPORT DETAILS1.Examiners: Paul V. Doyle Jr., Chief Examiner2.Results:RO PASS/FAILSRO PASS/FAILTOTAL PASS/FAILWritten4/20/04/2Operating Tests6/01/07/0 Overall4/21/05/23.Exit Meeting:Paul V. Doyle Jr., NRC, Examiner Stephen LaFlamme, WPI, Facility DirectorMr. Doyle thanked Mr. LaFlamme for his support in the administration of theexaminations. Mr. LaFlamme reported that he had no comments on the written examination. Mr. Doyle reported that the candidates were weak in general, not limited to any one system.ENCLOSURE 1 U. S. NUCLEAR REGULATORY COMMISSION RESEARCH AND TEST REACTOR LICENSE EXAMINATION FACILITY:Worcester Polytechnic Institute REACTOR TYPE:PoolDATE ADMINISTERED: 04/24/2006 REGION:1 CANDIDATE:___________________________INSTRUCTIONS TO CANDIDATE:
Answers are to be written on the exam page itself, or the answer sheet provided. Write answers oneside ONLY. Attach any answer sheets to the examination. Points for each question are indicated inparentheses for each question. A 70% in each category is required to pass the examination.
Examinations will be picked up three (3) hours after the examination starts.
% OF CATEGORY % OF CANDIDATE'SCATEGORY VALUE TOTAL SCORE VALUE CATEGORY 20 34 A. REACTOR THEORY, THERMODYNAMICS, AND FACILITYOPERATING CHARACTERISTICS 20 34 B. NORMAL AND EMERGENCYOPERATING PROCEDURES ANDRADIOLOGICAL CONTROLS 18 32 C. FACILITY AND RADIATIONMONITORING SYSTEMS 58 ______
% FINAL GRADEAll work done on this examination is my own. I have neither given nor received aid.
_________________________________________ Candidate's Signature NRC RULES AND GUIDELINES FOR LICENSE EXAMINATIONS During the administration of this examination the following rules apply:
1.Cheating on the examination means an automatic denial of your application and could result inmore severe penalties.
2.After the examination has been completed, you must sign the statement on the cover sheetindicating that the work is your own and you have not received or given assistance in completingthe examination. This must be done after you complete the examination. 3.Restroom trips are to be limited and only one candidate at a time may leave. You must avoid allcontacts with anyone outside the examination room to avoid even the appearance or possibilityof cheating.
4.Use black ink or dark pencil only to facilitate legible reproductions.
5.Print your name in the blank provided in the upper right-hand corner of the examination coversheet. 6.Print your name in the upper right-hand corner of the answer sheets.
7.The point value for each question is indicated in parentheses after the question.
8.Partial credit may be given. Therefore, ANSWER ALL PARTS OF THE QUESTION AND DONOT LEAVE ANY ANSWER BLANK. NOTE: partial credit will NOT be given on multiple choicequestions.
9.If the intent of a question is unclear, ask questions of the examiner only.
10.When turning in your examination, assemble the completed examination with examinationquestions, examination aids and answer sheets. In addition, turn in all scrap paper.
11.When you are done and have turned in your examination, leave the examination area as definedby the examiner. If you are found in this area while the examination is still in progress, yourlicense may be denied or revoked.
A. REACTOR THEORY, THERMODYNAMICS & FACILITY OPERATING CHARACTERISTICSPage 3 QUESTION: 001 (1.00)Which ONE of the following describes the term prompt jump
?a.The instantaneous change in power level due to withdrawing a control rod.
b.A reactor that has attained criticality on prompt neutrons alone.
c.A reactor that is critical using both prompt and delayed neutrons.
d.A negativity reactivity insertion that is less than eff.QUESTION: 002 (1.00)The effective neutron multiplication factor, K eff, is defined as:a.production/(absorption + leakage).
b.(production + leakage)/absorption.
c.(absorption + leakage)/production.
d.absorption/(production + leakage).QUESTION: 003 (1.00)As the moderator temperature increases, the resonance escape probability:a.increases, since the moderator becomes less dense.
b.decreases, since the time required for a neutron to reach thermal energy increases.
c.remains constant, since the effect of moderator temperature change is relatively small.
d.increases, since the moderator-to-fuel ratio increases.
