ML20138G431
| ML20138G431 | |
| Person / Time | |
|---|---|
| Site: | 05000134 |
| Issue date: | 04/28/1997 |
| From: | Eresian W NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20138G401 | List: |
| References | |
| 50-134-OL-97-01, 50-134-OL-97-1, NUDOCS 9705060296 | |
| Download: ML20138G431 (34) | |
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U. S. NUCLEAR REGULATORY COMMISSION OPERATOR LICENSING INITIAL EXAMINATION REPORT REPORT NO.: 50-134/0L-97-01 FACILITY DOCKET NO.: 50-134 FACILITY LICENSE NO.: R-61 FACILITY: Worcester Polytechnic Institute EXAMINATION DATES: April 14-16, 1997 EXAMINER: Warren J. Eresian, Chief Examiner SUBMITTED BY: h _J / C f 2. 9 f@
Warren J. Eredian, Chief Exadiiner Date
SUMMARY
The NRC administered initial license examinations to three Reactor Operator applicants and one Senior Reactor Operator (Upgrade) applicant. One Reactor Operator applicant and one Senior Reactor Operator (Upgrade) applicant passed the examination. Two Reactor Operator applicants failed the examination.
ATTACHMENT 1 9705060296 970501 PDR ADOCK 05000134 V PDR
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REPCRT DETAILS
- 1. Examiners:
Warren J. Eresian, Chief Examiner !
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- 2. Results:
1 R0 SR0 Total (Pass / Fail) (Pass / Fail) (Pass / Fail)
NRC Grading: 1/2 1/0 2/2
- 3. Written Examination: ;
One Reactor Operator applicant passed the written examination. One Reactor Operator applicant failed Category A but passed the examination overall. The third Reactor Operator applicant failed Categories A and B, failing the examination overall.
- 4. Operating Test: !
The Senior Reactor Operator (Upgrade) applicant passed the operating test. One Reactor Operator applicant (who passed the written examination) passed the operating test. The second Reactor Operator applicant (who failed Category A of the written examination) failed the operating test. The third Reactor Operator applicant (who failed the written examination overall) passed the operating test.
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- 5. Exit Meeting: l None.
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U. 3. NUCLEAR REGULATORY COMMISSION NON-POWER REACTOR LICENSE EXAMINATION !
FACILITY: Worcester Tech i l
REACTOR TYPE: Pool l DATE ADMINISTERED: 04/14/97 .
REGION: 1 CANDIDATE:
INSTRUCTIONS TO CANDIDATE:
Answers are to be written on the exam page itself, cr the answer sheet provided. Write answers one side ONLY. Attach any answer sheets to the examination. Points for each question are indicated in parentheses for each question. A 70% in each category is required to pass the examination.
Examinations will be picked up three (3) hours cfter the examination sterts,
% OF CATEGORY % OF CANDIDATE'S CATEGORY VALUE TOTAL SCORE VALUE CATEGORY 19 34 A. REACTOR THEORY.
THERMODYNAMICS, AND FACILITY OPERATING CHARACTERISTICS 20 36 B. NORMAL AND EMERGENCY OPERATING PROCEDURES AND RADIOLOGICAL CONTROLS 17 30 C. FACILITY AND RADIATION MONITORING SYSTEMS 56 %
FINAL GRADE All work done on this examination is my own. I have neither given nor received aid.
Candidate's Signature
s NRC RULES AND GUIDELINES FOR LICENSE EXAMINATIONS During the administration of this examination the following rules apply:
- 1. Cheating on the examination means an automatic denial of your application and could result in more severe penalties.
- 2. After the examination has been completed. you must sign the statement on the cover sheet indicating that the work is your own and you have not received or given assistance in completing the examination. This must be done after you complete the examination.
- 3. Restroom trips are to be limited and only one candidate at a time may leave. You must avoid all contacts with anyone outside the examination room to avoid even the appearance or possibility of cheating.
- 4. Use black ink or dark pencil only to facilitate legible reproductions.
- 5. Print your name in the blank provided in the upper right-hand corner of the examination cover sheet.
- 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 00 NOT LEAVE ANY ANSWER BLANK. NOTE: partial credit will NOT be given on multiple choice questions
- 9. If the intent of a quostion is unclear, ask questions of the examiner only.
- 10. When turning in your examination, assemble the completed examination with examination questions, 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 defined by the exminer. If you are found in this area while the examin6 tion .
is still in progrees, your license may be denied or revoked. j I
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A. REACTOR THEORY THERMODYNAMICS & FACILITY OPERATING CHARACTERISTICS Page 3 OUESTION: 001 (1.00)
An equal amount of positive reactivity is added to two identical critical reactors.
