ML20217G813
| ML20217G813 | |
| Person / Time | |
|---|---|
| Site: | Idaho State University |
| Issue date: | 03/31/1998 |
| From: | Doyle P NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20217G808 | List: |
| References | |
| 50-284-OL-98-01, 50-284-OL-98-1, NUDOCS 9804030056 | |
| Download: ML20217G813 (31) | |
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U. S. NUCLEAR REGULATORY COMMISSION i OPERATOR LICENSING INITIAL EXAMINATION REPORT I REPORT NO.: 50-284/OL-98-01 FACILITY DOCKET NO.: 50-284 FACILITY LICENSE NO.: R-110 FACILITY: Idaho State University EXAMINATION DATES: January 29,1998 EXAMINER: Paul oyle Chief miner SUBMITTED BY: e _ 7~ Jh 78 Paul Doyle, ChieKxapfffer Date
SUMMARY
On January 29,1998, the NRC administered an Operator Licensing Examination to one Senior Reactor Operator (Instant) Candidate at Idaho State University. The candidate passed all' portions of the NRC administered examination.
REPORT DETAILS
- 1. Examiners:
Paul Doyle, Chief Examiner
- 2. Results:
RO PASS / Fall SRO PASS / Fall TOTAL PASS / Fall Written 0/0 1/0 1/0 Operating Tests 0/0 1/0 1/0 Overall 0/0 1/0 1/0
- 3. Exit Meeting:
Paul Doyle, NRC, Examiner John Bennion, Reactor Administrator, Idaho State University Mr Doyle thanked Dr. Bennion, for his support of the examination and reminded him to get his comments on the written examination in quickly.
Enclosure 1 9804030056 980401 PDR ADOCK 05000284 V PDR
4
,4 Facility Comments and NRC Resolution Note: Although the examiner and the facility discussed wntten examination, but no formal comment have been received. The examination in enclosure 3 to this document-contains modifications as discussed at the exit meeting.
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Enclosure 2 -
United States Nuclear Regulatory Commission Operator Licensing Examination w / answer key
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Idaho State University 07/08/97 Enclosure 3
- Section A R Theory. Thermo. and Facility Characteristics Page1 QUESTION (A.1) [1.0)
The neutron source emits neutrons at a rate of 100 N/second. If the reactor K,is 0.8, which ONE of the following is the expected count rate in the reactor?
A. 125 N/second B. 250 N/second C. 375 N/second D. 500 N/second QUESTION (A.2) [1.0)
The reactor is at 5 watts, when someone inserts an experiment which causes a 10 second positive period. If the scram delay time is 1 second and the lowest scram setpcint is 9.7 watts, which ONE of the following is the MAXIMUM power the reactor will reach prior to scramming?
A. 9.1 watts B. 10.7 watts C. 15.5 watts D. 25 watts QUESTION (A.3) [1.0) I Which ONE of the following is the DOMINANT factor in determining the differential reactivity
]
worth of a control rod? l r
A. Radial and axial flux.
B. Total reactor power.
C. Control rod speed.
D. Delayed neutron fraction.
QUESTION (A.4) [1.0] ;
The reactor was shutdown by 1.0% Ak/k, when an experiment was placed into the glory hole. :
Count rate on the startup channelincreased from 15 cps to 30 cps. What is the worth of the experiment? j A. positive 1.01% Ak/k B. negative 1.01% Ak/k C. positive 0.508% Ak/k D. negative 0.508% Ak/k l
Section A R Theory. Thermo. and Facility Characteristica Page 2 QUESTION -(A.5) [1.0)
Glasstone & Sesonske list the delayed neutron fraction for U" (D) as 0.0065. The SAR lists p for the core as 0.0074. The S in the SAR is more commonly referred to as p . Which ONE of the following is the reason that p is larger than Q7 i
A. Delayed neutrons are born at higher energies than prompt neutrons resulting in a greater worth for the neutrons.
B. _ Delayed neutrons are bom at lower energies than prompt neutrons resulting in less leakage during slowdown to thermal energies.