(***** CATEGORY A CONTINUED ON NEXT PAGE *****)A. REACTOR THEORY, THERMODYNAMICS & FACILITY OPERATING CHARACTERISTICSPage 4 QUESTION: 004 (1.00)A 1/M curve is being generated as fuel is loaded into the core. After some fuel elements have beenloaded, the count rate existing at that time is taken to be the new initial count rate, C
- 0. Additionalelements ate then loaded and the inverse count rate ratio continues to decrease. As a result ofchanging the initial count rate:a.criticality will occur earlier (i.e., with fewer elements loaded.)b.criticality will occur later (i.e., with more fuel elements loaded.)c.criticality will occur with the same number of elements loaded as if there were no cangein the initial count rate.d.criticality will be completely unpredictable.QUESTION: 005 (1.00)A reactor is subcritical with a K eff of 0.955. A positive reactivity of 3.5% delta k/k is inserted into the core. At this point, the reactor is:a.supercritical.
b.exactly critical.
c.prompt critical.
d.subcritical.QUESTION: 006 (1.00)During the minutes following a reactor scram, reactor power decreases on a negative 80-second period,corresponding to the half-life of the longest-lived delayed neutron precursors, which is approximately:a.20 seconds.
b.40 seconds.
c.55 seconds.
d.80 seconds.
(***** CATEGORY A CONTINUED ON NEXT PAGE *****)A. REACTOR THEORY, THERMODYNAMICS & FACILITY OPERATING CHARACTERISTICSPage 5 QUESTION: 007 (1.00)A critical reactor with an initial population of 1x10 8 neutrons changes to one with a K eff = 1.001. Considering only the increase in neutron population, how many neutrons (of the increase) will be promptwhen the reactor population changes from the initial generation to the next? Assume eff = 0.007.a.700.
b.7,000 c.99,300.
d.100,000.QUESTION: 008 (1.00)A critical reactor is operating at a steady-state power level of 1.000 kW. Reactor power is increased to anew steady-state power level of 1.004 kW. Neglecting any temperature effects, what reactivity insertionis required to accomplish this?a.0.004 delta k/k.
b.0.4% delta k/k.
c.1.004% delta k/k.
d.Indeterminate, since any amount of positive reactivity could be used.
QUESTION: 009 (1.00)Which factor in the six-factor formula is represented by the ratio:number of neutrons that reach thermal energynumber of neutrons that start to slow downa.fast non-leakage probability.b.resonance escape probability.c.reproduction factor.
d.thermal utilization factor.
(***** CATEGORY A CONTINUED ON NEXT PAGE *****)A. REACTOR THEORY, THERMODYNAMICS & FACILITY OPERATING CHARACTERISTICSPage 6 QUESTION: 010 (1.00)During the neutron cycle from one generation to the next, several processes occur that may increase ordecrease the available number of neutrons. Which ONE of the following factors describes an increasein the number of neutrons during the cycle?a.Thermal utilization factor.
b.Resonance escape probability.c.Thermal non-leakage probability.d.Fast fission factor.QUESTION: 011 (1.00)Which ONE of the following elements will slow down fast neutrons most quickly, i.e., produces thegreatest energy loss per collision?a.Oxygen-16.
b.Uranium-238.
c.Hydrogen-1.
d.Boron-10.QUESTION: 012 (1.00)Which ONE statement below describes a negative fuel temperature coefficient?a.When fuel temperature decreases, negative reactivity is added.
b.When fuel temperature increases, positive reactivity is added.
c.When fuel temperature decreases, reactor power decreases.
d.When fuel temperature decreases, positive reactivity is added.
(***** CATEGORY A CONTINUED ON NEXT PAGE *****)A. REACTOR THEORY, THERMODYNAMICS & FACILITY OPERATING CHARACTERISTICSPage 7 QUESTION: 013 (1.00)A reactor is operating at criticality. Instantaneously, all of the delayed neutrons are suddenly removedfrom the reactor. The K eff of the reactor in this state would be approximately:a.1.007 b.1.000 c.0.000 d.0.993QUESTION: 014 (1.00)For the same constant reactor period, which ONE of the following transients requires the longest tooccur? A power increase of:a.5% of rated power - increasing from 1% to 6% of rated power.
b.10% of rated power - increasing from 10% to 20% of rated power.
c.15% of rated power - increasing from 10% to 25% of rated power.
d.20% of rated power - increasing from 15% to 35% of rated power.QUESTION: 015 (1.00)Which ONE of the following is the description of a thermal neutron?a.A neutron that possesses thermal rather than kinetic energy.
b.The primary source of thermal energy increase in the reactor coolant during reactoroperation.c.A neutron that has been produced in a significant time (on the order of seconds) after itsinitiating fission took place.d.A neutron that experiences no net change in kinetic energy after several collisions withatoms of the diffusing medium.