Reactor A at a power level of 10 watts, and Reactor B at a power level of 1000 watts.
Compared to Reactor A. the magnitude of the prompt jump in Reactor B will be:
- a. larger, because power level is higner.
- b. the same, because the magnitude depends only on how much reactivity is {
added. ,
- c. smaller, because at higher power levels the same reactivity addition has a i smaller effect. s i
- d. the same, unless the reactivity addition is - S,u. ;
i OUEST10N: 002 (1.00) -
Which ONE of the following conditions would increase shutdown margin? ,
- a. An experiment which added positive reactivity.
- b. Depletion of uranium fuel.
- c. Removal of a void from the core.
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- d. Decreasing fuel temperature.
QUESTION: 003 (1.00) :
, A reactor is exactly critical when a 100 cc void is introduced into the core. As a !
result a control rod with an average rod worth of 0.1% delta k/k/ inch must be withdrawn l 10 inches in order to make the reactor critical again. The void coefficient is: '
- a. + 0.01% delta k/k/cc
- b. + 0.10% delta k/k/cc l l
- c. - 0.01% delta k/k/cc !
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- d. - 0.10% delta k/k/cc j i
(***** CATEGORY A CONTINUED ON NEXT PAGE *****)
A. REACTOR THEORY. THERMODYNAMICS & FACILITY OPERATING CHARACTERISTICS Page 4 OUESTION: 004 (1.00)
A reactor is subcritical with a K.,f 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: 005 (1.00)
During the time when reactor power decreases, the delayed neutron fraction. S:
- a. decreases because delayed neutron precursors are being produced at a slower
- rate.
- b. increases because delayed neutrons are being produced from precursors that .,
, were formed at a higher power level.
i j c. decreases because prompt neutrons are being produced at a slower rate.
i d. remains unchanged.
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OUESTION: 006 (1.00) i A reactor fuel consisting of U-235 and U-238 is 20% enriched. This means that:
l a. 20% of the weight of the fuel consists of U-235.
i b. 20% of the volume of the fuel consists of U-235.
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- d. 20% of the atoms of the fuel ccnsists of U-235.
(***** CATEGORY A CONTINUED ON NEXT PAGE *****)
A. REACTOR THEORY. THERMODYNAMICS AND FACILITY OPERATING CHARACTERISTICS Page 5 0UESTION: 007 (1.00)
Inelastic Scatterina is the process whereby a neutrnn collides with a nucleus and:.
- a. recoils with the sa'e m kinetic energy it had prior to the collision.
- b. recoils with a lower kinetic energy. with the nucleus emitting a gamma ray,
- c. is absorbed by the nucleus, with the nucleus emitting a gamma ray.
- d. recoils with a higher kinetic energy. with the nucleus emitting a gamma ray. -
QUESTION 008 (1.00)
An example of a fissile isotope which occurs naturally is:
- a. Pu-239
- b. U-238
- c. U-235
- d. Th-232 OUESTION: 009 (1.00)
Reactor power level is determined by irradiating a gold foil. If the actual irradiation time is longer that the irradiation time used in the equation for the determination of power level, the measured power level will be:
- a. greater than the actual power level.
- b. less than the actual power level.
- c. the same as actual power level.
- d. greater or less than actual power level. depending on whether the irradiation was performed at a high or low power level.
(***** CATEGORY A CONTINUED ON NEXT PAGE *****)
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A. REACTOR THEORY THERMODYNAMICS AND FACILITY OPERATING CHARACTERISTICS Page 6 t
OUESTION: 010 (1.00) i The resonance escape probability is the probability that a fission neutron will escape '
capture in resonances as it slows down to thermal energies. As the moderator '
temperature increases, the resonance escape probability:
- a. increases, since the moderator becomes less dense. ,
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- b. decreases, since the time required for a neutron to reach thermal energy increases.
- c. remains constant since the effect of mcJerator temperature change is relatively small.
- d. increases, since the moderator-to-fuel ratio increases. '
OUESTION: 011 (1.00)
A reactor is operating at criticality. Instantaneously, all of the delayed neutrons i are suddenly removed from the reactor. The K,,, of the reactor in this state would be :
approximately: '
- a. 1.007
- b. 1.000
- c. 0.000
- 1. 0.993 OUESTION: 012 (1.00)
The WPI reactor is critical at full rated power, with reactivity = zero. A control rod is inserted and the power decreases to a lower steady-state value. The reactivity of the reactor at the lower power level is zero because: ;
- a. the positive reactivity due to the fuel temperature decrease balances the negative reactivity due to the control rod insertion. l
- b. the negative reactivity due to the fuel temperature decrease equals the :
negative reactivity due to the control rod insertion. l
- c. the positive reactivity due to the fuel temperature increase balances the negative reactivity due to the control rod insertion. l l
- d. the negative reactivity due to the fuel temperature increase equals the l negative reSctivity due to the control rod insertion. !
