ML20198P292
| ML20198P292 | |
| Person / Time | |
|---|---|
| Site: | University of Lowell |
| Issue date: | 11/27/1998 |
| From: | Doyle P NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20198P272 | List: |
| References | |
| 50-223-OL-98-03, 50-223-OL-98-3, NUDOCS 9901070022 | |
| Download: ML20198P292 (38) | |
Text
__
4 U S. NUCLEAR REGULATORY COMMISSION OPERATOR LICENSING INITIAL EXAMINATION REPORT REPORT NO.:
50-223/OL-98-03 FACILITY DOCKET NO.:
50-223 FACILITY LICENSE NO.:
R 125 FACILITY:
University of Massachusetts - Lowell EXAMINATION DATES:
November 16 - 19 1998 SUBMITTED BY:
/42778 Paul Doyle, ChiefJikram Date
SUMMARY
During the week of November 16,1998, the NRC administered examinations to six license candidates. The license candidates were 1 Senior Reactor Operator Upgrade,4 initial Reactor Operators and 1 Reactor Operator retaking Sections B and C of the written examination. One of the initial reactor operator candidates failed sections A and B of the written examination.
REPORT DETAILS 1.
Examiners:
Paul Doyle, Chief Examiner 2.
Results:
RO PASS / Fall SRO PASS / Fall TOTAL PASS / Fall Written 4/1 0/0 4/1
_ '.C.ating Tests 4/0 1/0 5/0 Overall 4/1 1/0 5/1 3.
Exit Meeting:
Paul Doyle, NRC, Examiner Leo Bobek, U. Mass-Lowell, Reactor Supervisor During the exit meeting, Mssrs. Doyle and Bobek discussed preliminary comments on the written examination. Mr. Doyle noted that he noted no generic weaknesses on the part of the license candidates, during the operating tests and thanked Mr. Bobek for his and his staffs support in the administration of the examinations.
ENCLOSURE 1 9901070022 981200 PDR ADOCK 05000223 V
PDR l
L I
l Facility Comments and NRC Resolution ENCLOSURE 2 I
r i
NOV-23-1998 14:04 FROM U.Lowell, Rad. Lab.
TO 13014153313 P.01 Leo Bobek University ofMassachusetts Low:ll Reactor Supervisor One Universtty Avenue Pinanski Hall 107A Lowell, Massachusetts 01834 tel. 978-934 3363 Jat 978-439 636i LOWett RADIATION LABORATORY November 23,1998 Mr. Paul Doyle USNRC washington, D.C. 20555
, Mail Stop 0-11-B-20
Dear Mr. Doyle:
Allow me to express my sincere appreciation for your efforts in providing an cperator licensing exam this past week at the University of Massachusetts Lowell Research Reactor. We appreciate your professionalism in providing and performing both a thorough and fair examination.
As discussed in our exit interview, we are submitting comments for three questions on the written examination.
For question A.5, answer 'B' is the correct answer.
For question B.4, both answers 'A' and 'C' are correct. In Standing Order #10, Part 3.0, the gamma cave alarm set point may be adjusted both due to the decay of Co-60 and if the source used is not of sufficient strength to trip the alarm.
For question B.15, answer 'A' in addition to answer 'C' may be considered corTect. Special Procedure 21 " Movement of Objects by Crane," does not specifically preclude a.ny lead from being transported over the stall pool. It does, however, specifically state that shinoinn casks within the rated load of the crane shall not be transported over the stall pool. The procedure goes on to state that extreme care should be taken when moving any object over the reactor pool and that, in general, heavy objects such as shipping casks should not be transported our the core. In practice, we do occasionally lift relatively light loads over the stall pool, for example the drive mechanisms wher. they are in need of repair.
Again, thank you for your efforts. If you require additional information, please let me know.
Sincerely,
'/
Leo 1. Bobek, Reactor Supervisor TOTAL P.01
1 l
i All facility comments accepted as written.
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Section A R Theorv. Thermo. and Facility Characteristics Pags 2 QUESTION (A.1)
Using the data taken during a core loading fuel (Table A.1, provided), estimate the number of fuel elements needed to go critical.
a.
9 b.
11 c.
13 d.
15 QUESTION
( A.'2)
The two figures below represent the order (number in box) and direction used in placing fuel into a reactor pool. Which of the following choices shows the preferred method for performing a 1/M plot, along with the correct reason.
O O,.,,,
DETECTOR DETECTOR CORI O_RC.
o_,,,
Figure 1 Figure 2 a.
Figure 1 because loading from the detector towards the source gives the first fuel element more emphasis resulting in a more conservative estimate of criticality.
b.
Figure 2 because loading towards the detector and the source gives the first fuel element more emphasis resulting in a more conservative estimate of criticality.
c.
Figure 1 because loading from the detector towards the source gives the last fuel element more emphasis resulting in a more conservative estimate of criticality.
i..
d.
Figure 2 because loading towards the detector and the source is gives the last fuel element more ernohasis resulting in a more conservative estimate of criticality, i
i t
I l-
l Section A R Theorv. Thermo. and Facility Characteristics Page 3 QUESTION (A.3) l Two reactors A and B, have identical fuel loading, rod worths and initial starting reactivities. The only difference between the reactors is that Reactor A has a rod speed of 30 inches /rninuto and Reactor B has l
a rod speed of 20 inches / minute. The reactors are started up simultaneously, with both reactors reading 10 counts /second at the start. Which of the following describes how the two reactors will relate when I
taken critical based on the stated conditions?