C. The fuel also includes US which has a relatively large p for fast fission.
D. The US in the core becomes Pu" (by neutron absorption), which has a higher p for fission.
QUESTION (A.6) [1.0)
Which ONE of the following correctly describes reactor behavior on four equal (in distance) insertions of the coarse control rod during a startup?
A. Each rod insertion will add an equal amount of reactivity.
B. The time for the subcritical neutron population to stabilize will increase with each withdrawal.
C. The neutron population increase will be less for each withdrawal as you approach criticality.
D. The critical rod height will decrease for an increase in time between rod insertions.
QUESTION (A.7) [1.0)
The Reactor temperature coefficient (a r) is - 0.00025 Ak/k/*C, and initial reactor temperature is !
20*F If you were to insert the coarse control rod adding a reactivity worth of +0.004 Ak/k into the reactor, which ONE of the following would be the final temperature in the core?
A. 4*C 4
B. 36*C C. 72*C D. 108*C I
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Section A B Theory. Thermo. and Facility Characteristics Page 3 QUESTION (A.8) [1.0)
The core design for Reactor A is a sphere of radius R. The core design for Reactor B is a cube with an edge length of R. Neutron leakage from reactor B as compared to A will be:
A. greater B. the same C. slightly less D. much less )
QUESTION (A.9) (1.0) !
Which ONE of the following is the MAJOR source of energy recovered from a fission?
A. Kinetic energy of the fission neutrons.
B. Kinetic energy of the fission fragments.
C. Decay of the fission fragments.
D. Prompt gamma rays.
QUESTION (A.10) [1.0)
Select the statement below vehich best describes delayed neutrons.
2 A. Neutrons emitted from the fission of U 3s that have an energy less than % Mev.
B. Neutrons reflected back into the core by the reflector, and subsequently cause fission.
C. Neutrons emitted by spontaneous fission of the fuel after the reactor is shutdown.
D. Neutrons emitted because of the p decay of certain fission products.
QUESTION (A.11) [1.0)
The term PROMPTJUMP refers to ...
A. the instantaneous change in power due to raising a control rod.
B. a reactor which has attained criticality on prompt neutrons only.
C. a reactor which is critical using both prompt and delayed neutrons.
D. a negative reactivity insertion which is greater than p.
- c Section A R Theory. Thermo. and Facility Characteristics Page 4 QUESTION (A.12) [1.0)
Inelastic scattering is the process by which a neutron collides with a nucleus and ....
A. recoils with the same kinetic energy it had prior to the collision B. recoils with a lower kinetic energy than it had prior to the collision, with the nucleus emitting a gamma ray.
C. is absorbed, with the nucleus emitting a gamma ray.
D. recoils with a higher kinetic energy than it had prior to the collision, with the nucleus emitting a gamma ray.
QUESTION (A.13) [1.0]
Which ONE of the following isotopes is both 'issile and occurs in nature?
A. U 233 B. Ursa C. Un2 D. Th 232 QUESTION (A.14) [1.0)
Which ONE of the following is an example of beta (D) decay?
87 A. 3 Br - > 33As
B. xBra7 ->uBr88 88 C. 3 Br*7->uSe t
s7 87 D. 3 Br ->3 Kr l l
QUESTION (A.15) (1.0)
With a constant period, increasing power from 10% to 30% power will take about as long )
as increasing power from 50% to 75%
A. 2.7 B. 2.0 C. 1.25 D. 0.8
Sechon A R Theory. Thermo. and Facility Characteristics Page5
' QUESTION (A.16) [1.0)
Which ONE of the following is the definition of effective multiplication factor (K,)?
A. # of neutrons produced from all fissions
- of neutrons in the previous generation.
B. # of neutrons produced from fast fissions
- of neutrons produced from thermal fission.
C. # of neutrons absorbed in the fuel
- of neutrons absorbed by fission products D. # of neutrons in the present oeneration
- of neutrons in the previous generation.
