ML20141A340
| ML20141A340 | |
| Person / Time | |
|---|---|
| Site: | Purdue University |
| Issue date: | 06/17/1997 |
| From: | Doyle P NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20141A324 | List: |
| References | |
| 50-182-OL-97-01, 50-182-OL-97-1, NUDOCS 9706200238 | |
| Download: ML20141A340 (35) | |
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U. S. NUCLEAR REGULATORY COMMISSION OPERATOR LICENSING INITIAL EXAMINATION REPORT REPORT NO.:
50-182/OL-97-01 FACILITY DOCKET NO.:
50-182 FACILITY LICENSE NO.:
R-87 FACILITY:
Purdue University EXAMINATION DATES:
June 2 - 3,1997 EXAMINER:
Paul Doyle, Chief Examipe l
SUBMITTED BY:
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77 Paul boyW, C,rf4f Examiner Date
SUMMARY
During the week of June 2,1997 the NRC administered an Operator Licensing Examination to one Reactor Operator Candidate at Purdue University. The candidate failed Section B of the written examination and passed all other portions of the examination.
REPORT DETAILS 1.
Examiner Paul Doyle, Chief Examiner 2.
Results:
RO PASS / Fall SRO PASS / Fall TOTAL PASS / FAIL Written 0/1 0/0 0/1 Operating Tests 1/0 0/0 1/0 Ovar:!:
0/1 0/0 0/1 3.
Exit Meeting:
Paul Doyle, NRC, Examiner Ed Merrit, Purduo University, Reactor Supervisor i
Frank Clikeman, Purdue University, Laboratory Director 1
During the exit meeting the facility staff gave their comments on the written examination.
The examiner thanked the facility for their assistance in the adminstration of the examinations.
l I
o ENCLOSURE 1 l
9706200238 970618 PDR ADOCK 05000182 l
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Comments on NRC Written Examination along with NRC Resolutions i
l Question A.3 Comment:
This question has no correct answer.
NRC Resolution:
Agree. Question Deleted.
l i
i Question A.10 Comment:
Ensure people realize that correct answer should include neutrons due to gamma reactions within the shutdown core.,
NRC Resolution:
l Agree. There is no need to change answer key. Question will be modified prior to its next use on an examination.
1 l
Question A.17 i
Comment:
l l
The answer to this question should be c instead of a.
NRC Resolution:
Agree. Answer key modified to accept c as correct answer.
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Section A R Theory. Thermo. and Facility Characteristics Page 2 l
QUESTION (A.1) [1.0]
l Several processes occur during the neutron cycle which increase or decrease the number of neutrons. Which ONE of the following describes a process which INCREASES the number of neutrons?
i a.
Fast Non-Leakage probability ($)
l b.
Resonance Escape Probability (p) c.
Thermal Utilization Factor (f) d.
Reproduction Factor (q)
OUESTlON (A.2) [1.0]
Question Deleted Which ONE cf the fcllcw ng ctctcm:nic ic th; dc':nltlcn of l?CACHi?!"
I c.
A mcccurc of the ccic'; fucl dcplctica.
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A mcccurc of the cccc'c dcvictica frcm prompt criticc:lty-c.
Equcl tc 1.00 AK/K when the rccctcr is crit;ccl.
)
d.
Equcl to 1.00 AK!K when the rcccist ls picmpt crit lcc'.
l QUESTION (A.3) [1.0]
l A thin foil target of 10% copper and 90% aluminum is in a thermal neutron beam. Given o, = 3.79 barns, o,
= 0.23 barns, o, = 7.90 barns, and o,
=1.49 barns, which ONE of the j
l iollowing reactions has the highest probability of occurring?. A neutron..
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l a.
scattering reaction with aluminum.
i b.
scattering reaction with copper.
c.
absorption in aluminum.
d.
absorption in copper.
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i S.qction A R Theory. Thermo. and Faci 0tv Characteristics Page 4 QUESTION (A.7) [1.0]
Excess reactivity is the amount of reactivity
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t a.
associated with samples.
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b.
required to achieve prompt criticality.
l c.
available above that required to make the reactor critical.
d.
associated with Xenon production.
QUESTION (A.8) [1.0)
Which ONE of the following is the purpose for having a neutron source?
a.
To compensate for neutrons absorbed by experiments installed in the reactor.
b.
To generate a sufficient population to start a fission chain reaction for reactor startup.
c.
To provide a means for allowing reactivity changes to occur in a subcritical reactor.
d.
To generate a detectable neutron level for monitoring reactivity changes in a shutdown reactor.
QUESTION (A.9) [1.0]
The reactor is shutdown by 0.015 AK/K. The Startup range count rate is 15 counts per minute.
After placing a sample into the reactor the coun't rate increases to 60 counts per minute. What is the worth of the sample?
a.
+ 0.0006 b.
+ 0.0113 c.
- 0,0006 d.
- 0.0113 I
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Section A R Theorv. Thermo. and Facility Characteristics Page 2 QUESTION (A.1) [1.0)
Several processes occur during the neutron cycle which increase or decrease the number of j
neutrans. Which ONE of the following describes a process which INCREASES the number of neutroi.c7 a.
Fast Non-Leakage probability (%)
b.
Resonance Escape Probability (p) i c.