Reactor A and Reactor B will be critical at the same power level with Reactor A at a higher rod a.
height.
l b.
Reactor A rod height is higher than Reactor B with Reactor B power higher than Reactor A.
Reactor A and Reactor B will be critical at the same rod height with Reactor B at a higher power level, c.
d.
Reactor B rod height is higher than Reactor A with Reactor A power higher than Reactor B.
QUESTION (A.4)
As primary coolant (moderator) temperature increases, control rod worth...
a.
decreases due to lower reflector efficiency.
b.
decreases due to higher neutron absorption in the moderator, c.
increases due to the increase in thermal diffusion length.
d.
remains the same due to constant poison cross section of the control rods.
QUESTION (A.5)
The Chief Reactor Operator tells you that the reactor is shutdown with a Shutdown Margin of 12.0%.
Nuclear instrumentation reads 100 cpm. The CRO inserts an experiment into the core and counts increase to 200 cpm. What is the resulting K,n for the core?
a.
0.920
- b. 0.946 c.
0.973 d.
1.000 QUESTION (A.6)
Which ONE of the following is an example of alpha (a) decay?
3.Br" 33Br" a.
- b. 3.Br" 33Br
c.
3.Br" 3,Se
- d. 3.Br" 3 Kr" i
I t
Section A R Theory, Thermo, and Facility Characteristics Page 4 QUESTION (A.7) l During a startup you increase reactor power from 50 watts to 1000 watts in 100 rieconds. What is reactor period?
a.
25 b.
33 c.
41 d.
50 QUESTION (A.8)
The reactor is operating with the Regulating Rod in Automatic mode. The Reactor Operator starts the secondary pump and both cooling tower fans. Average coolant temperature in the core decreases from 28'C to 20*C. Assume Regulating rod worth over the range of travel for this problem is 0.03%
AK/K/ inch, and average temperature coefficient over this temperature range is -0.88 x 10 tK/K/*C.
How far, and in which direction will the regulating rod move to maintain constant power?
a 2.35 inches, inward b.
2.35 inches, outward c.
2.73 inches, inward d.
2.73 inches, outward QUESTION (A 9)
Which ONE of the following statements concerning reactor poisons is NOT true?
a.
Following shutdown, Samarium concentration will increase to some value then stabilize.
b.
Following shutdown, Xenon concentration willinitially increase to some value then decrease exponentially.
c.
During reactor operation, Samarium concentration is independent of reactor power level.
d.
During reactor operation, Xenon concentration is dependent on reactor power level.
QUESTION (A.10)
An experimenter makes an error loading a rabbit sample, injecting the sample into the core results in a 100 millisecond period. If the first scram trip setpoint (actual) is 125%, and the scram delay time is 0.1 seconds, which ONE of the following is the resulting peak reactor power before the reactor shuts down?
a.
1.4 Megawatts
- b. ' 2.8 Megawatts c.
3.4 Megawatts d.
5.0 Megawatts l
Section A R Theorv. Thermo. and Facility Characteristics Page 5 QUESTION (A.11)
In a reactor the thermal neutron flux (0) is 2.5 x 10'8 fissions /cm /second, and the macroscopic cross.
2 section (I,) for fission is 0.1 cm. The fission rate is a.
2.5 x 10" fissions /cm/second
- b. 2.5 x 10'8 fissions /cm/second c,. 2.5 x 10" fissions /cm /second 8
8.
d.
2.5 x 10'8 fissions /cm /second 1
QUESTION - (A.12)
When compared to Q; D.,, is...
a.
smaller, because delayed neutror's are born at lower energies than prompt neutrons.
- b.
larger, because delayed neutrons are born at lower energies than prompt neutrons.
c.
smaller, because delayed neutrons are born at higher energies than prompt neutrons.
d.
larger, because delayed neutrons are born at higher energies than prompt neutrons.
QUESTION (A.13)
Each fission event releases approximately 200 Mev of energy. Which ONE of the following contributors to this energy is largest?
a.
Energy transferred due to resonance absorption of neutrons.
b.
Energy transferred due to thermalization of neutrons.
c.
Energy transferred due to slowing down of fission fragments.
d.
Energy transferred due to absorption of fission gammas.
QUESTION ' (A.14)
A fissile materialis one which will fission upon absorption of a M neutron. A fertile material is one which upon absorption of a neutron becomes a fissile material. Which ONE of the following isotopes is an example of a fertile material, s.
Utsa
- b. utss U se.
t c.
' d. ' pusse l-1 '
n 1
l '
l
=.
- - =... - -
i Section A R Theorv. Thermo, and Facility Characteristics Page 6 l
QUESTION (A.15)
Which one of the graphs supplied in figure A.1, most closely depicts the reactivity versus time plot for xenon for the following set of evolutions?
TIME Evolution l
1 Startup to 100% power, clean core l
2 100% operation for four days l
3 Sht.tdown for 15 hours1.736111e-4 days <br />0.00417 hours <br />2.480159e-5 weeks <br />5.7075e-6 months <br />
(
4 50% operation for 29 hours3.356481e-4 days <br />0.00806 hours <br />4.794974e-5 weeks <br />1.10345e-5 months <br /> a.
a
- b. b
- c. c d.
d QUESTION (A.16)
Five minutes after shutting down the reactor, reactor period is 3 x 10' counts per minute. Which ONE of the following is the count rate you would expect to three minutes later?
a.