(***** CATEGORY A CONTINUED ON NEXT PAGE *****)A. REACTOR THEORY, THERMODYNAMICS & FACILITY OPERATING CHARACTERISTICSPage 8 QUESTION: 016 (1.00)Which ONE of the reactions below is an example of a photoneutron source?a.1 H 2 + -> 1 H 1 + n b.92 U 238 -> 35 Br 87 + 57 La 148 + 3n + c.51 Sb 123 + n -> 51 Sb 124 + d.4 Be 9 + -> 6 C 12 + nQUESTION: 017 (1.00)The moderator temperature coefficient of reactivity is -1.25x10
-3 delta k/k/deg.C. When a control rodwith an average rod worth of 0.1% delta k/k/inch is withdrawn 10 inches, reactor power increases andbecomes stable at a higher power level. At this point, the moderator temperature has:a.increases by 8 degrees C.
b.decreased by 8 degrees C.
c.increased by 0.8 degrees C.
d.decreased by 0.8 degrees C.QUESTION: 018 (1.00)Fuel is being loaded into the core. The operator is using a 1/M plot to monitor core loading. Which ONEof the following conditions would result in a non-conservative prediction of core critical mass, i.e., thereactor would reach criticality prior to the predicted critical mass?a.The detector is too far away from the source and the fuel.
b.The detector is too close to the source and the fuel.
c.Excessive time is allowed between fuel elements being loaded.
d.A fuel element is placed between the source and the detector.
(***** CATEGORY A CONTINUED ON NEXT PAGE *****)A. REACTOR THEORY, THERMODYNAMICS & FACILITY OPERATING CHARACTERISTICSPage 9 QUESTION: 019 (1.00)It has been determined that the excess reactivity of a core is 0.50% delta k/k. The most recent rod worthdata show that:Control RodReactivity Worth#13.8% delta k/k#23.5% delta k/k#33.7% delta k/kThe actual shutdown margin (NOT the Tech. Spec. minimum) for this reactor is:a.7.2% delta k/k b.10.5% delta k/k c.11.0% delta k/k d.11.5% delta k/kQUESTION: 020Which ONE of the following factors in the six-factor formula can be varied by the reactor operator?a.Fast fission factor.
b.Reproduction factor.
c.Fast non-leakage factor.
d.Thermal utilization factor.
(***** END OF CATEGORY A *****)B. NORMAL/EMERGENCY OPERATING PROCEDURES AND RADIOLOGICAL CONTROLSP age 10QUESTION: 001 (1.00)Match the 10CFR Part 55 requirements listed in Column A for an actively licensed operator with thecorrect time period in Column B. Column B answers may be used once, more than once, or not at all.Column AColumn Ba.License Expiration1.1 year b.Medical Examination2.2 years c.Requalification Written Examination3.3 years d.Requalification Operating Test4.6 yearsQUESTION: 002 (1.00)In the event of an area evacuation, personnel should proceed to the emergency assembly area, located:a.in the operations boundary.
b.at Freeman Plaza.
c.at the Campus Police building.
d.in Stratton Hall.QUESTION: 003 (1.00)In accordance with 10 CFR 20, the "Annual Limit on Intake (ALI)" refers to:a.the amount of radioactive material taken into the body by inhalation or ingestion in one(1) year which would result in a committed effective dose equivalent of five (5) rems.b.the dose equivalent to organs that will be received from an intake of radioactive materialby an individual during the 50-year period following the intake.c.limits on the release of effluents to an unrestricted environment.
d.the concentration of a given radionuclide in air which, if breathed for a working year of2,000 hours0 days <br />0 hours <br />0 weeks <br />0 months <br />, would result in a committed effective dose equivalent of five (5) rems.
(***** CATEGORY B CONTINUED ON NEXT PAGE *****)B. NORMAL/EMERGENCY OPERATING PROCEDURES AND RADIOLOGICAL CONTROLSP age 11QUESTION: 004 (1.00)A survey instrument with a window probe is used to measure the beta-gamma dose rate from anirradiated experiment. The dose rate with the window open is 100 mrem/hour, and the dose rate withthe window closed is 60 mrem/hour. The gamma dose rate is:a.40 mrem/hour.
b.60 mrem/hour.
c.100 mrem/hour.
d.160 mrem/hour.QUESTION: 005 (1.00)The area radiation monitor at the pool level is out of service. As a result:a.the reactor cannot be operated.