Thermal Utilization Factor (f) l d.
Reproduction Factor (rl)
OUEST!ON (A.2) [1.0]
Question Deleted
?!hich ONE cf the fcllc :ng ::cicm nt; l: the d:Snitica of REACT!V!TV?
c.
? meccur; cf th; ccic's fucl dcp! t:ca.
b.
A mcccurc of th; cccc's devict:ca from prompt crit lcc ;ty.
l c.
Equcl tc 1.00 AK/K when the rcccict is crit;cci.
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d.
Equcl to 1.00 A!'JK when the ics; tor is prompt ci;tlcc'.
l QUESTION (A.3) [1.0]
A thin foil target of 10% copper and 90% aluminum is in a thermal neutron beam. Given l
o,,, = 3.79 bams, c., = 0.23 barns, o,,, = 7.90 barns, ar..i o,
=1.49 barns, which ONE of the I
following reactions has the highest probability of occurring?. A neutron.
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a.
scattering reaction with aluminum.
b.
scattering reaction with copper.
c.
absorption in aluminum.
d.
absorption in copper.
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Section A R Theory. Thermo. and Facility Characteristic 2 Page 3 1
QUESTION (A.4) [1.0]
Which ONE of the following is the MAJOR recoverable source of energy released during the fission process?
a.
Prompt gamma rays b.
Neutrinos c.
Capture gamma rays d.
Kinetic energy of the fission fragments.
QUESTION (A.5) [1.0]
Which ONE of the following isotopes would cause a colliding neutron to lose the most energy?
a.
H b.
H' c.
C
d.
U23s QUEST!ON (A.6) [1.0]
Which ONE of the following describes the difference between prompt and delayed neutrons?
Prompt neutrons..
a.
account for less than one percent of the neutron population, while delayed neutrons account for the rest.
b.
are released during fast-fission events, while delayed neutrons are released during thermal neutron events.
c.
are released during the fission process (fast & thermal), while delayed neutrons are released during the decay process, d.
are the dominating factor in determining i 9 actor period, while delayed neutrons have little effect on reactor period.
Section A R Theory. Thermo. and Facility Characteristics Page 4 QUESTION (A.7) [1.0]
Excess reactivity h the amount of reactivity..
a.
associated with samples.
b.
required to achieve prompt criticality, c.
available above that required to make the reactor critical.
d.
associated with Xenon production.
QUESTION (A.8) [1.0]
Which ONE of the fc" wing is the purpose for having a neutron source?
To compensate for neutrons absorbed by experiments installed in the reactor.
a.
b.
To generate a sufficient population to start a fission chain 'eaction for reactor startup.
To provide a means for allowing reactivity changes to occur in a suberitical reactor.
c.
d.
To generate a detectable neutron level for monitoring reactivity changes in a shutdown reactor.
QUESTION (A.9) [1.0]
The reactor is shutdown by 0.015 AK/K. The Startup range count rate is 15 counts per minute.
After placing a sample into the reactor the count rate increases to 60 counts per minute. What is the worth of the sample?
a.
+ 0.0006 b.
+ 0.0113 c.
- 0,0006 d.
- 0.0113
Section A R Theory. Thermo. and Facility Characteristics Page5 QUESTION (A.10) [1.0]
Which ONE of the following is the reason that G power stabilizes several hours after shutdown?
(Assume source inserted in core, nuclear instrumentation is operable and reading on-scale, and no reactivity changes are in progress.)
a.
Continuing decay of the shortest lived neutron precursor.
b.
Gamma saturation of the fission chamber, c.
Suberitical multiplication of source neutrons.
d.
Neutron activation of the fission chamber.
QUESTION (A.11) [1.0]
The book Nuclear Reactor Engineering, by Glasstone & Sesonske states that the delayed neutron fraction (D) for u2"is 0.0065. However your Safety Analysis report states the D,%,,is approximately 0.0075. Why is D,w,, larger than p?
a.
The fuel contains U2" which has a large p for fast fissions.
b.
The fuel contains Pu " which has a large p for thermal fissioning.
2 Delayed neutrons are born at a higher energy level than fission neutrons resulting in a c.
greater amount of neutrons from fast fissions.
d.
Delayed neutrons are born at a lower energy level than fission neutrons resulting in fewer being lost to fast leakage.
QUESTION (A.12) [1.0]
You've shutdown the reactor and power is decreasing at a steady negative period. The fission chamber output reads 100 cpm. What would you expect reactor power to read 3 minutes later?
a.
50 cpm b.
25 cpm c.
10 cpm d.
5 cpm l
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HerJ;gfLTheory Thermo. and Facility Characteristics Page 6 QUESTION (A.13) [1.0]
Which ONE of the four factors listed that is MOST affected by an increase in poison level in the reactor?
a.
Fast fission factor (c) b.
Thermal Utilization factor (f) c.
Resonance Escape probability (p) d.
Reproduction Factor (rl)
QUESTION (A.14) [1.0)
Which ONE would be the resultant K, for an exactly critical reactor where all of the delayed neutrons were instantaneously removed?
a.
1.007 b.
1.000 c.
0.993 d.
0.000 QUESTION (A.15) (1.0)
K, for the reactor is 0.85, when you place an experiment worth +16% AK/K into the core. The new K.,is.
a.