QUESTION (A.17) [1.0] -
You are performing a startup and the reactor is critical at a very low power level. If you establish a 26 second period, how long will it take to increase reactor power by a factor of 10,0007 A. 1 minute B. 2 minutes C. 3 minutes D. 4 minutes 1
END OF SECTION A
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Section B Normal. Emeroency and Radioloaical Control Procedures Page 6 QUESTION (B.1) [1.0)
Which ONE of the following is the power level above which the thermal column door must be closed?
A. 0.01 watts l
B. 0.05 watte I C. 0.1 watts I i
D. 0.5 watts j QUESTION (B.2) [1.0) j Which ONE of the following conditions violates Technical Specifications for Operating Staff?
(Note 2" person denotes a person certified by Reactor Supervisor as qualified to activate manual scram and initiate emergency procedures.)
A. SRO on panel,2" person in reactor room, no one on-call.
B. RO on panel,2"' person in reactor room, SRO on-call. ]
l C. SRO on panel, SRO on-call, no 2" person in reactor room. I i
D. RO on panel, SRO in reactor room, no one on-call.
QUESTION (B.3) [2.0, 0.5 each)
Match the Operator License requirement (from 10 CFR 55) in Column A with the proper time period from column B.
Column A Column B A. License Renewal 1. 1 year B. Medical Examination 2. 2 years C. Requalification Written 3. 3 years D. Requalification Operating Test 4. 4 years
- 5. 5 years
- 6. 6 years
Section B Normal. Emeroency and Radioloaical Control Procedures Page 7 QUESTION (BA) [1.0)
Which ONE of the following is the definition of a Safety Channel?
A. A combination of sensor, lines, amplifiers and output devices which are connected for the purpose of measuring or responding to the value of a process variable B. Any apparatus devices or material that is a normal part of the reactor assembly.
C. A combination of safety channels and associated circuitry which forms an automatic protective system for the reactor, or provides information which requires manual protective be initiated.
D. A measuring channel in the reactor safety system QUESTION (B.5) (2.0,0.5 each]
Identify each of the following values as either a Safety Limit (SL), a Limited Safety Setting (LSSS) or a Limiting Condition for Operation (LCO).
A. Power 2100 watts )
B. Temperature a 120 C C. Excess Reactivity 0.70% Ak/k (corrected to 20*C) l D. Failure of Shield Water interlock.
QUESTION (B.6) (1.0) j Which ONE of the following materials may NOT be irradiated in the reactor?
A. Materials corrosive to reactor components.
B. Fissionable Materials.
1 C. Explosive Materials. j l
D. Liquid Materials.
QUESTION (B.7) [1.0)
Which ONE of the following conditions requires the thermal column to be filled with water or '
graphite?
A. Critical Experiment B. During use of neutron radiography collimator.
C. Measuring reactivity worth of thermal column water or graphite.
D. Reactor power calibration
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Section B Normal. Emeraency and Radioloaical Control Procedures Page 8 QUESTION (B.8) [1.0]
Rod scram times were performed in January 1997. Identify the last month in which the surveillance must be performed without exceeding a Tech Spec requirement.
A. June,1997 B. August,1997 C. January,1998 D. May,1998 QUESTION (B.9) [1.0]
Which ONE of the following reactor shutdowns is only to be performed if power is less 0.1 watt?
A. Decrease sensitivity of either Channel #1 or Channel #3 to produce a low level scram.
B. Insert reactivity & allow power to increase without a range change until a high level trip on either Channe! #1 or Channel #3 occurs.
C. Shut off the console power.
D. Simulate an earthquake QUESTION (B.10) [1.0]
ISU Surveillance procedures 1,2 and 3 require working on energized equipment. Which ONE of the following conditions must be met to work on energized equipment? In accordance with these procedures another person must be present who is .
A. qualified to administer Cardio-Pulmonary Resuscitation (CPR).
B. familiar enough with the facility to deenergize the console.
C. a qualified Emergency Medical Technician (EMT).
D. familiar enough with facility procedures to initiate the emergency plan.
QUESTION (B.11) [1.0]
Which ONE of the following is NOT a recognized method (per the Emergency Plan) to verify the reactor has scrammed?