(***** CATEGORY A CONTINUED ON NEXT PAGE *****)
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A. REACTOR THEORY, THERMODYNAMICS AND F ACIUTY OPEllATINli DIARAGlTRISTICS Page 7 l QUESTION: 013 (2.00) i In a critical reactor,100 fast neutrons are produced from fission and start to slow ,
down. 20 neutrons are captured in resonance peaks. and 10 leak out of the core after t i they have reached thermal energy. The remaining neutrons are absorbed in fuel and
- other materials. Each fission produces 2.5 neutrons, and 85% of the neutrons absorbed i in fuel result in fissions. For this reactor. the thermal utilization factor is- !
l a. 0.47 i
l b. 0.62 ,
- c. 0.67
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i d. 1.613 i t
QUESTION: 014 (1.0u) t A hypothetical fuel produces 20% of its power from the fission of element X and 80% of its )ower from the fission of element Y. The beta fraction of element X is 0.006 and ;
i the Jeta fraction of element Y is 0.008. The beta fraction of the fuel as a whole is-i :
l a. 0.0064 t
- b. 0.0070 l
! c. 0.0076 i '
4 d. 0.0140
! OUESTION: 015 (1.00) l A 1/M curve is being generated as fuel is loaded into the core. After some fuel
- elements have been loaded, the count rate existing at that time is taken to be the new ,
! initial count rate C o. Additional elements are then loaded and the inverse count rate j j ratio continues to decrease. As a result of changing the initial count rate:
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- a. criticality will occur earlier (i.e. with fewer elements loaded.) ,
j b, criticality will occur with the same number of elements loaded.
- c. criticality will occur later (i.e. with more elements loaded.)
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- d. criticality will be completely unpredictable. '
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(***** CATEGORY A CONTINUED ON NEXT PAGE *****) ;
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. 1 A. REACTOR THEORY, THERMODYNAMICS AND FACILITY OPERATING CHARACTERISTICS Page 8 i OUESTION: 016 (1.00) i Reactor A increases power from 10% to 20% with a period of 50 seconds. Reactor B j increases power from 20% to 30% with a period of also 50 seconds. Compared to reactor A. the time required for the power increase of reactor B is:
- a. longer than A.
- b. exactly the same as A.
- c. approximately the same as A.
.d, shorter than A. )
QUESTION: 017 (1.00) i Wnich ONE of the following would result in a determination of the excess reactivity of the WPI reactor?
- a. The reactor is critical at a low power level, with all safety blades are full out and the regulating blade at some position. The reactivity :
remaining in the regulating blade (i.e. its rod worth from its present ;
position to full out) is the excess reactivity. l
- b. All blades are full in The safety blades and the regulating blade are ;
withdrawn until the reactor becomes critical. The total rod worth ,
withdrawn is the eness reactivity. l
- c. The reactor is at full power (10kW). The total rod worth of all blades withdrawn is the excess reactivity.
- d. The reactor is at full power (10 kW). The rer Jiating blade is moved from its present position to full in. The negativ; reactivity inserted by the regulating blade is the excess reactivity.
1 QUESTION: 018 (1.00)
The term " buckling" in a reactor refers to:
- a. the ratio of average neutron flux to maximum neutron flux.
- b. the ratio of reflected neutron flux to average neutron flux.
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- c. the curvature of the neutron flux. ;
- d. self-shielding of reactor fuel.
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(***** END OF CATEGORY A *****) i l
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B. NORMAL / EMERGENCY PROCEDURES AND RADIOLOGICAL CONTROLS Page 9 OUESTION: 001 (1.00)
When verifying Period Meter performance during a startup, if indicated period does not fall within the calculated limits:
- a. a second measurement must be made before the startup can continue,
- b. rod withdrawal must stop and the SRO notified.
- c. the reactor must be innediately shutdown.
- d. the startup can continue only under the direct supervision of the SRO.
QUESTION: 002 (1.00)
In accordance with the Fuel Unloading Procedure, fuel element transfers require:
- a. a licensed operator at the console, a licensed operator on the bridge, and a senior operator present.