b.the reactor can continue to operate.
c.the reactor can continue to operate only if the alarm setpoints of the remaining radiationmonitors are lowered.d.the reactor can continue to operate only if the monitor is replaced by an alarming unitcapable of detecting gamma radiation.QUESTION: 006 (1.00)Two different gamma point sources have the same curie strength. The gammas from Source A have anenergy of 1 Mev, and the gammas from Source B have an energy of 2 Mev. The dose rate from eachsource is measured at a distance of 10 feet using a G-M tube. Which ONE of the following statements iscorrect?a.The measured dose rate of Source B is four times that of Source A.
b.The measured dose rate of Source B is two times that of Source A.
c.Both measured dose rates are the same.
d.The measured dose rate of Source B is half that of Source A.
(***** CATEGORY B CONTINUED ON NEXT PAGE *****)B. NORMAL/EMERGENCY OPERATING PROCEDURES AND RADIOLOGICAL CONTROLSP age 12QUESTION: 007 (1.00)In order to maintain an active reactor or senior reactor operator license, the license-holder must performthe functions of his/her position for at least:a.four hours per calendar quarter.
b.three hours per calendar quarter.
c.one hour per month.
d.sixteen hours per year.QUESTION: 008 (1.00)Two centimeters of lead placed in a beam of gamma rays reduce the radiation level from 400 mR/hourto 200 mR/hour. Which ONE of the following is the total thickness of lead that would reduce the gammaradiation level from 400 mR/hour to 50 mR/hour?a.3 cm.
b.4 cm.
c.6 cm.
d.8 cm.QUESTION: 009 (1.00)In accordance with the Power Level Calibration Procedure, in order to give the proper indication afterpower level is determined:a.the pointers in the linear power meters are adjusted.
b.the compensating voltages of the compensated ion chambers are adjusted.
c.the high voltages to the compensated ion chambers are adjusted.
d.the positions of the compensated ion chambers are adjusted.
(***** CATEGORY B CONTINUED ON NEXT PAGE *****)B. NORMAL/EMERGENCY OPERATING PROCEDURES AND RADIOLOGICAL CONTROLSP age 13QUESTION: 010 (1.00)In accordance with the Technical Specifications, which ONE situation below is permissible?a.An experiment that has a moving component having a reactivity worth of $0.50.
b.Storage of a fuel element outside the reactor pool with a radiation level of 90mRem/hour at the storage container surface.c.A depth of water in the reactor pool nine (9) feet above the top of the end box of the fuelelements.d.A safety blade withdrawal rate of 8 inches/minute.QUESTION: 011 (1.00)A radiation survey of an area reveals a general radiation reading of 1 mrem/hour, but there is a smallsection of pipe (point source) that reads 10 mrem/hour at one (1) meter. Which ONE of the followingdefines the posting requirements for the area in accordance with 10 CFR 20?a."CAUTION RADIATION AREA" b.CAUTION RADIOACTIVE MATERIAL" c.CAUTION HIGH RADIATION AREA" d.GRAVE DANGER, VERY HIGH RADIATION AREA"QUESTION: 012 (1.00)In accordance with the Technical Specifications, the reactor will be in a shutdown condition if:a.the shutdown margin with the highest worth control blade fully withdrawn is greater than1% delta k/k.b.there is no indication of neutron level on any measuring channel.
c.there are less than 12 fuel elements loaded on the grid plate.
d.the three control blades are fully inserted.
(***** CATEGORY B CONTINUED ON NEXT PAGE *****)B. NORMAL/EMERGENCY OPERATING PROCEDURES AND RADIOLOGICAL CONTROLSP age 14QUESTION: 013 (1.00)Each of the five Emergency Operating Procedures require that the Emergency Director be informed. The Emergency Director is normally:a.the Senior Reactor Operator with the most seniority.
b.the Radiation Safety Officer.
c.the Reactor Facility Director.
d.The Director of the WPI Nuclear Engineering Program.QUESTION: 014 (1.00)In accordance with the Technical Specifications, which ONE situation below is NOT permissible?a.Reactor critical with the regulating blade fully inserted.
b.Total cold, clean excess reactivity, including experiments = 0.4% delta k/k.
c.Temperature coefficient of reactivity = -5x10
-5 delta k/k/deg. F with an average corewater temperature of 100 degrees F.d.Reactor operation with SRO not in the reactor facility.QUESTION: 015 (1.00)The facility ventilation system is required to be operating whenever:a.reactor power exceeds 1 kW.
b.the Ar-41 monitor is inoperable.
c.the thermal column and beam port exhaust fans are inoperable.
d.the reactor is operating.