A. Rods Engaged Lights Out.
B. Decreasing current trace on channels 2 and 3 strip charts.
C. Audible bang when rods hit bottom.
D. Period meter pegged low.
Section B Normal. Emeroency and Radiolooical Control Procedures Page 9 QUESTION (B.12) [1.0]
Given the following information, calculate the half-life of the sample.
Time (in minutes) Counts per minute 0 900 30 740 60 615 90 512 120 427 180 294 A. 551 minutes B. 122 minutes C. 111 minutes D. 100 minutes QUESTlON '(B.13) [1.0)
During a survey you read 100 mrem /hr with the window open and 40 mrem /hr with the window closed. Which ONE of the following is the dose rate due to GAMMA radiation?
A. 140 mrem /Hr B. 100 mrem /Hr C. 60 mrem /Hr
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D. 40 mrem /Hr QUESTION (B.14) [1.0) j Identify which ONE of the following correctly describes the relative penetrating power of the '
listed types of radiation from least penetrating to most penetrating.
A. a. p, y B. a, y, p C. y, a, p D. y,p,a E. p, a, y F. p,y,a 1
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I Section B Normal. Emeroency and Radioloaical Control Procedurel Page 10 QUESTlON (B.15) [2.0] Question changed justprior',to administrati6ni You have a 100 mrem /hr field due to 0.75 Mev gammas. You need to reduce the field to 5 mrem /hr. You've used 15 cm of water and 45 cm of concrete. How much lead must you add?
(Show all work) The attenuation coefficient (p) for water, concrete and lead are 0.0785,0.18 and 1.235 cm respectively.
A. 7.5 cm B. 3.75 cm C. 0.75 cm D. 0.375 cm l
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END OF SECTION B
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Section C Plant and Radiation Monitorina Systems Page 11 QUESTION (C.1) [1.0)
Which ONE of the following is the approximate value for how much negative reactivity would be added to the reactor if the safety fuse were to melt?
1 A. 0.005 Ak/k i I
B. 0.01 Ak/k I C. 0.05 Ak/k i
D. 0.1 Ak/k QUESTION (C.2) [1.0)
Which ONE of the listed materials will add positive reactivity if placed into the glory hole?
A. Virgin Polyethylene B. Cadmium Plug C. Gold Foils D. Borated Polyethylene QUESTION (C.3) [1.0]
Which ONE of the following detectors is the type used for Safety Channel #17 A. BF3filled Proportional Counter B. BF3 filled Compensated lonization Chamber C. BF3 filled Uncompensated lonization Chamber D. U 25 lined Fission Chamber QUESTION (C.4) [1.'l Where would you go to d lergize the ventilation system during an emergency?
A. On the reactor rou.n wall opposite room 15 (Reactor Supervisor Office)
B. On the corridor wall just outside the door to room 23 (Suberitical Assembly Laboratory).
C. On the corridor wall just outside the door to room 19 (Reactor Observation Room).
D. Just inside the door to room 22 (Counting Laboratory).
e Sechon C Plant and Radiation Monitorina Systems Page 12
' QUESTION .(C.5) [1.0) Question _ chen0ed Wadministfalion:
Which ONE of the following is NOT an interlock preventing rod wdWrewelinsertiori?
A. Both safety rods must be fully inserted prior to inserting the coarse control rod.
B. Both safety rods must be fully inserted prior to inserting the fine control rod.
C; The coarse control rod must be fully withdrawn prior to inserting the safety rods.
D. The fine control rod must be greater than or equal to half inserted prior to inserting the safety rods.
QUESTION (C.6) [2.0,0.4 each)
Match the purpose in column A with the correct material Column A Column B A. fast neutron shield 1. Lead B. reflector 2. Graphite C. gamma-ray shield 3. Beryllium D. moderator in core 4. Aluminum E. moderator in fuse 5. Polyethylene
- 6. Polystyrene
- 7. Water QUESTION (C.7) [1.0)
Which ONE of the following is the gas used in the rabbit tube assembly.