- b. a licensed operator at the console and a senior operator on the bridge,
- c. a senior operator at the console and a licensed operator on the bridge.
- d. a licensed operator at the console end a licensed operator on the bridge.
QUESlION: 003 (1.00)
In accordance with the Technical Specifications, which ONE situation below is permissible?
- a. An experiment which has a moving component having a reactivity worth of 50.50.
- b. An excess reactivity above cold. clean critical of 1% delta k/k.
- c. A depth of water in the reactor pool 9 feet above the top of the end box of the fuel elements.
- d. Pool water resistivity - 5x10 ohm-cm.
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(***** CATEGORY B CONTINUED ON NEXT PAGE *****)
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- 8. NORMAL / EMERGENCY PROCEDURES AND RADIOLOGICAL CONTRCLS Page 10 i P
OUESTION: 004. (1.00) ,
The primary source of radiation release to the environment through the ventilation system during reactor operation is:
- a. gamma emission from activated structural members.
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- b. Argon-41 from the beam port and thermal column. ;
- c. Nitrogen-16 from pool water evaporation.
- d. Alpha-Beta radiation from activation of air.
QUESTION: 005 (1.00)
When noerating below 1 kW
- a. the Ar-41 system must be on. the rooms above the reactor locked, and the area radiation monitoring system operational.
b, the Ar-41 system must be on.
- c. the rooms above the reactor must be locked. l
- d. the area radiation monitoring system must be operational.
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'0VESTION: 006 (1.00)
In accordance with the Technical Specifications, which ONE situation below is NOT l' permissible?
- a. Storage of a fuel element outside the reactor pool with a radiation level of 90 mrem / hour at the storage container surface.
- b. Pool water activity = 10" pCi/ml.
- c. Temperature coefficient of reactivity = -5x10'S delta k/k/deg F with an average core water temperature of 100 degrees F.
- d. Reactor subcritical with all blades withdrawn. 1
(***** CATEGORY B CONTINUED ON NEXT PAGE *****)
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4 B. NORMAL / EMERGENCY PROCEDURES AND RADIOLOGICAL CONTROLS Page 11 QUESTION: 007 (1.00)
In accordance with 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 than 1% delta k/k.
- b. the reactor key is removed.
- c. there are less than 12 fuel elements loadad on the grid plate. !
- d. the three control blades are fully inserted.
QUESTION: 008 (1.00) j A portable radiation inonitor may temporarily replace one of the fixed area radiation monitors provided that: :
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- a. the required alarms are operational.
- b. the portable monitor be capable of measuring neutron dose rates. >
- c. the portable monitor be used for a maximum of one (1) week. l
- d. the portable monitor is calibrated (not a source check) before each startup.
h OUESTION: 009 (1.00) ;
During critical operation of the reactor safety system functions which are required to I be operable at a.]_1 times are:
- a. reactor period reactor power. pool water level. l
- 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 *****) .
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l B. NORMAL / EMERGENCY PROCEDURES AND RADIOLOGICAL CONTROLS Page 12 l 4
- OUESTION: 010 (1.00) !
An Emergency Action Level is:
- a. a condition which calls for immediate action, beyond the scope of normal operating procedures, to avoid an accident or to mitigate the consequences
- of one.
j b. a class of accidents for which predetermined emergency measures should be taken or considered. l l
! c. a 3rocedure that details the implementation actions and methods required to j l aclieve the objectives of the Emergency Plan. !
l a specific instrument reading or observation which may be used as a 2
d.
! threshold for initiating appropriate emergency procedures.
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00EST10N: 011 (1.00) i
! A licensed operator who fails to actively perform the functions of an operator for a minimum of four hours per calendar quarter:
a, cannot operate the reactor unless he/she has performed a minimum of six i hours of licensed functions under the direction of an operator or senior
- operator.
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- b. cannot operate the reactor until he/she has successfully completed ao oral or written examination on console operation.
!.. c. can continue to operate che reactor only under the direction of an operator i or senior operator until ten (10) startups are completed.
- d. must operate the reactor for a sufficient number of hours in the next i calendar quarter so that at least eight hours of operation have occurred in the two quarters.
1 QUESTION: 012 (1.00) !
i i The facility ventilation . system is required to be operating whenever:
j a. reactor power exceeds 1 kw.
- b. the Ar-41 monitor is inoperable. ;
1 l c. the thermal column and beamport exhaust fans are inoperable.
- d. whenever the reactor is operating.