(***** CATEGORY B CONTINUED ON NEXT PAGE *****)B. NORMAL/EMERGENCY OPERATING PROCEDURES AND RADIOLOGICAL CONTROLSP age 15QUESTION: 016 (1.00)The "Shutdown Checklist" requires that "watt-hours" be calculated following each reactor shutdown. Watt-hours provide a measure of:a.the peak power reached during operation.
b.fuel burnup during operation.
c.the average power generated during operation.
d.shutdown margin.QUESTION: 017 (1.00)In accordance with the Checkout and Operation Procedure, the B-10 detector may be fully removed fromthe neutron flux when:a.the Log N channel is on scale.
b.one Percent Power channel and the Log N channel are on scale.
c.both Percent Power channels are on scale.
d.both Percent Power channels and the Log N channel are on scale.QUESTION: 018 (1.00)During critical operation of the reactor, the safety system functions that are required to be operable at alltimes are:a.reactor period, reactor power, pool radiation monitor.
b.reactor period, reactor power, manual scram.
c.reactor power, neutron count rate, pool water level.
d.reactor power, manual scram, pool water level.
(***** CATEGORY B CONTINUED ON NEXT PAGE *****)B. NORMAL/EMERGENCY OPERATING PROCEDURES AND RADIOLOGICAL CONTROLSP age 16QUESTION: 019 (1.00)As part of the reactor checkout procedure prior to operation, the regulating blade is withdrawn frombeyond its "in" limit, and then it is checked that no control blade can be withdrawn. The purpose of thischeck is to:a.ensure that the reactor can only be taken critical using the regulating blade.
b.verify that a control blade cannot be moved if the Startup count rate meter shows lessthan 50 counts per second.c.verify that the regulating blade will scram when the source bottle is used to obtain aperiod of about six seconds.d.verify that the regulating blade position indicator is operating properly.QUESTION: 020 (1.00)In accordance with the Emergency Plan, the term "on-site" means:a.within the operations boundary.
b.within the Emergency Planning Zone.
c.the area within the site boundary.
d.the WPI campus.
(***** END OF CATEGORY B *****)C. FACILITY AND RADIATION MONITORING SYSTEMSPage 17QUESTION: 001 (1.00)Upon the receipt of a scram signal, the regulating blade:a.magnet is de-energized, and the blade falls into the core.
b.remains where it is, and must be manually driven into the core.
c.automatically drives into the core.
d.magnet and drive both fall into the core.QUESTION: 002 (1.00)The Beam Port design protects personnel against radiation from the port by:a.a shutter in the pipe and a plug.
b.portable shielding around the beam port.
c.alternately stacked graphite logs and a stepped closure door.
d.graphite filler plugs.QUESTION: 003 (1.00)Which ONE of the safety blade withdrawal interlocks below may be bypassed?a.5 second time delay.
b.Regulating blade withdrawn from its lowest position.
c.Reactor in scram condition.
d.Log count rate below 3000 CPM.
(***** CATEGORY C CONTINUED ON NEXT PAGE *****)C. FACILITY AND RADIATION MONITORING SYSTEMSPage 18QUESTION: 004 (1.00)Which ONE of the following is the approximate rate at which the ventilation system is designed tocompletely change the reactor compartment air?a.1 change per hour.
b.>2 changes per hour.
c.>3 changes per hour.
d.>4 changes per hour.QUESTION: 005 (1.00)Which ONE of the following demineralizer regeneration processes will remove radioactive particulatesfrom the resin bed?a.Resin mixing.
b.Caustic soda treatment.
c.Acid solution treatment.
d.Backwash.QUESTION: 006 (1.00)Which alarm(s) provide indication of abnormal conditions at Campus Security Headquarters?a.Area radiation monitors only.
b.Area radiation monitors and reactor pool low water level.
c.Loss of electrical power.d.Reactor pool low water level only.(***** CATEGORY C CONTINUED ON NEXT PAGE *****)C. FACILITY AND RADIATION MONITORING SYSTEMSPage 19QUESTION: 007 (2.00)Match the instrument channel listed in Column A with the correct detector listed in Column B. Itemslisted in Column B may be used more than once or not at all.Column AColumn Ba.Log N/Linear Channel1.Proportional counter b.Startup Channel2.Fission chamber c.Safety Channel3.Na-I scintillation detectord.Area radiation monitor4.GM detector5.Compensated ion chamber 6.Uncompensated ion chamberQUESTION: 008 (1.00)Which ONE of the following is the normal flow rate for the cleanup system circulation pump?a.5 gpm.
b.10 gpm.
c.15 gpm.
d.20 gpm.