10' cpm 5
b.
8 x 10 cpm 5
c.
5 x 10 cpm 5
d.
3 x 10 cpm OUESTION (A.17)
Excess reactivity is the amount of reactivity...
a.
associated with b.
needed to achieve prompt criticality c.
available below that which is required to make the reactor suberitical.
d.
available above that which is required to keep the reactor critical.
QUESTION (A.18)
Which ONE of the following statements correctly describes how delayed neutrons allow for safe control of the reactor?
a.
More delayed neutrons are produced than prompt neutrons resulting in a longer time to reach a stable subcritical count rate, b.
Delayed neutrons are born at higher energies than prompt neutrons, resulting in a shorter reactor period from increased leakage.
c.' Delayed neutrons take longer to thermalize than prompt neutrons, resulting in a longer reactor period.
d.
Delayed neutrons increase the average neutron lifetime, resulting in a longer reactor period.
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l-Section A R Theorv. Thermo, and Facility Characteristics Pags 7 l
i 1
i.
QUESTION (A.19) i The primary reason a neutron source is installed in the reactor is to...
a.
allow for testing and irradiation of experiments when the core is shutdown.
i b.
supply the neutrons required to start the chain reaction for subsequent reactor startups.
c.
provide a neutron level high enough to be monitored for a controlled reactor startup, j
)
d.
Increase the excess reactivity of the reactor which reduces the frequency for refueling.
1 QUESTION (A.20)
With the reactor on a CONSTANT positive period, which ONE of the following power changes would take the LONGt!ST time?
a.
5%, from 95% to 100%
b.
10%, from 80% to 90%
c.
15%, from 15% to 30%
d.
20%, from 60% to 80%
.. _.. ~. -
Section B Normal. Emeroencv and Radioloaical Control Procedures PaA 8 l-i:
OUESTION (B.1) [1.0]
Which ONE of the following is the maximum number of fuel elements which may be out of the mechanically enforced planar geometry at any one time, when transporting fuel from the shipping l
' container to the reactor?
a.
One
. b.
Two c.
Four i
d.
Nine.
I
. QUESTION
-(B.2) [1.01 IRRADIATED FUEL is any fuel element or partial element that emits sufficient radiation capable of
' del:vering a whole body dose equivalent rate greater than or equal to...
- a. -10 mrem /hr at 1 foot b.
100 mrem /hr at 1 foot c.
10 mrem /hr at 1 meter d.
100 mrem /hr at 1 meter QUESTION (B.3) -[1.0]
What is the maximum K,, allowed (per Technical Specifications) for reactor fuel element storage under quiescent flooding with water, a.
0.7
- b. 0.75 c.
0.8
- d.
0.85 QUESTION (B.4) [1.0)
Which ONE of the following describes the reason why it is necessary to review and reset the Gamma Cave alarm setpoints in accordance with Standing Order #10?
- a.
The decay of the Co-60 source,
- b. ;The position of the core relative to the detector.
- c. ' The rack used having sufficient level to reach setpoints.
l
- d. The expected maximum power ' level for the next operating period.
I i
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f
.- -.. -.-- ~..._ _ -... -.. - -_ - -
Section B Normal. Emeroenev and Radioloalcal Control Procedures Page 9 QUESTION (B.5) [1.0]
Which ONE of the following coriditions regarding experiments is not allowed under ANX condition? The experiment...
- a.. contains cryogenic liquids.
- b. ' contains 2.1 milligrams of explosive material
)
i
- c. causes a reduction in the reading for the_ startup channel.
- d. causes the outside temperature of a submerged material to reach 90*C (176'F)
QUESTION _ (B.6) [1.0]
Technical Specification 4.4 Specification 7, requires a measurement of air flow in the stack exhaust te be 1
measured every two years if the measurement was last performed on January 31,1997, then it must be performed no later than...
. a.
January 31,1999
- b. April 30,1999 i-c.
July 31,1999
- d. January 31,2000 QUESTION (B.7) [1.0]
Limiting Conditions for Operation (LCOs) are...
limits on very important variables that are found to be necessary to reasonably protect the integrity of a.
certain physical barriers which guard against the uncontrolled release of radioactivity.
b.
settings for automatic protective devices related to those variables having significant safety functions.
e c.
combinations of sensors, interconnecting cables or lines, amplifiers and output devices which are -
connected for the purpose of measuring the value of a variable.
d.
the lowest functional capability or performance levels of equipment' required for safe operation of the facility.
QUESTION - (B.8) [2.0,0.5 each]
Identify each of the conditions listed below as a Channel Check (CC), Channel Test (CT) or a Channel
= Calibration (CAL) a.
Comparing period on the startup channel with period on the Log-N channel.
b.
Holding a source next to a portable radiation detector and noting meter movement.
- c. ' Holding a calibrated source next to a portable radiation detector and noting a specific reading.
d.
Dipping a temperature probe in an ice bucket then adjusting the channel to correct the reading.
- n,-
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y
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m Section B Normal. Emeraency and Radiolooical Control Procedures Pags 10 l
OUESTION (B.9) [1.O]
You bring a radiation monitor into the pump room during reactor operation. ' If you were to open the window on the detector you would expect the meter reading to...
l-(Assume no piping leaks) 1 a.
increase, because you would now be receiving signal due to H and O betas, 8
b.
remain the same, because the Quality Factors for gamma and beta radiation are the same.
c.
increase, because the Quality Factor for betas is greater than for gammas.
d.
remain the same, because you still would not be detecting beta radiation.