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.i B. NORMAL / EMERGENCY PROCEDURES AND RADIOLOGICAL CONTROLS Page 13 >
OUESTION: 013 (1.00)
The term " cold, clean, critical condition" means that: l
- b. the reactor core is at the ambient pool water temperature of between 70 and i 75 degrees F. and that the core is free of any experiments ,
- c. the reactor core is less than 60 degrees F. and is free of xenon and :
samarium ,
- d. the reactor is critical and free of any experiments OUESTION: 014 (1.00)
As part of the reactor checkout procedure prior to operation, the regulating blade is withdrawn from beyond its in limit, and then it is checked that no control olade can be '
, withdrawn. The purpose of this check is to:
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- 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 less than 50 counts per second !
- c. verify that the regulating blade will scram when the source bottle is used I to obtain a period of about six seconds I l
- d. verify that the regulating blade position indicator is operating properly j l
OUESTION: 015 (1.00) '
A High Radiation area is established in a room for an experiment. The area has been posted as a High Radiation Area. Which ONE of the following additional actions must be taken?
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- a. Equip the area with a surveillance camera. l
- b. Place portable radiation monitors in the area.
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- c. Equip the door with an audible or visible alarm.
- d. Place a lock on the door.
(***** CATEGORY B CONTINUED ON NEXT PAGE *****)
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B. NORWsL/ EMERGENCY PROCEDURES AND RADIOLOGICAL CONTROLS Page 14 00ESTION: 016 (1.00)
"The minimum shitdown margin under any condition with the highest worth control blade fully withdrawn shall be no less than 1% delta k/k." This is an example.of a(n):
- a. g3neral operating limitation.
- b. procedural requiement.
- c. safety limit.
- d. surveillance requirement.
QUESTION: 017 (1.00)
The limit for minimum water level above the core is based on:
- a. providing adequate neutron shielding during operation.
- b. providing adequate gamma radiation shielding during operation.
- c. providing sufficient suction head for the purification pump.
- d. providing the proper amount of core cooling.
i OUEST10N: 018 (1.00)
Which ONE of the following activities may be performed by a licensed operator without the permission or supervision of a senior licensed operator?
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- a. Maintenance of the regulating rod drive,
- b. Movement of fuel from the core to a fuel rack. j
- c. Placing the pool water level safety switch in the BYPASS position. l
- d. Measurement of rod drop times.
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(***** CATEGORY B CONTINUED ON NEXT PAGE *****)
B. NORMAL / EMERGENCY PROCEDURES AND RADIOLOGICAL CONTROLS Page 15 0UESTION: 019 (1.00)
In accordance with 10CFR20, which ONE of the following defines " Total Effective Dose l Equivalent (TEDE)?"
- a. The sum of Internal Dose and External Dose.
- b. The dose that the whole body receives from sources outside the body.
- c. The sum of External Dose and Organ Dose.
- d. The dose to a specific organ or tissue resulting from an intake of radioactive material.
OVESTION: 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 *****)
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C. FACILITY.AND RADIATION MONITORING SYSTEMS Page 16 OUESTION: 001 (1.00) l During a reactor startup. safety blades cannot be withdrawn unless: i
- a. the Boron-10 counter is fully inserted and the Log N channel is above 3000 CPM.
! l l b. the regulating blade is fully inserted and the Log N channel is above-3000 1 CPM. l l C. the Boron-10 counter is fully inserted and the Startup Channel is above l l 3000 CPM. ,
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'd. the regulating blade is fully inserted and the Startup Channel is above j 3000 CPM.
l OUESTION: 002 (1.00) l i
lhe " TEST" position of the Master Switch allows: l
- b. control power and lamp indication operability testing.
- c. control blaJe drive motion without energizing the magnets.
- d. control blade drive motion with energized magnets.
QUESlION: 003 (1.00)
In case of a radioactive spill. the ventilation system: .
- a. exhaust duct must be closed.
- b. supply and exhaust ducts must be closed.
- c. fans must be tripped.
- d. remains operating. ]
(***** CATEGORY C CONTINUED ON NEXT PAGE *****)
C. FACILITY AND RADIATION MONITORING SYSTEMS Page 17 OVESTION: 004 (1.00)
Which ONE condition below will result in an alarm? ,
- a. Reactor period - 20 seconds.
- b. Ar-41 monitor reading of 2000 CPM.
- c. Pool level 5 inches below overflow pipe.
- d. Overflow tank high level.
QUESTION: 005 (1.00) f Upon the receipt of a scram signal. the regulating blade:
- a. magnet is oe-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: 006 (1.00)
Which ONE condition below will NOT result in a reactor scram?