A. Air B. Carbon Dioxide C. Helium D. Nitrogen QUESTION (C.8) [1.0)
Which ONE of the following signals will result in opening the interlock bus?
A. Manual scram switch B. Period trip '
C. Earthquake sensor D. Channel #1 high (95% full scale)
Section C Plant and Radiation Monitorina Systems Page 13 QUESTION (C.9) [1.0]
Which ONE of the following is NOT a characteristic associated with using fueled control rods ,
vice poison control rods? l A. Smaller reactor size.
B. Less than critical mass when shutdown.
C. More symmetrical flux distribution when operating.
D. More difficult calculations for a homogeneous reactor, ,
I QUESTION (C.10) [1.0]
' Which ONE of the following provides the motive force for control rod withdrawal during a SCRAM?
A. Gravity B. Spring C. Fast Motor l
D. Gravity and spring.
QUESTlON (C.11) [2.0,0.25 EACH] Question changed during administration Identify the following parts on the number rod drive mechanism from Figure 1 attached to your handout.
A. Capsule i B. Lead Screw I
C. Motor D. Bearing E. Dash Pot )i F. Sy~trcc Uplimit adjust screw 1 G. Magnet H. Chain Drive 1
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I Section C Plant and Radiation Monitorina Systems Page 14 QUESTION (C.12) [1.0)
Which ONE of the following is the reason you manipulate the Channel #1 RANGE switch when the Channel #1 detector is raised?
A. To ensure three channels of indication.
B. To preclude a high power trip.
C. To preclude a low power trip.
D. To ensure three channels of protection.
QUESTION (C.13) [1.0)
Which ONE of the following ensures a scram would occur in spite of a grid to cathode short in the 6L6 vacuum tube in the Safety Chassis?
A. Magnet current Reversal Relay.
B. Sensitrol Reset Relay.
C. Overcurrent Meter Relay.
D. Interlock Bus Reset Relay. ;
I QUESTION (C.14) [1.0] J Which ONE of the following statements correctly completes the sentence concerning the access ports? The access ports ..
A. penetrate through the shield tank, passing by the reflector and the lead shield.
1 B. pass through the shield tank up to the lead shield j C. pass through the shield tank, lead shield and the reflector up to the core container.
D. pass through the shield tank up to the reflector QUESTION (C.15) [1.0]
The reactor is critical, with the Fine Control Rod (FCR) fully inserted. If you wish to reposition the FCR to the mid-plane of its travel, how far and in what direction must you move the Coarse Control Rod (CCR), maintaining critical conditions?
A. 6.7 cm, out of core B. 3.3 cm, into core C. 3.3 cm, out of core D. 6.7 cm, into core END OF SECTION C END OF EXAMINATION
Section A R Theory. Thermo. and Facility Characteristics Page 15 A.1 D
REFERENCE:
Glasstone, S. And Sesonske, A NuclearReactorEngineering, Kreiger Publishing, Malabar, Florida, 1991,9 3.162 A.2 B
REFERENCE:
Glasstone, S. And Sesonske, A, NuclearReactorEngineering, Kreiger Publishing, Malabar, Florida,1991, S 5.18 P=Po e'" = 9.7 x e " = 9.7 x 1.1052 = 10.72 A.3 A
REFERENCE:
Glasstone, S. And Sesonske, A, NuclearReactorEngineering, Kreiger Publishing, Malabar, Florida, 1991,9 5.225.
A.4 C
REFERENCE:
SDM = 1 - K.,/K,, or K,, = 1/(1 + SDM) = 1/(1 + .01) = 0.990 CR,/CR2 = (1 - K,n)/(1 - K.,,) or 1 - K,n = (1 - K.,,) CR,/CR2 = 0.0099 (15/30) = 0 00495 1 - K,n = 0.00495 K., = 1 - 0.00495 = 0.995 Reactivity Added = (K,,, - Kon)/K,,,K,n
= (0.990 - 0.995)/(0.995 x 0.990) = 0.005076 (positive) or 0.508%
A.5 B
REFERENCE:
Burn, R., Introduction to Nuclear Reactor Operations, @ 1988, @ 3.2.4.