QUESTION: 009 (1.00)The evacuation alarm setpoints for the area radiation monitors are:a.Pool - 50 mrem/hrBeam Tube - 50 mrem/hrThermal Column - 20 mrem/hr b.Pool - 50 mrem/hrBeam Tube - 20 mrem/hrThermal Column - 20 mrem/hr c.Pool - 20 mrem/hrBeam Tube - 20 mrem/hrThermal Column - 50 mrem/hr d.Pool - 20 mrem/hrBeam Tube - 50 mrem/hrThermal Column - 50 mrem/hr(***** CATEGORY C CONTINUED ON NEXT PAGE *****)C. FACILITY AND RADIATION MONITORING SYSTEMSPage 20QUESTION: 010 (1.00)Control blades are withdrawn from the core at a nominal speed of:a.4.0 inches/minute.
b.7.5 inches/minute.
- c. 24.0 inches/minute.
d.32.0 inches/minute.QUESTION: 011 (1.00)Which ONE of the following describes how control blade position indication is generated when the bladeis between the full in and full out positions? As the blade moves,a.the impedance of a pick-up coil changes, generating a change in voltage proportional toposition.b.a chain driven optical pulse generator produces pulses whose number is proportion toblade travel.c.a series of limit switches open and close as the blade passes.
d.a ten-turn potentiometer generates a signal proportional to position.QUESTION: 012 (1.00)An abnormal condition is indicated by the lighting of a box on the annunciator panel and the sounding of an alarm horn. Pressing the "Acknowledge" on the annunciator panel or control console will always:a.silence the horn and extinguish the light.
b.silence the horn only if the condition has returned to normal.
c.silence the horn.
d.extinguish the light.(***** CATEGORY C CONTINUED ON NEXT PAGE *****)C. FACILITY AND RADIATION MONITORING SYSTEMSPage 21QUESTION: 013 (1.00)Which ONE of the following systems does NOT receive emergency power from the battery backupsystem following a loss of normal power?a.Area radiation monitoring system.
b.Evacuation alarms.
c.Emergency lighting system.
d.Safety instrumentation system.QUESTION: 014 (1.00)During periodic leak testing of the neutron source, filter paper wipes are counted for the detection of:a.alpha radiation.
b.beta radiation.
c.gamma radiation.
d.neutrons.QUESTION: 015 (1.00)Which ONE of the following will cause a building evacuation alarm?
a.Loss of electrical power.b.High pool temperature.
c.High radiation level at fuel storage container surface.
d.Low pool water level.(***** CATEGORY C CONTINUED ON NEXT PAGE *****)C. FACILITY AND RADIATION MONITORING SYSTEMSPage 22QUESTION: 016 (1.00)During full power operation, the proportional counter is fully withdrawn to its uppermost position so thatthe:a.scalar does not become saturated.
b.counter is not damaged by radiation.
c."Startup channel full-in" annunciator will not alarm.d.high count rate will not initiate a reactor scram.QUESTION: 017 (1.00)Which ONE of the following control blade withdrawal interlocks provides protection against anabnormally high excess reactivity?a.Log N count below 3000 cpm.
b.5-second delay subsequent to reactor startup.
c.Regulating blade is withdrawn from its lowest position.
d.Flux rises above a preset level before the safety blades are completely withdrawn.QUESTION: 018 (1.00)
When the Master Switch is in the "TEST" position:a.all blade withdrawal interlocks are bypassed.
b.the blade drives may be moved without withdrawing the blades.
c.electronic scrams are bypassed.
d.electronic and relay scrams are bypassed.(***** END OF CATEGORY C *****)(***** END OF EXAMINATION *****)A. REACTOR THEORY, THERMODYNAMICS & FACILITY OPERATING CHARACTERISTICS ANSWER: 001 (1.00)
A.
REFERENCE:
Lamarsh, Introduction to Nuclear Engineering, 2 nd. Edition, page 286.ANSWER: 002 (1.00)
A.
REFERENCE:
Lamarsh, Introduction to Nuclear Engineering, 2 nd. Edition, page 103ANSWER: 003 (1.00)
B.
REFERENCE:
Lamarsh, Introduction to Nuclear Engineering, 2 nd. Edition, page 313ANSWER: 004 (1.00)
C.