1.01 b.
0.98 c.
0.93 d.
0.90 l
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Section A R Theory. Thermo. and Facility Characteristira Page 7 QUESTION _ (A.16) [1.0]
With the reactor on a constant period which transient will take the LONGEST time to complete?
A reactor power change of...
5% of rated power, going from 1% to 6% of rted power.
a.
b.
10% of rated power, going from 10% to 20% +: rated power.
15% of rated power, going from 20% to 35% of rated power.
c.
d.
20% of rated power, going from 40% to 60% of rated power.
QUESTION (A.17) [1.0]
Regulating rod worth for a reactor is 0.001 AK/K/ inch. The moderator temperature coefficient (cir
) for the same reactor is 0.0005 AK/K/*F. If moderator temperature increases by 9'F.
By how much, and in which direction must the regulating rod move to compensate?
a.
4% inches, outward b.
9 inches, outward c.
4% inches, inward d.
9 inches, inward QUESTION (A.18) [1.0)
In a CRITICAL reactor, of 100 fast neutrons produced from fission,20 neutrons are captured in resonance peaks, and 10 leak out. The remainder are absorbed in the core (fuel and other materials). Each fission produces 2.5 neutrons, and 85% of the neutrons absorbed in the fuel result in fissions. For this reactor the thermal utilization factor (f) is: (SHOW ALL WORK) a.
0.47 b.
0.62 c.
0.67 d.
1.61
i Section A R Theory. Thermo. and Facility Characteristics Page 8 j
QUESTION (A.19) [1.0]
Which ONE of the following conditions would INCREASE the shutdown margin of a reactor?
a.
Inserting an experiment adding positive reactivity.
b.
Lowering moderator temperature if the moderator temperature coefficient is negative.
c.
Depletion of a burnable poison.
i d.
Depletion of uranium fuel.
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END OF SECTION A
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i Section B Normal Emeroency and Radioloaical Control Procedures Page 9 QUESTION (B.1) [1.0]
i Two sheets of % inch thick lead reduces a radiation beam from 200 mR/hr to 100 mR/hr, at one foot. What will be the radiation measurement at 1 foot if you add another (for a total of 3) %
inch lead sheet?
a.
71 mR/hr b.
50 mR/hr c.
35 mR/hr d.
17 mR/hr QUESTION (B.2) [1.0) in the process of saving someone's life you receive 6 Rem. How is this radiation dose tracked?
a.
Tracked by the facility as "occupationa Jose" b.
Tracked by the facility us a " planned special exposure" c.
Exempt from tracking per Emergency Plan d.-
Tracked by the NRC as a " planned special exposure" l
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7 Section 8 Normal. Emeraency and Radioloaical Control Procedures Page 10 -
QUESTION (8.3) [2.0,0.5 each)
Match the actions listed in column A with its appropriate technica! specification definition of Channel Check, Channel Test or Channel Calibration.
a.
Observe overlap between Nuclear Instrument channels.
b.
Replace resistance temperature detector with a precision resistance bridge to check i
proper temperature circuit operation.
l c.
Monitor Nuclear Instrumentation after shutdown verifying power decreases by a factor of 10 in three minutes.
d.
Based on a flux measurement using gold foils, adjust Nuclear Instrumentation.
QUESTION (B.4) [2.0,0.5 each)
Match the requirements associated with your individual licensed listed in column A with the correct frequency in column B.
Column A Column B a.
Requalification Written 6 years b.
Requalification Operating Test 4 years c.
Medical Examination 2 years d.
License Expiration 1 years t
QUESTION (B.5) [1.0)
Which ONE of the following is the 10 CFR 20 definition of TOTAL EFFECTIVE DOES EQUlVALENT (TEDE)?
a.
The sum of the deep does equivalent and the committed effective dose equivalent.
b.
The dose that your whole boay receives from sources outside the body, c.
The sum of the external deep dose and the organ dose.
d.
The dose to a specific organ or tissue resulting from an intake of radioactive material.
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Section B Normal. Emeraency and Radioloaical Control Procedures Page 11 QUESTION (B.6) [2.0,0.4 each]
Match the Technical Specifications experiment categories listed in column A with their respective maximum reactivity worths in column B. (Values from column B be may be used more than once, or not at all.)
Column A Column B a.
Single movable 1.
0.001 AK/K b.
Single unsecured 2.
0.002 AK/K c.
Single secured 3.
0.003 AK/K d.
Total moveable and unsecured 4.
0.004 AK/K e.
Total secured 5.
0.005 AK/K 6.
0.006 AK/K QUESTION (B.7) [2.0,0.5 each]
Match the general radiation area levels in column A with the conesponding 10 CFR 20 definitions listed in column B. (Items in column B may be used more than once or not at all.)
Column A Column B a.
1.5 mrem /hr 1.
Unrestricted Area b.
15 mrem /hr 2.
Radiation Area c.
210 mrem /hr 3.
900 mrem /hr 4.
Very High Radiation Area QUESTION (B.8) [1.0]
You are part of a team cleaning up an accident. You have received 1.3 Rem (whole body dose) so far this calendar year. You have no committed dose. Which one of the following is the longest you can work in the accident field of 4.7 Rem /hr, without exceeding your annual 10 CFR 20 TEDE limit? (Emergency Dose is NOT authorized.)
a.