OUESTION (B.10) {1.0)
Which ONE of the following is the maximum reactivity of a rabbit sample which may be inserted by someone who does NOT have an operator (RO or SRO) license?
a.
0.01 % Ak/k
- b. 0.02 % Ak/k c.
0.10 % Ak/k d.
0.20 % Ak/k QUESTION (B.11) 12.0, 0.5 each]
Identify the modes [ Forced Convection (above 0.1 Mw) (FC), Natural Convection (NC), Cross Pool flow pattern (CP) or Down-Comer flow pattern (DC), or all modes (ALL)] for which each of the following scrams is required to be operational. (Modes may be used more than once or not at all.)
a.
Pool level 2'3" above centerline of core, b.
Either Coolant Riser Gate or Downcomer Gate opens c.
Coolant Inlet Temperature 108'F d.
Manual Scram button QUESTION (B.12) [1.01 According to the Safety Analysis Report (SAR), which ONE of the following locations has the potential of generating the greatest amount of Ar"?
a.
Thermal Column Case Vent b.= Beam Port c.
Pneumatic Tube l
l d.
Primary Coolant (Pool)
L l
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l Section B Normal. Emeroency and Radioloaical Control Procedures Pzgn 11
(
OUESTION (B.13) 11.0]
You are the console operator during insertion of a sample into and later removal of a sample from the l
core. Which ONE of the following items are you MQI required to log in the console operator's log?
a.
Sample Number
- b. Time In/Out l
- c.
Exposure
- d. Total Reactivity worth of allincore samples l
QUESTION (B.14) [1.0)
While working on an experiment your extremities (hands) received the following doses: 100 mrem (Q),
25 mrem (y) and 5 mrem neutrons (unknown energy). What is your total dose?
a.
175 mrem b.
155 mrem c.
145 mrem d.
130 mrem QUESTION (B.15) [1.0)
Which ONE of the followhg statements conceming crane operations is NOT true?
a.
Loads may NOT be lifted over the stall pool, b.
Fuel shipping casks may be lowered into the bulk pool provided the gate is in place iri the stall pool.
c.
Loads must be attached directly to the load block hook without the use of slings.
d.
Side pulls (dragging) is not allowed.
QUESTION (B.16) [1.0)
Which ONE of the following is the minimum number of hours you must stand watch per quarter to maintain your license active?
a.
'l b.
4 c.
8 d.
12 r
l
_m_.
i 1
i Section' B' Normal. Emeroenev and Radioloolcal Control Procedures Paga 12 l..
QUESTION...(B.17) [1.01 l,
A'new experiment generates radioactive source which emits'a 1.5 MeV gamma. The mass attenuation coefficient for 1.5 MeV gammas for lead is 0.051 cm / gram and the density of lead is 11.4 gram /cm'.
2 The thickness of the lead sheets is 1 cm. The facility director tells you to buy a lead pig for shipping the p
source which will reduce the dose rate by a factor of 10. The lead pigs are manufactured in 1 cm increments of thickness and are expensive. Which ONE of the following is the minimum thickness lead j
pig required?
a.
1 cm,
b.
2cm' I
l c.
4 cm.
- )
..d.
8cm 1
QUESTION 18.18)[1.0)
)
According to EO 7 Stuck Rod of Safety B/ede, which ONE of the following is the console operator's
' primary responsibility?
- l
' a; Maintain power level constant.
. b.' -To unstick the stuck rod, j
i
- c. -To run the unstuck blades and regulating rod in.
- d. To determine the cause of the stuck rod.
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I' Section C Facility and Radiation Monitorina Svstems Paga 13 QUESTION ' (C.1 ) [1.0)
Using the drawing of the primary system provided (Figure C.1), for a normal full power lineup, the primary takes a suction from the and returns to the a.
bulk pool, stall pool b.
bulk pool, bulk pool c.
stall pool, bulk pool d.
stall pool, stall pool.
QUESTION (C.2 ) [2.0, 0.5 eachl Match the Major Ventilation System Components listed below with the correct symbol @ through @ from figure C.2 provided, a.
Emergency Exhaust Fan
- b.
Main Exhaust Fan c.
Main Supply Fan d.
Thermal Column and Beam Tubes Exhaust Fan QUESTION (C 3 ) [2.0,0.33 eachl Using Figure C.3, match each of the core locations listed in column A with its correct component from column B.
Column A (Grid Position)
Column B
- a. A1 1.
Proportional Counter b.
A2
- 2. Compensated lon Chamber c.
A5
- 3. Startup Source d.
B4
- 4. Graphite Reflector Element
. e.
D9
- 5. Fuel Element f.
G9
- 6. Irradiation Basket
- 7. Servo Control Element (Regulating rod) 4
- -. ~,
Section C Facility and Radiation Monitorina Svstems Prgs '14 g
QUESTION (C.4 ) [2.0,0.33 eachl Identify whether the following scrams are ENABLED or DISABLED after placing the range switch (7S5) in the "O.10 MW" position.
a.
Primary low flow.
b.
Pool high temperature c.
Core inlet high temperature, d.' Bridge Movement e.