REFERENCE:
Experiment No. 3, Critical Mass Determination.ANSWER: 005 (1.00)
D.
REFERENCE:
Lamarsh, Introduction to Nuclear Engineering, 2 nd. Edition, page 282.Reactivity = (K-1)/K = -4.7% delta K/K. If + 3.5% delta K/K is added, the new reactivity will be-1.2%, i.e., subcritical.ANSWER: 006 (1.00)
C.
REFERENCE:
Lamarsh, Introduction to Nuclear Engineering, 2 nd. Edition, page 76.ANSWER: 007 (1.00)
C.
REFERENCE:
Increase = 1.001x10 8 - 1x10 8 = 1x10 5. Prompt neutron population = 0.993x1x10 5 = 99,300.ANSWER: 008 (1.00)
D.
REFERENCE:
Lamarsh, Introduction to Nuclear Engineering, 2 nd. Edition, page 285.ANSWER: 009 (1.00)
B.
REFERENCE:
Lamarsh, Introduction to Nuclear Engineering, 2 nd. Edition, page 266.ANSWER: 010 (1.00)
D.
REFERENCE:
Lamarsh, Introduction to Nuclear Engineering, 2 nd. Edition, page 267.
ANSWER: 011 (1.00)
C.
REFERENCE:
Lamarsh, Introduction to Nuclear Engineering, 2 nd. Edition, page 60.ANSWER: 012 (1.00)
D.
REFERENCE:
Lamarsh, Introduction to Nuclear Engineering, 2 nd. Edition, page 307.ANSWER: 013 (1.00)
D.
REFERENCE:
Lamarsh, Introduction to Nuclear Engineering, 2 nd. Edition, page 286.ANSWER: 014 (1.00)
A.
REFERENCE:
Lamarsh, Introduction to Nuclear Engineering, 2 nd. Edition, page 284.ANSWER: 015 (1.00)
D.
REFERENCE:
Glasstone, Nuclear Reactor Engineering, 3 rd. Edition, Section 1.39.ANSWER: 016 (1.00)
A.
REFERENCE:
Glasstone, Nuclear Reactor Engineering, 3 rd. Edition, Section 2.73.ANSWER: 017 (1.00)
A.
REFERENCE:
Lamarsh, Introduction to Nuclear Engineering, 2 nd. Edition, page 307.Reactivity added by control rod = 0.001 delta k/k/inch x 10 inches = 0.01 delta k/k(0.01 delta k/k)/1.25x10
-3 delta k/k/deg.C = 8 degrees C.ANSWER: 018 (1.00)
A.
REFERENCE:
A detector that is too far from the source and fuel w ill underestimate the effects of adding fuel, since themeasured counts will not appreciably increase with each fuel element addition.ANSWER: 019 (1.00)
B.
REFERENCE:
Shutdown Margin = Total Rod Worth - Excess ReactivityShutdown Margin = 11.0% - 0.5% = 10.5% delta k/kANSWER: 020 (1.00)
D.
REFERENCE:
Lamarsh, Introduction to Nuclear Engineering, 2 nd. Edition, page 222.
B. NORMAL/EMERGENCY OPERATING PROCEDURES AND RADIOLOGICAL CONTROLSANSWER: 001 (1.00)A, 4; B, 2; C, 2; D, 1.
REFERENCE:
WPI Requalification Program.ANSWER: 002 (1.00)
B.
REFERENCE:
Emergency Plan, page 9.ANSWER: 003 (1.00)
A.
REFERENCE:
10 CFR 20.ANSWER: 004 (1.00)
B.
REFERENCE:
With the window closed, no betas are measured. The gamma dose rate is 60 mrem/hour.ANSWER: 005 (1.00)
D.
REFERENCE:
WPI Technical Specifications, Section 3.3.ANSWER: 006 (1.00)
C.
REFERENCE:
G-M tubes are not sensitive to energy.ANSWER: 007 (1.00)
A.
REFERENCE:
WPI Requalification Program.ANSWER: 008 (1.00)
C.
REFERENCE:
Each 2 cm. of lead reduces the radiation level by a factor of 2. Therefore 6 cm. reduces it by a factor of 8.ANSWER: 009 (1.00)
D.
REFERENCE:
OP-6, Power Level Calibration Procedure.ANSWER: 010 (1.00)
B.
REFERENCE:
WPI Technical Specifications, Section 5.9.
ANSWER: 011 (1.00)
C.