47 minutes b.
1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> 3 minutes c.
1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> 16 minutes d.
1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> 20 minutes
Section B Normal. Emeraency and Radioloaical Control Procedures Page 12 QUESTION (B.9) [1.0]
Which ONE of the below is the lowest level of Purdue Reactor Staff who may authorize restart following a scram?
a.
Licensed Reactor Operator on the console.
b.
Licensed Senior Reactor Operator on Call.
c.
Reactor Supervisor.
d.
Facility Director QUESTION (B.10) (1.0)
An Emergency Action Levelis:
a condition which calls for immediate action, beyond the scope of normal operating a.
procedures, to avoid an accident or to mitigate the consequences of one.
b.
a class of accidents for which predetermined emergency measures should be taken or considered.
a procedure that details the implementation actions and methods required to achieve c.
the objectives of the emergency plan.
d.
a specific instrument reading or observation which may be used as a threshold for initiating appropriate emergency procedures.
i QUESTION (B.11) [1.0]
l Which ONE of the following is the maximum reading (at one foot) for which a sample holder may be removed from the pool?
(
a.
1 mR/hr l
b.
7% mR/hr c.
100 mR/hr l
d.
1 R/hr i
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Section B Normal. Emeroency and Radiolooical Control Procedures Page 13 QUESTION (B.12) [1.0)
Which ONE of the following conditions is a violation of a Technical Specification Limiting Condition of Operation?
a.
Primary coolant pH at 4.6 i
b.
Primary coolant resistivity at 400,000 ohm-cm.
c.
An experiment at 95*C d.
Pool water level at 12% feet above the core.
QUESTION (8.13) [1.0]
Which ONE of the following conditions is a REPORTABLE OCCURRENCE?
Dropping material into the shutdown core, with a reactivity worth of 0.4%AK/K.
a.
b.
A core excess reactivity of 0.5%AK/K.
An unexpected short-term reactivity change causing a period of 19 seconds c.
d.
Discovering the scram setpoint for the safety channel was set at 125% power.
QUESTION (B.14) [1.0]
Which ONE of the following Setbacks is not required by Technical Specifications?
a.
Linear Channel Low Level b.
Linear Channel High Level c.
Log Count Rate Low Level Period d.
Log N Channel High Level Period OUESTION (B.15) [1.0)
Which ONE of the following the scrams is NOT required by Technical Specifications?
a.
7% mR/hr on console monitor b.
7 second period on Log Count Rate Channel c.
Manual scram in hall d.
CSA Trouble i
"* END OF SECTION B "*
..._..__.__._____..._._m.._.___._--
Section C Plant and Radiation Monitorina Systems Page 14 QUESTION (C.1) [1.0)
Which ONE of the following correctly identifies the result of a loss of compensation to a Compensation lon chamber at low power levels?
a.
Unchanged b.
Higher than actual c.
Lower than actual I
d.
Higher or lower than actual depending on power level.
QUESTION (C.2) [2.0,0.5 each)
Match the Nuclear Instrumentation channels with their correct functions. (Protection refers to scrams and setbacks, while control relates to input to the automatic circuit for the servo control system.)
' Column A Column B a.
Startup Channel 1.
Setback and Slow Scram b.
Log-N Period Channel 2.
Setback and Fast Scram c.
Pool Top Radiation Area Monitor 3.
Slow Scram Only l
d.
Safety Channel 4.
None e.
Continuous Air Monitor QUESTION (C.3) [1.0}
i Which ONE of the following is the Neutron startup source used at Purdue?
a.
Pu-Be l
b.
Am-Be l
c.
Sb-Be d.
Ra-Be i
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Section C Plant and Radiation Monitorina Systems Page 15 QUESTION (C.4) [1.0]
Which ONE of the following components within the purification system is responsible for maintaining primary conductivity low?
a.
Heat exchanger b.
Cuno Filter c.
Freon compressor d.
Cartridge type Demineralizer QUESTION (C.5) [1.0]
Which ONE of the following is the method used to reduce mechanical shock to the shim-safety rods when scramming?
a.
Small spring located at bottom of rod.
b.
A Piston moves into a dashpot as the rod nears the bottom of travel.
c.
An electrical-mechanical brake energizes when the lower limit is reached.
d.
There is no method for absorbing mechanical shock.
QUESTION (C.6) (1.0]
l Which ONE of the following is the correct method used to determine fine control rod position l
indication? A ratiometer is connected to...
[
l a.
a series of limit switches located every 0.1 inch or rod travel l
I b.
a precision potentiometer mechanically connected to the drive unit.
c.
a series of limit switches located every 0.5 inch of rod travel.
d.
a precision coil electrically coupled to the rod.
QUESTION (C.7) [1.0]
Which ONE of the following elements is used as the neutron absorber in the Shim-Safety rods?
a.
Hafnium I
b.
Aluminum l
l c.
Borated Stainless Steel d.
1 l
Section C Plant and Radiation Monitorina Systems Page 16 QUESTION (C.8) [1.0]
An experimenter drops a sample while preparing to count it. He exits the room and closes the door. Which meter would you hold up to the closed door to determine the extent of the problem prior to entering to clean up the spill.
~
a.