Coolant gates open. (Riser and downcomer).
f.
Thermal Column Door QUESTION (C.5 ) - [10]
3 The auxiliary operator reports thick black smoke coming from the primary pump. Where would you tell the auxiliary operator to go to deenergize power to the pump?
a.
Motor Control Center 1 b.
Motor Control Center 2 c.
Emergency Distr. Swbd. (480V end) d.
Hot Cell Power Panel QUESTION (C.6 ) [1.0)
Which one of the following combinations of detector alarms cause you to activate the " Limited Radiation Emergency Alarm"7 a.
Stack Monitor (A) and Bridge Monitor (K).
b.
Reactor Constant Air Monitor (C) and Fission Product Monitor (E),
c.
Facilities Exhaust Monitor (F) and Pump Room Monitor (P).
d.'
Bridge Monitor (K) and Control Room Monitor (R).
~ -.
l Section C Facility and Radiation Monitorino Svstems Page 15
' QUESTION (C.7 ) [2.0,0.5 each]
Match each of the control blade rod withdrawalinterlocks in column A with its setpoint from colemn B.
Column A -
Column B
- a. Low source count rate
_ cps.'
3.
L l
, b.
Short Period. _ sec'nds.'
S i
o t
t c; Low flux.__ %
7
_ d. Time delay block after " reactor startup"
_ seconds.
10 15 t
20 l-
-30 o
OUESTION (C.8 )' (2.0,0.66 each)
Match the purpose in column B for each of the Pneumatic Tube components in column A.
Column A Column B
- a. Wind-Gate Cabinet
- 1. Provide motive force for rabbit b.
Slide Gate Valves
- 2. Prevent draining of reactor pcol by siphon action.
t c.. Centrifugal Exhauster
- 3. Provide means for determining rabbit direction.
QUE'STION (C.9 ) [1.0)
.Which ONE of the following is the type of startup source used at the University of Mass.-Lowell Reactor?
- a.
l b.
Plutonium-Beryllium
- c. Neptunium-Antimony
- d. Americium-Beryllium LQUESTION (C.10 )
-[1.01
- Which ONE of the following correctly identifies part of a typical beamport arranged in order of prox;mity to the reactor core face outward.
- a. - Inner tube, thimble, instrument tube, shutter assembly-
- b.. Thimble, inner tube, instrument tube, shutter assembly c.
Inner tube, thimble, shutter assembly, instrument tube
'd! Thimble, inner tubei shutter assembly, instrument tube f-l r
[...
4
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Section C Facility and Radiation Monitorino Svstems Pagn 16 l
GUESTION (C.11 )
[1.0]
After placing the MASTER SW/TC#in the Qg position, a warning bell sounds. Which ONE of the I
following is the correct mathod for resetting the alarmc on the SCAM PANEL for this condition?
a.
Press the SCRAM RESET button then the ANNUN RESET button.
b.
Placa the MASTER SW/TC# in the Igall position, then back to the gg vasition, c.
Wait approximately 10 seconds for the warning bell to stop, then press the SCAM #ESET button, d.
Press the ANNUN RESET button, then the ANNUN ACKN button on the SCAM PANEL.
QUESTION (C.12 )
[1.01 Which ONE of the following conditions will result in a control blade withdrawal inhibit?
a.
Positive 20 second Log N period.
b.
Movement of the startup detector.
c.
Startup dstector indication of 5 CPS.
d.
Picoammuter range switch in the rnost sensitive position.
i QUESTION (C.13 )
[1.0}
A heat exchanger is designed to return water at 80.0'F, at a flow of 1500 gpm and an initial temperature of 91.4*F. Which ONE of the following is the heat removal capacity of the heat exchanger in Megawatts? (Use formulae and constants from Equation Sheet.)
a.
1.2 Mwatt b.
1.6 Mwatt c.
2.0 Mwatt d.
2.4 Mwatt QUESTION (C.14 )
[1.0) l Which ONE of the follovfing is the type of detector 'Jsed by the Stack Effluent Monitor for measuring airborne radioactive particulates?
a.
An end window GM type beta-gamma sensitive detector.
i
- b. A gamma sensitive, lead filtered, io. ' r, amber.
c.
A shielded gas cylinder containing a 12-inch GM type detector.
l d.
A Beta scintillation r'etector.
a 4
Section' C' Facility and Radiation Monitorina Svstems Paga 17 I
QUESTION (C.15 )'
[1.01:
Placing the MASTER SWITCH in the g position allows...
a.
Insertion of scram signals without deenergizing the scram magnets, b.
control power and lamp indication for operability testing.
' c.
control' drive motion without energizing the scram magnets.
- 6.,nontrol blade drive motion with energized scram mrgnets.-
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7 Section A R Theorv. Thermo. and Facility Characteristics Page 18 (A.1) b (See attached sketch - 11 fuel elements)
REF:
Burn, R., /ntroduction to Nuclear Reactor Operations,
- 1988, 5 5.5, pp. 5-18, through 5 25.
(A.2) a REF:
Burn, R., Introduction to iwc/ ear Reactor Operations, e 1988, 5 5.5, pp. 5-18, through 5-25.
-(A.3) c REF:
Burn, R., /ntroduction to Nuclear Reactor Operations, e 1988, 5 5.1 - 5.5, pp. 5-1, through 5-28.
(A.4) c REF:
Burn, R.', Introduction to Nuclear Reactor Operations,
- 1988, i 7.2, p. 7-1-7-9.