A.6 B
REFERENCE:
Glasstone, S. And Sesonske, A, NuclearReactorEngineering, Kreiger l Publishing, Malabar, Florida,1991, S 5.288.
A.7 A
REFERENCE:
Temp. = p/a r= (-0.004GO)/(-0.000250 = 400/25 = 16* 20 + 16 = 36 A.8 A
REFERENCE:
Glasstone, S. And Sesonske, A, NuclearReactorEngineering, Kreiger Publishing, Malabar, Florida,1991, $ , p.154. i A.9 8 .
REFERENCE:
Glasstone, S. And Sesonske, A, NuclearReactorEngineering, Kreiger q Publishing, Malabar, Florida,1991, S@ 1.51 & 1.52, and Table 1.2, p.16.
A.10 D '
REFERENCE:
P = Poe'". The increase with the greatest P/Po will take the longest time.
1 A.11 A
REFERENCE:
Glasstone, S. And Sesonske, A, NuclearReactorEngineering, Kreiger i I
Publishing, Malabar, Florida, 1991, @ 5.31, p. 240.
A.12 B
REFERENCE:
Glasstone, S. And Sesonske, A, NuclearReactorEngineering, Kreiger Publishing, Malabar, Florida,1991, SS 2.88 - 2.93, pp. 70 & 71.
A.13 C
REFERENCE:
Glasstone, S. And Sesonske, A, NuclearReactor Engineering, Kreiger Publishing, Malabar, Florida, 1991, @$ 141 - 142, pp.13 & 14.
e Section A R Theory. Thermo. and Facility Characteristics Page 16 A.14 D-
REFERENCE:
Chart of the Nuclides A.15 A
REFERENCE:
Time is proportiorial to In(Pp) whic'h implies ratio will be in(Pp),
divided by in(Pp)2 in(3)/In(1.5) = 2.7 A.16 D
REFERENCE:
NRC examination administered 6/90.
A.17 D
REFERENCE:
In(10,000) = (time,e.)/26 9.210 = time /26 time = 26 x 9.210 =
239.467 or 4 minutes.
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END OF SECTION A r
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Section B Normal. Emeroency and Radiolooical Control Procedures Page 17 B.1 D
REFERENCE:
ISU TS 9 3.4 B.2 C
REFERENCE:
ISU TS 9 6.1.9 B.3 A,6; B,2; C,2 or 1: D,1 Answer added por facilitp comment st exPLmeetingSSU PW"":#Mplan has yearly written,
REFERENCE:
10 CFR 55.21,10 CFR 55.55, & 10 CFR 55.59 B.4 D
REFERENCE:
ISU TS 91.0 Definitions j j
B.5 A, SL; B, LSSS; C, LCO; D, LCO
REFERENCE:
ISU TS 99 2.1,2.2 and 3.0 B.6 C
REFERENCE:
ISU TS 9 3.3 B.7 D ;
REFERENCE:
ISU TS,9 3.4.
B.8 D l
REFERENCE:
ISU TS 9 4.2 j l
B.9 D
REFERENCE:
AGN Operating Procedure #1,9 Vil.A steps 2,4,5 & 8.
B.10 B
REFERENCE:
ISU Surveillance Procedures,1,2 and 3, Step I.A B.11 C
REFERENCE:
ISU Emergency Plan, @ 2.0 EMERGENCY PROCEDURES, Fire or Explosion steps 1 a, b & c.
B.12 C
REFERENCE:
A=AeM g A
294 = 900e A180 = A = 0.00621 180 In(0.5) , g3$
B.13 D
REFERENCE:
Dose (y) = Dose with window closed B.14 A
REFERENCE:
Glasstone, S. And Sesonske, A, NuclearReactorEngineering, Kreiger Publishing, Malabar, Florida, 1991, 9@ 2.20 - 2,79, pp. 46 - 67.