Geiger Muller, to detect a radiation field b.
Geiger Muller, to detect radiation contamination c.
lon Chamber, to detect a radiation field d.
lon Chamber, to detect radiation contamination QUESTION (C.9) (1.0)
Which ONE of the following is the shim-safety rod speed?
a.
17.7 inch / minute b.
13.2 inch / minute c.
8.8 inch / minute d.
4.4 inch / minute QUESTION (C.10) [1.0)
Which ONE of the following is the correct method to be used to emergency shut down the reactor if the rods do not scram?
l f
a.
Remove Fuel assernbly H-2.
b.
Remove Reflector assembly H-1 l
j c.
Insert a cadmium bar into Isotope Production assembly H-6 d.
Dump boric acid into pool.
l
Section C Plant and Radiation Monitorino Systems Page 17 OUESTION (C.11) [1.0)
A visitor inadvertently hits the gang-lower switch. How may the operator stop the rods from inserting?
Reenergizing the Log Count Rate Channel.
a.
b.
Ranging UP on the Linear Level Channel.
Momentarily placing the Raise-Lower switch in either the raise or lower position.
c.
d.
Not required. Rod insertion will stop when the gang lower switch is released.
QUESTION (C.12) [1.0]
Which ONE of the following is the detector type used in the Radiation Area Monitors?
a.
Scintillation Detector b.
lon Chamber c.
Geiger Muller d.
Proportional Counter QUESTION (C.13) [1.0]
What is the purpose of the Startup channel drive mechanism?
a.
To maintain the instrument on-scale.
b.
To prevent burnout of the U23s coating on the detector during high power.
To maintain coupling between the fission chamber and the neutron source as they are c.
both withdrawn from the core.
d.
To prevent shorting out the preamplifier due to detector saturation.
i
Section C Flant and Radiation Monitorina Systems Page 18 QUESTION (C.14) [1.0]
Maximum design flow rate for the lon Exchanger (Demineralizer) is 20 gpm, but the design flow rate of the pump is 30 gallons per minute How is the system setup to prevent too much flow to the Demineralizer?
A pipe with an orifice bypasses some flow around the Demineralizer.
a.
b.
A throttle valve in the system is adjusted to supply proper flow, Cavitation due to inadequate Net Positive Suction Head (NPSH)is used to derate the c,
pump flow rate.
d.
Differential pressure across the cartridge type filters is kept high to reduce flow.
i QUESTION (C.15) [1.0]
Which ONE of the following is the name of the console light which indicates that the shim-safety rods are at the proper height for a critical experiment fuel movement (% out)?
a.
SHIM b.
SAFETY c.
TEST d.
SOURCE QUESTION (C.16) [1.0]
Which ONE of the following channels supplies input 'n the Regulating Rod SERVO system?
a.
Start-up Channel (1) b.
Log N & Period Channel (2) c.
Linear Power Channel (3) d.
Safety Channel (4)
Section C Plant and Radjat[on Monitorina Systems Page 19 QUESTION (C.17) [1.0)
Which ONE of the following conditions will NOT prohibit withdrawal of the shim-safety rods?
a.
Reactor period at 12 seconds.
b.
Linear channel reading 112% range.
Startup channel Count Rate at 1 cps.
c.
d.
Log Count Rate Selector in USE position.
"* END OF SECTION C *"
- "* END OF EXAMINATION "*"
L Section B Normal. Emeroency and Radioloaical Control Procedures Page 23
)
ANSWER (B.1) a i
REFERENCE (B.1)
A half-thickness is two sheets. I = la (%)" = 0.3535
- 200 mR/hr = 70.71 mR/hr ANSWER (B.2) b REFERENCE (B.2) 10 CFR 20.1206 ANSWER (B.3) a, check; b, test; c, check; d, cal REFERENCE (B.3)
Technical Specifications 61.0 Definitions l
ANSWER (B.4) a,3; b,4; c,3; d, i REFERENCE (B.4) 10 CFR 55 99 21,55, & 59 (2) l ANSWER (B.5) a REFERENCE (8.5) l 10 CFR 20.1003, Definitions ANSWER (B.6) a,3; b,3; c,4; d,3; e,6 REFERENCE (B.6)
Technical Specifications 9 0.1 Reactivity Limits ANSWER (B.7) a,1; b,2; c,3; d,4 REFERENCE (8.7) 10 CFR 20.1003, Definitions ANSWER (B.8) a REFERENCE (B.8)
First calculate can get: 5 - 1.3 = 3.7 Rem.