(A.5) e b _ Typographical error REF:
Burn, R., Introduction to Nuclear Reactor Operations,
- 1988, I XXXXXXXX K,n(l) = 1/(1 + SDM)
= 1/1.120 = 0.892857 CR(1)[1 - K,n(l)] = CR(f)[1 - K,n(f)] 100(1 - 0.893) = 200 (1 - x) %(1 -
0.893) = 1 - x 1 - x = 0.0535714:
x = 1 - 0.0535714 = M (A.6) a -
REF:
Burn, R.,' Introduction to Nuclear Reactor Operations,
- 1988, 9 2.4.6, p. 2-33.
(A.7) b REF:
Bern, R., Introduction to Nuclear Reactor Operations,
- 1988, 6 4.3, p. 4-4. P = Po e* In(PIPo)
= t/T T = t/(In(P/Po) T = 100/In(20) = 33.381 (A.8) a REF:
Burn, R., /ntroduction to Nuclear Reactor Operations,
- 1988, b 6.4.1, p. 6-5.
Reactivity due to temperature: -0.88 x 10 AK/K/*C x -8'C = + 7.04 x 10~' AK/K Movement: Rod must add 7.04 x 10' AK/K, therefore (7.04 x 10 AK/K) + 0.0003 AK/K = 2.346 inches in the negative (inward) direction.
(A.9) c REF:
Burn, R., /ntroduction to Nuclear Reactor Operations,
- 1988, il 8.4, & 8.6 pp. 8.10 through 8.14.
(A.10) c REF:
Burn, R., /ntroduction to Nuclear Reactor Operations,
- 1988, 5 4.3, p. 4 4. P = Po e" P = 1.2 5 Mwatt x e * = 1.25 Mwatt x 2.7183 = 3.3978 Mwatt (A.11) c l-REF:
Burn, R., Introduction to Nuclear Reactor Ope ations,
- 1988, 9 2.6.2, p. 2 50.
l (A.12) b REF:
Burn, R., Introduction to Nuclear Reactor Operations,
- 1988, E 3.2.2, p. 312.
(A.13) c l
REF:
Burn, R., Introduction to Nuclear Reactor Operations,
- 1988, 5 3.2.1, Table 3.2, p. 3-5.
l (A.14) c REF:
Burn,' R., /ntroduction to Nuclear Reactor Operations,
- 1988, E 3.2, Example 3.2, p. 3-2.
(A.15) a 4
REF:
Burn, R., Introduction to Nuclear Reactor Operations,
- 1988, 9 8.4.3, p. 8-19.
(A.16) d REF:
Burn, R., Introduction to Nelear Reactor Operations, e 1988, i 4.0, pp. 4-14 thru 4-17. For S/D reactor T = -80 seconds. Time = 180 seconds. P = Po e" = 3 x 10' e * = 3.162 x 105
1 i
- Section 'A R Theorv.-Thermo. and Facility Characteristics -
Page 19 l-(A.17) d.
REF:
Burn, R., Introduction to Nuclear Reactor Operations,
- 1988, E 6.2.2 p. 6-6.
I l~
(A.18) d REF:
Burn, R., introduction to Nuclear Reactor Operations,
- 1988, 6 3.2.4, pp. 3-13 & 3-31.
- (A,19) c -
)
REF:
Burn, R., Introduction to Nuclear Reactor Operations,
- 1988, E 6.2, p. 5-1, l
(A.20)' c I
- REF:
Burn, R., /ntenduction to Nuclear Reactor Oparations,
- 1988, t 4.4(b) p. 4-11. (P/Po) 1 1
1 1
I
.m Section B Normal. Emeroency and Radioloaical Control Procedures Pags 20 l:
- (B.1). RO 1, i 1.2.4 ~
c REF:
L L
-(B.2)
'b REF:
RO-11 1 1.1 (B.3) c REF:
Technical Specifications 5 5.4, p. IV-40 (B.4) a or c Second correct answer added per facility comment.
. REF: ' ULR Standing Order #10.
(B.5) c REF:
T.S. I 3.6, specifications 3,5, 7 and 8.
(B.6) c REF:. T.S. 4.4, Specification 7 and T.S.1.26.
(B.7) d REF:
(B.8) a, CC; b, CC; - c, CT; d, CAL REF:
T.S. I 1.0 DEFINITIONS (1.3,1,4,1.5)
(B.9)- d
' REF:
BASIC Radiological Concept (Betas don't make it through piping.)
(B.10) b REF:
RO 4, il 4.1.5 & 4.1.6.
(B.11) a, NC; b,DC: c,FC; ALL REF:
T.S. I 3.3, table (B.12) b REF:
SAR pp. 3-18 and 7 2.
(B.13) c REF:
NRC examination 01/27/87 and RO-4.
(B.14) d REF:
10CFR20 (A rem = a rem = a rem)
(B.15) c or a, Second correct answer added per facility comment.
REF:
NRC Exam 1/27/98 and SP-21.