Section B Normal. Emeraency and Radioloaical Control Procedures Page 18 B.15 C
REFERENCE:
I=la xe w sro) , ,ww.) , ,wenn in(1/l o ) = pmox gro + pm. %. + pg, xp,
-2.996 + 0.0785(15) + 0.18(5) = 1.235(X) = -2.996 + 1.1775 + 0.9 = -0.918
-0.918 = 1.235(X) X = -0.918/1.235 = -0.7435 l
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1 END OF SECTION B
Section C Plant and Radiation Monitorina Systems Page 19 C.1 C
REFERENCE:
ISU Technical Specifications (TS), S 2.1 BASIS C.2 A
REFERENCE:
NRC examination Bank C.3 A
REFERENCE:
ISU SAR 9 4.3.2, P. 61 C.4 A
REFERENCE:
Emergency Plan,6 2.0 EMERGENCY PROCEDURES, Nuclear Ememency1#3.
C.5 D
REFERENCE:
ISU SAR $ 3.1 Control Rods C.6 A,7; B,2; C,1; D,5; E,6;
REFERENCE:
ISU, Safety Analysis Report (SAR),9 4.2, Table 4.2-1 C.7 D
REFERENCE:
NRC examination bank C.8 C
REFERENCE:
NRC examination question bank.
C.9 D
REFERENCE:
Rewrite of NRC examination question administered May 1988 C.10 D
REFERENCE:
Rewrite of NRC examination question administered 5/88.
C.11 A,1; B,6; C,8; D,5; E,7; F,4; G,2; H,3
REFERENCE:
NRC administered examination 5/88 C.12 C
REFERENCE:
NRC Exam administered 6/90.
C.13 C
REFERENCE:
NRC Examination administered 6/90.
C.14 C
REFERENCE:
NRC examination administered 6/90.
C.15 B
REFERENCE:
NRC examination administered 6/90.
END OF SECTION C END OF EXAMINATION
D o
U. S. NUCLEAR REGULATORY COMMISSION NON-POWER INITIAL REACTOR LICENSE EXAMINATION FACILITY: Idaho State University REACTOR TYPE: AGN-201 DATE ADMINISTERED: July 8,1996 REGION: IV CANDIDATE:
INSTRUCTIONS TO CANDIDATE:
Answers are to be written on the answer sheet provided. Attach the answer sheets to the examination. Points for each question are indicated in brackets for each question. A 70% in each section is required to pass the examination. Examinations will be picked up three (3) hours after the examination starts.
% OF '
CATEGORY % OF CANDIDATE'S CATEGORY
_VALUE TOTAL SCORE VALUE CATEGOR';
17.00 - 7 3L7_ A. REACTOR THECRY, THERMODYNAMICS AND FACILITY OPERATING CHARACTERISTICS i- 18.00 34.6 B. NORMAL AND EMERGENCY OPERATING PROCEDURES AND RAplOLOGICAL CONTROLS -
17.00 27_ C. PLANT AND RADIATION MONITORING SYSTEMS i
52.00 % TOTALS ;
FINAL l
GRADE
' j All work done on this examination is my own. I have neither given nor received aid. ]
i i
l Candidate's Signature -
1..
,t L,
r NRC RULES AND GUIDELINES FOR LICENSE EXAMINATIONS -
-During the administration of this examination the following ru'les 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 neither received nor given assistance in completing the !
examination. This must be done after you complete the examination. 1
- 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. i j
- 4. Use black ink or dark pencil g_n.!y n to facilitate legible reproductions. I l
- 5. Print your name in the blank provided in the upper right-hand comer of the examination cover sheet I and each answer sheet.
- 6. Mark your answers on the answer sheet provided. USE ONLY THE PAPER PROVIDED AND DO NOT WRITE ON THE BACK SIDE OF THE PAGE.