Time = Can get + rate: (3.7 Rem)/(4 7 Rem /hr) x 60 = 47.2 min ANSWER (B.9)'
l a
REFERENCE (B.9)
. Emergency Procedure located behind the Emergency Plan. Also pp.13 - 15 in PUR-1 Operating Manual (1965). NOTE: This violates 10 CFR 50.54.m(1)
I
Section A R Theorv. Thermo. and Facility Characteriglips Page 20 ANSWER (A.1) d REFERENCE (A.1)
Glasstone, S. And Sesonske, A NuclearReactorEnglneering, Kreiger Publishing, Malabar, Florida,1991, S 3.154, p.188 ANOWER (A.2) Question Deleted, b
REFERENCE (A.2)
O!;;;;' enc, O. And 0;;;n;k;, A. Nucl:ce Occclcr Enginccring, Krclgcr Pub'!;hing, '.';';b;r, I;;r d;,1001, S 5.0, p. 231 ANSWER (A.3) c REFERENCE (A.3)
Glasstone, S. And Sesonske, A, NuclearReactor Engineering, Kreiger Publishing, Malabar, Florida,1991, SS 2.108 - 2.1.114, pp. 77 - 80 ANSWER (A.4) 1 d
REFERENCE (A.4)
Glasstone, S. And Sesonske, A, Nuclear Reactor Engineering, Kreiger Publishing, Malabar, Florida, 1991, $@ 1.50 - 1.55, Table 1.2, pp.16,17 ANSWER (A.5) a REFERENCE (A.5)
Glasstone, S. And Sesonske, A, Nuclear ReactorEngineering, Kreiger Publishing, Malabar, Florida,1991, SS 3.81 - 3.85, Table 3.3, pp.164,165 ANSWER (A.6) c REFERENCE (A.6)
Glasstone, S. And Sesonske, A, Nuclear Reactor Engineering, Kreiger Publishing, Malabar, Florida, 1991, @ 2.183, p.107 ANSWER (A.7) c REFERENCE (A.7)
Burn, R., Introduction to Nuclear Reactor Operations, @ 1988, S 6.2.2, pp. 6-2 & 6-3.
ANSWER (A.8) d REFERENCE (A.8)
Burn, R., Introduction to Nuclear Reactor Operations, C 1988, 5 5.2, p. 5-1.
pm
__s
Sartion A R Theory. Thermo. and Facility Characteristics Page 21 ANSWER (A.9) b REFERENCE (A.9)
Reactivity (p) = -0.015AK/K K, = 1/(1 - p) = 1/[1-(-0.015)] = 1/1.015 = 0.9852 CR,/CR = (1 - Kw2)/(1 - K,,)
1 - Ke2 = [CR, (1 - K,,)]/CR Ker = 1 - [CR,(1 - K,i)/CR }
2 2
2 Kw2 = 1 -[15/60(1 - 0.9852) = 1 - (1 - 0.9852)/4 = 1 - 0.01478/4 = 1 - 0.003695 = 0.9963-Worth = (K,, - Km2)/K,,K,2 = (0.9963 - 0.9852)/(0.9852 x 0.9963) = +0.0113 AK/K ANSWER (A.10) c REFERENCE (A.10)
Burn, R., Introduction to Nuclear Reactor Operations, @ 1988, Chapt. 5 9 5.3, pp. 5 5-13.
'.11)
ANSWER d
REFERENCE (A.11)
Burn, R., IntIUduction to Muclear Reactor Operations, @ 1988, 9 3.2.4, p. 3-12.
ANSWER (A.12) c REFERENCE (A.12)
Glasstone, S. And Sesonske, A, Nuclear Reactor Engineering, Kreiger Publishing, Malabar, Florida,1991, g 5.45, p. 246 P=Po e" 100 (e '") = 10.54 ANSWER (A.13) b REFERENCE (A.13)
Glasstene, S. And Sesonske, A, Nuclear Reactor Engineering, Kreiger Publishing, Malabar, Florida, 1991,9 3157, p.189 ANSWER (A.14) c REFERENCE (A.14)
- Glasstone, S. And Sesonske, A, Nuclear Reactor Engineering, Kreiger Publishing, Malabar, Florida, 1991, 9 5.9, p. 321 ANSWER (A.15) l l
b REFERENCE (A.15)
Reactivity (p) = (K, - 1)/K, = 0.1765 = -17.65% AK/K.
-17.65% AK/K + 16.0% AK/K = -1,65% AK/K Final K, = 1/(1 - p) = 1/[1 - (-0.0165)] = 0.9838
Section A R Theorv. Thermo. and Facility Characteristics Page 22 ANSWER (A.16) l a
i REFERENCE (A.16)
Glasstone, S. And Sesonske, A, NuclearReactor Engineering, Kreiger Publishing, Malabar, Florida, 1991, 9 5.18, p. 234 ANSWER (A.17) Answer changed per facility comment.
ac REFERENCE (A.17) l A 9'F HEATUP, will add 9'F x -0.0005 AK/K/*F = -0.0045 AK/K. To compensate, the I
regulating rod must add 0.0045 positive reactivity, which implies move out.
+0.0045 AK/K + 0.001 AK/K/ inch = 4.5 inches ANSWER (A.18) c REFERENCE (A.18) 100 10 = 70 neutrons are absorbed in the core (fuel, clad, etc.). Since the reactor is critical the number of fission = 100 neutrons + 2.5 neutrons / fission = 40 fissions. Since 85% of neutrons absorbed in the U235 result in a fission, there were 40 fissions /0.85 fissions / neutrons absorbed by fuel = 47 neutrons. The thermal utilization = 47/70 =.0.67.
. Glasstone, S. And Sesonske, A, NuclearReactor Engineering, Kreiger Publishing, Malabar, Florida, 1991,9 2.156, p.189 ANSWER (A.19)
. d REFERENCE (A.19)
Burn, R., Introduction to Nuclear Reactor Operations, @ 1988, 9 6.2.3, p. 6-4.