(B.16) b 4
. REF:
NRC exam 3/29/98 also 10CFR55.53(e)
' (B.17) c REF:
= 0.051 cm /g x 11.4 g/cm' = 0.5814 cm I = lo e""
0.1 = e'""' in(0.1) = 0.5814 x x d
= In(0.1) + 0.5814 = 3.96 or 4 cm (B.18) c REF:
EO 7, also NRC Exam administered 8/3/88
Section C Facility and Radiation Monitorina Svstems Pags 21
-(C.1) c l
REF:
SAR, t 4.2.2 (C.2) a, @;
b, @;
c, @;
d, @
REF:
SAR, Figure 3.5 (C.3) a, 2; 5, 4: c, 3; d, 5; e, 7; f,1 REF:: SAR Figure 4.1, Core Arrangement (C.4 )
a, D; b, E; c, D; d, E; e,D;:f,E; REF:
ULR Technical Specifications, 6 3.3. R.O.9 " Reactor and Control System Checkout Procedures",
9.2.2.(d).~
(C.5 ) a REF:
U. Mass. - Lowell supplied Reactor Electrical Distribution Sheet.
(C.6 ) d REF:
U. Mass - Lowell, FSAR Appendix 10.
(C.7 )
a, 3; b,15; c, 5; d,10 REF:
USAR, 5 4.4.9 and table 4.4. R.O.9 "Rea: tor and Control system Checkout Procedures".
. (C.8 )
a, 3; b, 2; c,1 REF:. SAR I 4.3.3, p. 4-35.
(C.9 ) d REF:
SAR l 4.1.4, p. 4-6.
(C.10 )
d REF:
NRC exam administered Jan,1987, also SAR pp. 6 4 & 6-5.
(C.11 )
a REF:
RO 9, Step 3.25, p. RO-9-4. Also NRC exam administered March,1994.
(C.12) b
- REF; ULR RO-9, Rev 8, p RO-9 6, Standing Order #11, p 2.
(C.13 )
d REF:
Equation Sheet; d = the, hT = th hH = UA hT d = 1500 88###"#
- N lbrn x 60 *'""'#8 x 1.0 x (91.4'E-80.0'8 x 8 minutes Ibm *F gallon hour
- IU d = 8.208 x 108
= 2.407 Megawatts (C.14 )
d REF:
SM 17.4.6(2), p. 7 21. Also NRC exam administered March,1994.
(C.15 )
c REF:
NRC sxamination administered March,1993 and SAR Table 4.3.
U. S. NUCLEAR REGULATORY COMMISSION NON-POWER INITIAL REACTOR LICENSE EXAMINATION FACILITY:
U. Massachusetts-Lowell REACTOR TYPE:
GE POOL DATE ADMINISTERED:
1998/11/16 REGION:
I 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 Candidates Category Value Intgl Score Value Cateaorv 20.00 33.3 A.
Reactor Theor", Thermodynamics and Facility Operating Characteristics 20.00 33.3 B.
Normal and Emergency Operating Procedures and Radiological Controls 20.00 33.3 C.
Facility and Radiation Monitoring Systems 60.00 TOTALS FINAL GRADE All work done on this examination is my own. I have neither given nor received aid.
Candidate's Signature
l 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 neither received nor 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 gdy to facilitate legible reproductions.
5.
Print your name in the blank provided in the upper right-hand corner of the examination cover sheet and each answer sheet.
1 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 fer each question is indicated in (brackets] after the question.
l 8.
If the intent of a question is unclear, ask questions of the examiner only.
l 9.
When turning 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 allinformation 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.
To pass the examination you must achieve a grade of 70 percent or greater in each category.
11.
I l
12.
These is a time limit of three (3) hours for comr,ietion of the examination.
13.
When you have completed and turned in you examination, leave the examination area. If you are observed in this area while the examination is still in progress, your license may be denied or revoked.
F i
EQUATION SHEET
- o O = the AT = th AH = UA AT P,,, = (p -p)2
= 3 x 10-" second S
S A,y = 0.1 seconds -1 scg =
R (1 -K,y,) = CR (1 -K
=
3 2
en
-p 1-Ke/
CR (-p3) = CR (-P )
3 2
2 i
SUR = 26.06. '"P 1-Ken 1
CR o
3
- p-p M=
M=
=
1-K,y, 1-K,y CR2 P = P 10 "
I 8
P = p(1 -p) P o
T P=Pe o
o P-P f
SOM =
T=
T = E- +
b-P K,y p-Q p
Aj.
K,y, - K,
(K -1)
Ap =
T,_ 0.693 p =
_,y eu y
A K
ett, X Keu en 2
DR = 6CiE(n) og,g,2, og,g 2 g
DR =DR e.u g2 o
DR - Rem, Ci - curies, E - Mev, R - feet (p2-0)*, P -0)*
I i
- Peak, Peak, 1 Curie = 3.7 x 10' dis /sec 1 kg = 2.21 lbm 1 Horsepower = 2.54 x 10' BTU /hr 1 Mw = 3.41 x 10' BTU /hr 1 BTU = 778 ft-Ibf F = 9/5 *C + 32 1 gal (H 0) = 8 lbm
- C = 5/9 (*F - 32) 2 cp = 1.0 BTU /hr/lbm/ F c, = 1 cal /sec/gm/ C f
Section A' R Theorv Thermo, and Facility Characteristics Page 4 v
A.1 - abcd A.11 a b c d A.2 abcd A.12 a b c d A.3 abcd A.13 a b c d -
A.4 abcd A.14 a b c d A.5 - a b c d A.15 a b c d A.6 abcd A.16 a b c d A.7 abcd A.17 a b c d A.8 abcd A.18 a b c d e
A.9 abcd A.19 a b c d A.10 a b c d A.20 a b c d
,s
l Section B Normal /Emera. Procedures & Rad Con Prgs 5 w
B.1.