- a. Reactor period - 6 seconds.
- b. Pool monitor - 50 mrem / hour.
- c. CIC High Voltage - 700 volts.
- d. Linear Power at 115% of range.
(***** CATEGORY C CONTINUED ON NEXT PAGE *****)
C. FACILITY AND RADIATION MONITORING SYSTEMS Page 18 OUESTION: 007 (1.00)
The Beam Port design protects personnel against radiation from the port by:
- a. a shutter and concrete shield plugs.
b, portable shielding around the beamport.
- c. alternately stacked graphite logs and a stepped closure door.
- d. graphite filler plugs, l QUESTION: 008 (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, l
- c. Reactor in scram condition.
- d. Log count rate below 3000 CPM. [
OUESTION: 009 (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.
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(***** CATEGORY C CONTINUED ON NEXT PAGE *****)
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C. FACILITY AND RADIATION MONITORING SYSTEMS Page 19- ;
OVESTION: 010 (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.
OUESTION: 011 (1.00)
When normal electrical power is lost, emergency power is provided by batteries to:
- a. area radiatinn monitors, evacuation alarms, and facility emergency lighting.
f b. area radiation monitors, control rod drive system, and evacuation alarms.
- c. neutron detectors, evacuation alarms, and facility emergency lighting. ;
l d. neutron detectors, control rod drive system, and evacuation alarms.
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! OUESTION: 012 (1.00) l l
An abnormal condition is indicated by the lighting of a box on the annunciator panel l and the sounding of an alarm horn. Pressing the " Acknowledge" on the annunciator panel !
or control console will always.
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- 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 *****)
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. J' Page 20 C. FACILITY AND RADIATION MONITORING SYSTEMS QUESTION: 013 (1.00)
During full power operation, the proportional counter is fully withdrawn to its uppermost position so that the:
- a. high count rate interlock will not prevent blade withdrawal.
- b. counter is not damaged by radiation.
- c. "startup channel full-in" Mnunciator will not alarm.
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- d. high count rate will not initiate a reactor scram.
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OUESTION: 014 (1.00) j The shrouds which surround each safety blade have small holes at the bottom. The purpose of these holes is to:
- a. minimize the effect of viscous damping on scram times. ,
- b. provide a cooling water path through the shrouds.
- c. provide points where a shroud lifting tool can be attached.
- d. smooth out the thermal neutron flux distribution at the bottom of the core.
OVESTION: 015 (1.00)
L I Period information is supplied from:
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- a. safety channel #1.
- b. safety channel #2.
- c. log N amplifier.
- d. BF3 channel.
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C. FACILITY AND RADIATION MONIf0 RING SYSTEMS Page 21 OUESTION: 016 (2.00) .
- For the locations labeled 'A' through "H' on Figure 1 and listed in Column I, select the proper component from the item list in Column II. Only one answer may occupy a space in Column I.
Column I (Ficure label) Column II (Item list)
A. 1. Compensated Ion Chamber B. 2. Proportional Counter C. 3. Neutron Source D. 4. Safety Blade E. 5. Regulating Blade F.
G.
H.
I
! (***** END OF CATEGORY C *****)
- (***** END OF EXAMINATION *****)
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4 EQUATION SHEET i 1
1 l 0 = m c, AT CRi (1-Keff): - CR2 (1-Keff)2 l
SUR - 26.06/r P - P 10" a
P = Po e""' r - (t*/p) + [(B-p)/A,,7p] ,
A,r, - 0.1 seconds'1 DR2 D i 2 - DRf 2
i DR - DRo e* DR - 6CiE/D 2 p = (Keff-1)/Keff
- 1 Curie - 3.7x10'8 dps 1 gallon water = 8.34 pounds i.
- 1 Btu - 778 ft-lbf F - 9/5 C + 32 1 & = 3.41x10 5BTU /hr C = 5/9 ( F - 32)
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F/6URE /
1 A. REACTOR THEORY, THERMODYNAMICS AND FACILITY OPERATING CHARACTERISTICS ANSWER SHEET MULTIPLE CHOICE (Circle or X your choice)
If you change your answer, write your selection in the blank.
001 a- b c d 002 a b c d 003 a b c d 4
- 004 a b c d
^
005 a b c d 006 a b c d l 007 a b c d 008 a b c d 009 a b c d 5
010 a b c d
- 011 a b c d l
l 012 a b c d
- 013 a b c d 014 a b c d
- 015 a b c d ;
- 016 a b c d 4
017 a b c d 018 a b c d k
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- 8. NORMAL / EMERGENCY PROCEDURES & RADIOLOGICAL CONTROLS ANSWER SHEET MULTIPLE CHOICE (Circle or X your choice)
If you change your answer, write your selection in the blank.