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- END OF SECTION A
- I i!.
Section B Normal. Emeraency and Radioloaical Control Procedures Page 23 ANSWER-(B.1) l t
a i
REFERENCE (B.1)
A half-thickness is two sheets. I = lo (%)" = 0.3535
- 200 mR/hr = 70.71 mR/hr ANSWER (B.2) b REFERENCE (B.2) 10 CFR 20.1206 ANSWER (B.3) a, check; b, test; c, check; d, cal REFERENCE (B.3)
Technical Specifications S 1.0 Definitions ANSWER (B.4) a,2; b,1; c, ?; d,6 REFERENCE (8.4) 10 CFR 55 99 21,55, & 59 (2) l ANSWER (B.5) i a
REFERENCE (B.5) 10 CFR 20.1003, Definitions ANSWER (B.6) a,3; b,3; c,4; d,3; e,6 REFERENCE (B.6) i Technical Specifications @ 3.1 Reactivity Limits l
l ANSWER (B.7) i a,1; b,2; c,3; d,4 REFERENCE (B.7) 10 CFR 20.1003, Definitions ANSWER (B.8) a i
REFERENCE (B.8)
First calculate can get: 5 - 1.3 = 3.7 Rem.
Time = Can get + rate: (3.7 Rem)/(4.7 Rem /hr) x 60 = 47.2 min l
ANSWER (B.9) l a
REFERENCE (B.9)
Emergency Procedure located behind the Emergency Plan. Also pp.13 - 15 in PUR-1 Operating Manual (1965). NOTE: This violates 10 CFR 50.54.m(1) v l
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f
('
\\
l Sechon B Normal. Emeroency and Radiolooical Control Procedm.e1 Page 24 l
ANSWER (B.10) a I
REFERENCE (B.10)
Emergency Plan, S 2.0 Definitions ANSWER (B.11) i d
REFERENCE (B.11)
PUR procedure 91-2 Sample Irradiation, procedure steps 2 and 7.
{
ANSWER (8.12) d REFERENCE (B.12)
Technical Specifications $$ 3.3 and 3.5 ANSWER (B.13) d REFERENCE (B.13)
)
Technical Specifications S 3.2 & 1.27 l
ANSWER (B.14) a REFERENCE (B.14)
PUR-1 Procedure M-1 Procedure for Checking Meter-Contact Switches, Channel 3 and i
Technical Specifications Table 1.
ANSWER (B.15) d REFERENCE (B.15)
Technical Specifications Table i Safety Channels Required for Operation, also 12/80 i
Requalification Examination Question E.1 l
1 I
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"* END OF SECTION B ~
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. ~,,
. - ~ _
Section C Plant and Radiation Monitorina System 1 Page 25 t
ANSWER (C.1) b REFERENCE (C.1)
NRC administered examination August 1992.
ANSWER (C.2) a,1; b,2; c,3; d,2; e,4 REFERENCE (C.2)
Instrumentation Block Diagram ANSWER (C3) a REFERENCE (C.3)
Old Requal Exam administered December,1977 ANSWER (C.4) d REFERENCE (C.4)
PUR-1 Operating Reactor, Lockheed Nuclear Products, $ 1.6 Process System ANSWER (C.5) b REFERENCE (C.6)
Supplied drawing for Shim-Safety Rod.
ANSWER (C.6) b REFERENCE (C.6)
PUR-1 Operations Manual 1962, Lockheed Nuclear Products,91.5.6.6 ANSWER (C.7) c REFERENCE (C.7)
PUR-1 Operating Manual, Lockheed Nuclear Products, @ 1.1, General Specifications ANSWER (C.8) c REFERENCE (C.8)
Standard NRC question ANSWER (C.9) l d
REFERENCE (C.9) i PUR-1 Operations Manual,1962, Lockheed Nuclear Products, @ 1.1 General Specifications l
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1 Section C Plant and Radiation Monitorino Systems Page 26 ANSWER (C.10) d REFERENCE (C.10)
Old Requalification question 1297, question E.2 ANSWER (C.11) c REFERENCE (C.11)
PUR-1 Operating Manual 1962, Lockheed Nuclear Products, $ 1.5.6.5.
ANSWER (C.12) a REFERENCE (C.12)
PUR-1 Operating Procedure M-5, Procedure forRadiation Area Monitor, figure 1 l
ANSWER (C.13)
I a
j REFERENCE (C.13) i l
PUR-1 Operation Manual 1962, Lockheed Nuclear Products, 1.5.6.3 Fission Chamber Dn've j
System l
l ANSWER (C.14) i b
REFERENCE (C.14) l PUR-1 Operations Manual 1962, Lockheed Nuclear Products, S 1.6 Process System ANSWER (C.15) a REFERENCE (C.15)
PUR-1 Operations Manual 1962, 61.5.6.1, Shim Safety Rod Drive System ANSWER (C.16) c REFERENCE (C.16) j Supplied drawings I'
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- ANSWER (C.17) d REFERENCE (C.17)
PURDUE Requalification Examination 1268, question E.2.