abcd 8.10 a b c d B.2 abcd B.11a FC NC CP DC ALL
~B.3 abcd B.11b FC ^!r CP DC ALL B.4 abcd-B.11 c FC NC CP DC ALL B.5 abcd B.11 d FC NC CP DC ALL B.6 abcd B.12 a b c d B.7 abcd B.13 a b c d B.8a CC CT CAL B.14 a b c d B.8b CC CT CAL B.15 a b c d B.8c CC CT CAL B.16 a b c d B.8d CC CT CAL __
B.17 a b c d B.9 abcd B.18 a b c d
=-
Section C Facility and Radiation Monitorina Systems Paga 6 W
C.1 abcd C5 abcd C.2a @ @ - @ @ @ @ @
C.6 abcd C.2b @ @ @ @ @ @ @
C 7a 3 5 7 10 15 20 30 C.2c @ @ @ @ @ @ @
C.7b 3 5 7 10 15 20 30 C.2d @ @ @ @ @ @ @
C.7c 3 5 7 10 15 20 30,
C.3a 1 2
3 4 5
6 7
C.7d 3 5 7 10 15 20 30 C.3b 1 2
3 4 5
6 7
C.8a 1 2
3 C.3c 1 2
3 4 5
6 7
C.8b 1 2
3 C.3d 1 2
3 4
5 6 7 C.8c 1 2
3 C.3e 1 2
3 4 5
6 7
C.09 a b c d C.3f 1 2
3 4 5 6
7 C.10 a b c d C.4a E D
C.11 a b c d C.4b E D
C.12 a b c d C.4c E D
C.13 a b c d C.4d E D
C.14 a b c d C.4e E D
C.15 a b c d C.4f E D
n/
6 Table A.1 1/M Plot for New Fuel Loading Number of Count Rates for all Rods Out Elements Loaded Detector A Detector B Detector C 0
270 303 250 2
290 400 476 4
323 526 666 6
385 800 1075 8
472 1250 1818
0 1
deha m 4
500KW 250 KW
[
1/2
><-3-><
4 TlWE a
xe delta lyK 500 KW 250 KW f
(
1/2
><-3-><
4
)
TlWE J
Xs dehe FJK h
500 KW 250 KW
[
\\
1/2
><-3-><
4 TlWE i -
C xe delta K/K l
500IrW 250 KW ji 1/2
> <- 3 -) <
4 TIME d
FIGURE A.1 1
.h
't Retention Tank 52,000 gallons.
.. ru...s
. fmen check Valves P 37 and P 12 p.16 P-IS P-17 P-IS 0180*F 4 P' l.l BULK STALL i-l l-l l-}
l
-l I
POOL poot
,T
.{P-2 P-I3 I
.P-i4 P-IO ff P-44
'P)
{l P-22 j.}
P.27.
s chrintary Pump
'i P-45
/
e-29 P.23 P.16 P-l '2
/
k
- -l
}.l
'.t I ' I v
IIOLD-UP TANK l'
3,000 gallons j
.CE I
(
P-47 U-embe IMw j
(,,, ' P-30 P / I P-4s tp) Drain ~0180*F TR) (TE ) P-3 4 P-33 P-31 l(T i 903l ( TE I l"8 I-l i^! l-l Flow Orifice I i -ll l f-f j P-19 R) P-23 II P-32 y l } *, pui i P-3 5 I P-40 v.c %, Yw s (p1 P.3,
- v. ca,
BULK w-- P-42 P-39 P-36 P-6 P-4 P-g P-2 P-1 P-5 P-3 P-7, poot P-41 I'I' l l ST M 1 l tFT) poot l P.24 I P ) r-42 I p,I _I [ I(~l B 3g l-l Anti-S phon Lines p AntL5ipke 1,ines > P-2 5 Figure C.1 l
... o O 'O H G Il{ D lE ( i i ( l 0 @< j' l, I ff sg ll \\\\D II ! Eg @(. l d { i d I IU \\\\ j Y Y ctvy g s\\ l [ G @ - }.1 's c li i is OF x a ^ _D \\ 3.g...;.i...... I E3 (I i t l'jBa*' a Vacuum l S C"h"8 Breaker l j ne. ting Figure C.2
o =,
- 1 l
i A + I I llll! ! l' B i 1i l i i l I C ( ) l I! I D ( ) !I t l ( I E I l! F ( ) I I I ( ) it ,) G 1 2 3 4 5 6 7 8 9 Figure C.3
3 Table A.1 1/M Plot for New Fuel Loading Number of Elements Loaded Count Rates for all Rods Out Detector A Detector B Detector C Reading Reading Reading 0 270 303 250 2 290 400 476 4 323 526 666 6 385 800 1075 8 472 1250 1818 CR/CRo CR/CRo CR/CRo 0 1 1 1 2 0.93 0.76 0.53 4 0.84 0.58 0.38 6 0.7 0.38 0.23 8 0.57 0.24 0.14 10 12 1/M Plot 1 ~[..3 O.8 <- 5 $ 0.6 I-N.- - -- - H o j 50.4 7._ l 0.2l -l i a 0 i-- 0 2 4 6 8 10 12 Number of Fuel Elements j -=- Detector A --- Detector B -=- Detector C l l}}