- 7. The point value for each question is indicated in (brackets) after the question.
- 8. If the intent of a question is unclear, ask questions of the examiner only.
- 9. '
When tuming in your examination, assemble the completed examination with examination questions,
. examination aids and answer sheets. In addition turn in all scrap paper.
L 10. Ensure all information you wish to have evaluated as part of your answer is on your answer sheet.
Scrap paper will be disposed of immediately following the examination. )
l
- 11. To pass the examination you must achieve a grade of 70 percent or greater in each category.
11 2.' There is a time limit of three (3) hours for completion of the examination.
- f13.- When you have completed and tumed in you examination, leave the examination area. If you are
- obsarved in this area while the examination is still in progress, your license may be denied or revoked.
a, -
- 1. __ . _ _ _ _ _ _ _ . . _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ . . _ _ _ _ _ . _ _ _ _ _ . _ _ _ _ _ _ . _ _ _ _ _ . _ . _ _ _ _ _ _
o-j, EQUATION SHEET Q = thc, bT = rh bH = UA bT p" , (p-0) 2a(k)t
. I' = 1 x 10** seconds SCR = E =
-p 1-K,,
A,, = 0.1 seconds-1 CR,(1-K,,,) = CR2 (1'Ker,)
CR (-p,) = CR 2(~P2) 3
^
M= '"*
SUR = 20.06 .
i
.S-P. 1 -K,,,
M= 1
=
CR, p = p,10sn 1 -K,, CR2 1
SDM = (1-K,,) p,pe 0 i gow T= I' _ P = OII ~P) Po p_p D-P Ap=
K,,, - K,,, T = g- + }.9 \
k,,, x K,,, p h,p_
7.% , 0.693 (K,,-1)
A P= gee DR #DR o e
- DR,d, = DR22 d DR - Rem, Ci- curies, DR = 6CiE(n) E - Mev, R - feet g2 (p2-0)* ,
(Pt- 0)*
Peak2 Peak, 1 Curie = 3.7 x 10 dis /sec 1 kg = 2.21 lbm 8
i Horsepower = 2.54 x 10 BTU /hr 1 Mw = 3.41 x 10' BTU /hr
.1 GTU = 778 ft-lbf
- F = 915
- C + 32 1 gal (H,0) = 8 lbm *C = 5/9 (*F - 32) ;
1 c, o 1.0 BTU /hr/lbmI* F c, = 1 callsec/gmI*C ]
i
C 1
SECTION A A.1 ABCD A.10 A B C D A.2 A.B C D A.11 - A B C D A.3 ABCD A.12 A B C D A.4 ABCD A.13 A B C D A.5 ABCD A.14 A B C D A.6 ABCD A.15 A B C D A.7 ABCD A.16 A B C D A.8 ABCD A.17 A B C D 4
A.9 ABCD 1
q 1
j I
i
_ __ __:__ a
~
a SECTidN B B.1 ABCD B.6 'ABCD B.2 ABCD B.7 'A B C D _
Years B.3 A.123456 B.8 ABCD Years B123456 B.9 ABCD Years C123456 B.10 A B C D Years
.D123456 B.11 A B C D l
B.4 ABCD B.12 A B C D I B.5A SL LSSS LCO B.13 A B C D B SL LSSS LCO B.14 A B C D C SL LSSS LCO B.15 A B C D D SL LSSS LCO I
9 SECTION C C.1 ABCD C.10 A B C D C.2 ABCD C.11 A 1 2 3 4 5 6 7 C.3 ABCD B12 3 4 5 6 7 C.4 . A B C D C12 3 4 5 6 7 C.S . A B C D D1234567 C.6A 1 2 3 4 5 6 7 E1234567 B1234567 F1234567 C1234567 G1234567 D1234567 H12 3 4 5 6 7 E1234567 C.12 A B C D F1234567 C.13 A B C D C.7 ABCD C.14 A B C D C.8 ABCD C.15 A B C D C.9 A B C'D