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"* END OF SECTION C "*
1
- END OF EXAMINATION "*"
4 4
P U. S. NUCLEAR REGULATORY COMMISSION NON-POWER REACTOR LICENSE EXAMINATION FACILITY:
Purdue University REACTOR TYPE:
Pool DATE ADMINISTERED:
1997/06/01 REGION:
3 CANDIDATE:
INSTRUCTIONS TO CANDIDATE:
Answers are to be written on the answer sheet provided. Attach the answer sheets to the I
examination. Points for each question are indicated in paren-theses for each question. A 70%
overall 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 CATEGORY 20.00 35.1 A.
REACTOR THEORY, THERMODYNAMICS AND i
FACILITY OPERATING CHARACTERISTICS 19.00 33.3 B.
NORMAL AND EMERGENCY OPERATING PROCEDURES AND RADIOLOGICAL CONTROLS 18.00 31.6 C.
PLANT AND RADIATION MONITORING SYSTEMS t
57.00 TOTALS FINA8. GRADE All work done on this examination is my own. I have neither given nor received aid.
4 Candidate's Signature
NRC RULES AND GUIDELINES FOR LICENSE EXAMINATIONS During the administration of this examination the following rules apply:
1.
j Cheating on the examination means an automatic denial of your ap%ication 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 nct received or given
' assistance in completing the examination. This must be done after you complete the examination.
l 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 i
appearance or possibility of cheating.
l i
i 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
-l cover sheet.
1 6.
Fillin the date on the cover sheet of the examination (if necessary).
7.
Print your name in the upper right-hand corner of the first page of each section of your answer sheets.
j 8.
~ Before you turn in your examination, consecutively number each answer sheet, I
including any additional pages inserted when writing your answers on the examination question page.
l j
9.
The point value for each question is indicated in parentheses after the question.
10.
Partial credit will NOT be given.
11.
If the intent of a question is unclear, ask questions of the examiner only.
12.
When you are done and have turned in your examination, leave the examination area as J
defined by the examiner. If you are found in this area while the examination is still in progress, your license may be denied or revoked.
J i
v.
EQUATION SHEET i
d = the, AT = is AH = UA AT p'"**, (p - D)2 2cx(k)f t' = 1 x 10~* seconds SCR =
1 -K,,
CR (1 -K,,,) = CR,(1 -K,,,)
A,, = 0.1 seconds -1 3
SUR = 26.06l,,p]
1 -K,"*
A M=
S-P i -K,,,
8N 1
CR P = P,10 i
M=
=
1-K,,
CR, SDM = (1 -K,y) pa pe T
c g.,
i T=
P = OI1'E) P, f
f p-p D-P l
K,,, - K,,,
T = g< + [f-p]
Ap =
k,, x K,,,
P A,ep l
P T* = 0.693 (K,y-1)
P A
gou DR =DR, e
DR,d, = DR d,'
h a
DR - Rem, Ci-curies DR = SCIE (n)
E - Mev, R - feet j
g2 (P -D)", (P -D)*
2 i
- Peak, Peak, P
1 Curie = 3.7 x 10' dis /sec 1 kg = 2.21 lbm 1 Horsepower = 2.54 x 108 BTU /hr 1 Mw = 3.41 x 10' BTU /hr l
1 BTU = 778 ft-Ibf
'F = 9/5 *C + 32 1 gal (H O) = 8 lbm
- C = 5/9 (*F - 32) 2 cp = 1.0 BTU /hr/lbm/*F c, = 1 cal /sec/gm/*C i
l Section A R Theory. Thermo & Farm. Ooeratina Characteristics Pags 1 v
ANSWER SHEET l
A.1 abcd A.11 a b c d l
A.2 abcd A.12 a b c d A.3 abcd A.13 a b c d L
i A.4 abcd A.14 a b c d l
A.5 abcd A.15 a b c d 4
'l A.6 abcd A.16 a b c d 1
A.7 abcd A.17 a b c d A.8 abcd A.18 a b c d A.9 abcd A.19 a b c d i
A.10 a b c d I
7-.
Sechon B Normal /Emeroency. Procedures & Rad Con Pega 2 ANSWER SHEET B.1 a b c d B.6d 1 2 3 4.5 6 B.2 a b c ' d B.6e 123456 B.3a check cal test B.7a 1234 B.3b check cal test.
B.7b 1234 B.3c check cal test B.7c 1234 B.3d ~ check cal test B.7d 1234 Years B.4a 6 4 2 1 B.8 abcd Years B.4b 6 4 2 1 B.9 abcd-Years B.4c 6 4 2 1 B.10 a b c d Years B.4d 6 4 2 1 B.11 abcd B.5 abcd B.12 a b c-d __
B.6a 1 2 3-4 5 6 B.13 a b c d B.6b 123456 B.14 a b c d B.6c 123456 B.15 & b c d
l Sechon C Plant and Rad Monitorina Systems P ge 3 l
l l
ANSWER SHEET l
l C.1 abcd C.8 abcd l
l l
r C.2a.1 2 3 4 C.9 abcd i
e C.2b 1 2 ' 3 4 C.10 a b c d l
C.2c 1 2 3 4 C.11 a b c d I
C.2d a b c d C.12 a b c d l
C.3 abcd C.13 a b c d i
l C.4 abcd C.14 a b c d h
C.5 abcd C.15 a b c d C.6 abcd C.16 a b c d l
t C.7.abcd C.17 a b c d I
I s
t t
l l
l
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