REFERENCE:
10 CFR 20; 10 mrem/hour at one meter = 111 mrem/hour at 30 centimeters.ANSWER: 012 (1.00)
C.
REFERENCE:
WPI Technical Specifications, Definitions.ANSWER: 013 (1.00)
C.
REFERENCE:
Emergency Plan, 3.1.1.ANSWER: 014 (1.00)
A.
REFERENCE:
WPI Technical Specifications, Section 2.1.ANSWER: 015 (1.00)
D.
REFERENCE:
WPI Technical Specifications, Section 4.3.ANSWER: 016 (1.00)
B.
REFERENCE:
Watt-hours is a unit of energy, therefore measures fuel burnup.ANSWER: 017 (1.00)
D.
REFERENCE:
OP-1, Reactor Startup,Section II.7.ANSWER: 018 (1.00)
B.
REFERENCE:
WPI Technical Specifications, Table 4.1.ANSWER: 019 (1.00)
A.
REFERENCE:
OP-1, Reactor Startup,Section I.12.ANSWER: 020 (1.00)
C.
REFERENCE:
Emergency Plan, Definitions.
C. FACILITY AND RADIATION MONITORING SYSTEMSANSWER: 001 (1.00)
C.
REFERENCE:
SAR, Section 4.2.2.2.ANSWER: 002 (1.00)
A.
REFERENCE:
SAR, Section 1.3.ANSWER: 003 (1.00)
D.
REFERENCE:
WPI Technical Specifications, Table 4.1.ANSWER: 004 (1.00)
B.
REFERENCE:
SAR, Section 9.1.ANSWER: 005 (1.00)
D.
REFERENCE:
Demineralizer Regeneration Procedure.ANSWER: 006 (1.00)
B.
REFERENCE:
Emergency Plan, Section 7.1.ANSWER: 007 (1.00)A,5; B,1; C,5; D,4.
REFERENCE:
SAR Sections 7.4, 7.5, 7.6.ANSWER: 008 (1.00)
B.
REFERENCE:
SAR, Section 5.3.ANSWER: 009 (1.00)
B.
REFERENCE:
OP-1, Section 5.2.ANSWER: 010 (1.00)
B.
REFERENCE:
SAR, Section 7.7.
ANSWER: 011 (1.00)
B.
REFERENCE:
SAR, Section 7.7.ANSWER: 012 (1.00)
C.
REFERENCE:
SAR, Section 7.3.ANSWER: 013 (1.00)
D.
REFERENCE:
SAR, Section 8.2.ANSWER: 014 (1.00)
A.
REFERENCE:
SAR, Section 4.2.4.ANSWER: 015 (1.00)
D.
REFERENCE:
Technical Specifications, Table 4.1.ANSWER: 016 (1.00)
B.
REFERENCE:
SAR, Section 7.4.ANSWER: 017 (1.00)
D.
REFERENCE:
SAR, Section 7.7.ANSWER: 018 (1.00)
B.
REFERENCE:
SAR, Section 8.1.
A. REACTOR THEORY, THERMODYNAMICS AND FACILITY OPERATING CHARACTERISTICSANSWER SHEETMULTIPLE CHOICE (Circle or X your choice)If you change your answer, write your selection in the blank.001abcd _____
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(***** END OF CATEGORY A *****)
B. NORMAL/EMERGENCY OPERATING PROCEDURES AND RADIOLOGICAL CONTROLSANSWER SHEETMULTIPLE CHOICE (Circle or X your choice)If you change your answer, write your selection in the blank.001a_____b_____c_____d _____
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(***** END OF CATEGORY B *****)
C. FACILITY AND RADIATION MONITORING SYSTEMSANSWER SHEETMULTIPLE CHOICE (Circle or X your choice)If you change your answer, write your selection in the blank.001abcd _____
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(***** END OF CATEGORY C *****)EQUATION SHEETQ = m c p TCR 1 (1-K eff)1 = CR 2 (1-K eff)2SUR = 26.06/P = P 0 10SUR(t)P = P 0 e(t/) = (*/) + [(-)/eff]eff = 0.1 seconds
-1 DR 1 D 1 2 = DR 2 D 2 2DR = DR o e-tDR = 6CiE/D 2 = (K eff - 1)/K eff1 eV = 1.6x10-19 watt-sec.1 Curie = 3.7x10 10 dps1 gallon water = 8.34 pounds 1 Btu = 778 ft-lbfF = 9/5C + 321 Mw = 3.41x10 6 BTU/hrC = 5/9 (F - 32)