001 a b c d 002 a b c d 003 a b c d 004 a b c d 005 a b c d 006 a b c d 007 a b c d 008 a b c d 009 a b c d 010 a b c d 011 a b c d 012 a b c d 013 a b c d
, 014 a .b c d l
015 a b c d 016 a b c d 017 a b c d
! 018 a b c d
(
019 a b c d 020 a b c d l
C. FACILITY AND RADIATION MONITORING SYSTEMS ANSWER SHEET MULTIPLE CHOICE (Circle or X your choice)
< If you change your answer, write your selection in the blank.
001 a b c d 002 a b c d 003 a b c d 004 a b c d 005 a b c d 006 a b c d 007 a b c d 008 a b c o 009 a b c d 010 a b c d 011 a b c d 012 a b c d ,
013 a b c d !
014 a b c d l 015 a b c d l
016 a b c d e f g h j i
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(***** END OF CATEGORY C *****) l 1
A. REACTOR THEORY THERMODYNAMICS AND FACILITY OPERATING CHARACTERISTICS ANSWER: 001 (1.00) '
A.
REFERENCE:
Lamarsh. Introduction to Nuclear Engineering 2nd Edition, pg. 288.
0/0, = S(1-p)/(S-p) Since the ratio of the magnitude of the prompt jump to the initial -
power is the same for both reactors. the prompt jump must be larger in Reactor B.
ANSWER: 002 (1.00) !
- 8. !
REFERENCE:
1 Any condition which adds negative reactivity increases shutdown margin.
ANSWER: 003 (1.00)
C.
REFERENCE:
Lamarsh, Introduction to Nuclear Engineering 2nd Edition, pg. 315.
Reactivity due to voids + reactivity of rods = 0 (100 cc)x(Void coefficient) + (0.1% delta k/k/ inch)x(10 inches) = 0 Void coefficient - (1% delta k/k)/100 cc = - 0.01% delta k/k/cc ANSWER: 004 (1.00)
D.
REFERENCE:
Lamarsh, Introduction to Nuclear Engineering, 2nd Edition, pg. 282.
Reactivity = (k-1)/k = (0.955 -1)/0.955 -4.7% delta k/k. If + 3.5% delta k/k is added, the new reactivity will be -4.7% + 3.5% = -1.2%, i.e. subcritical.
ANSWER: 005 (1.00) -
I B. !
~
REFtRENCE:
Lamarsh, Introduction to Nuclear Engineering. 2nd Edition, pg. 281.
ANSWER: 006 (1.00) i D.
REFERENCE:
Lamarsh Introduction to Nuclear Engineering. 2nd Edition, pg. 104.
ANSWER: 007 (1.00) 8.
REFERENCE:
Lamarsh, Introduction to Nuclear Er.gineering 2nd Edition pg. 44.
ANSWER: 008 (1.00)
C.
REFERENCE:
Lamarsh, Introduction to Nuclear Engineering, 2nd Edition, pg. 104.
P P
ANSWER: 009 (1.00)
A.
REFERENCE:
Power Level Calibration Procedure.
For a given count rate over a shorter period of time, the measured flux (i.e. power level) must be higher.
ANSWER: 010 (1.00) 8.
REFERENCE:
Lamarsh. Introduction to Nuclear Engineering. 2nd Edition, pg. 313.
ANSWER: 011 (1.00)
D.
REFERENCE:
Lamarsh. Introduction to Nuclear Engineering. 2nd Edition. pg. 286.
ANSWER: 012 (1.00)
A.
REFERENCE:
Lamarsh. Introduction to Nuclear Engineering. 2rd Eoition. pg. 307.
ANSWER: 013 (2.00)
C.
REFERENCE:
Lamarsh. Introduction to Nuclear Engineering. 2nd Edition, pg. 262.
A total of 70 thermal neutrons (100-20-10) are absorbed in fuel plus other materials.
Since the reactor is critical, there were 40 fissions (40x2.5 = 100). Since 85% of absorptions result in fission, there were 40/0.85 = 47 neutrons absorbed in fuel. The thermal utilization = 47/70 = 0.67.
ANSWER: 014 (1.00)
C.
REFERENCE:
Lamarsh. Introduction to Nuclear Engineering 2nd Edi' ion, pg. 74.
The beta fraction for the fuel is the power weighted average of the beta fractions for each component.
Beta - (0.2)(0.006) + (0.8)(0.008) = 0.0076 ANSWER: 015 (1.00) 8.
REFERENCE:
Experiment 3. Critical Mass Determination.
ANSWER: 016 (1.00)
D.
REFERENCE:
Lamarsh. Introduction to Nuclear Engineering. 2nd Edition, 3g. 279.
The power for reactor A increases by a factor of 2, while t1e power for reactor B increases by a factor of 1.5. Since the periods are the same, power increase B takes a shorter time.
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ANSWER: 017 (1.00)
A.
REFERENCE:
Regulating Blade Worth and Excess Reactivity Measurement Procedure.
ANSWER: 018 (1.00)
C.
REFERENCE:
Lamarsh Introduction to Nuclear Engineering, 2nd Edition, pg. 227.
I l
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B. NORMAL / EMERGENCY PROCEDURES & RADIOLOGICAL CONTROLS l AEWER: 001 (1.00)
C. '
REFERENCE:
WPI Standing Order 2 i ANSWER: 002 (1.00)
A.
REFERENCE:
WPI Fuel Unloading Procedure :
. ANSWER: 003 (1.00)
D. i
~
REFERENCE:
WPI Technical Specifications. Section 2.1. j ANSWER: 004 (1.00) i B.
REFERENCE:
RHSC Regulations and Argon Release Calculations ANSWER: 005 (1.00)
D.
REFERENCE:
WPI Procedure OP-1. ,
4 ANSWER: 006 (1.00)
B.
REFERENCE:
WPI Technical Specifications. Section 2.1.
ANSWER: 007 (1.00) 1 C.
i
REFERENCE:
WPI Technical Specifications. Section 1.0 ANSWER: 008 (1.00)
A. i REFERENCE WPI Technical Specifications. Section 3.3 l
ANSWER: 009 (1.00) l B. 1 I
REFERENCE:
WPI Technical Specifications. Table 4.1 ANSWER: 010 (1.00)
D.
REFERENCE:
WPI Emergency Preparedness Plan. Page 2
. . - - . . . .~- . . - . .-. -. - _ - .- .. - -- .-
l 1
ANSWER: 011 (1.00) i A.
REFERENCE:
WPI Requalification Program ANSWER: 012 (1.00)
D. ;
REFERENCE:
l WPI Technical Specifications, Section 4.3 ANSWER: 013 -(1.00) i
- 8. l
REFERENCE:
I
- WPI Technical Speci fications. Section 1.0 ANSWER: 014 (1.00)
A.
REFERENCE:
j WPI Procedure OP-1.
) ANSWER: 015 -(1.00)
C.
REFERENCE:
- WPI Radiation. Health and Safeguards Committee. Page 2 1
ANSWER: 016 (1.00) i C. I i
REFERENCE:
WPI Technical Specifications., Section 2.1.
ANSWER: 017 (1.00) i B.
REFERENCE:
- SAR. Section 4.5.
, ANSWER: 018 (1.00)
, D.
REFERENCE:
- Rod Drop Measurement Procedure.
, .i ANSWER: 019 (1.00) I A. i' i
REFERENCE:
l 10CFR20.
i
- ANSWER: 020 (1.00)
. C.
I
REFERENCE:
'WPI Emergency Preparedness Plan. Page 2.
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C. FACILITY AND RADIATION MONITORING SYSTEMS l
ANSWER: 001 (1.00)
D. -
REFERENCE:
WPI SAR. Section 4.3.9 ANSWER: 002 (1.00) '
C.
REFERENCE:
WPI SAR. Section 4.3.3 .
1 ANSWER: 003 (1.00)
D. .
REFERENCE. .
WPI SAR. Section 3.2.2 ,
ANSWER: 004 (1.00) I B. D (2 correct answers).
REFERENCE:
'WPI Reactor Instrumentation Setpoint Summary i
ANSWER: 005 (1.00) i C. i
REFERENCE:
WPI Checkout and Operation Procedure i ANSWER: 006 (1.00)
B.
REFERENCE:
WPI Reactor Instrumentation Setpoint Summary ANSWER: 007 (1.00)
A .'
REFERENCE:
WPI SAR Section 4.2.1 ANSWER: 008 (1.00)
D.
REFERENCE:
WPI Technical Specifications. Table 4.1.
ANSWER: 009. (1.00)
A.
REFERENCE:
WPI SAR. Section 4.4 l ANSWER: 010 (1.00) l D.
REFERENCE:
! WPI Technical Specifications. Table 4.1 Y