ML20247H010
| ML20247H010 | |
| Person / Time | |
|---|---|
| Issue date: | 07/17/1989 |
| From: | Perkins K Office of Nuclear Reactor Regulation |
| To: | Jaudon J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| References | |
| NUDOCS 8907280253 | |
| Download: ML20247H010 (81) | |
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k UNITED STATES l
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g NUCLEAR REGULATORY COMMISSION 7,
- p WASHINGTON, D. C. 20555
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.dul M 1989 FEMORANDUP FOR: Johns P. Jaudon, Deputy Director Operations Branch Division of Reactor Safety Pegion IV FROM:
Kenneth E. Perkins, Jr., Chief Operator Licensing Branch Division of Licensee Performance and Ouality Evaluation, NRR
SUBJECT:
RESULTS OF GENERIC FUNDAMENTALS EXAMINATION SECTION (GFES) Oc TPF KRITTEN LICENSING EXAMINATION FOR REGION IV On June 28, 1989, NRC administered the PWR and BWR Generic Fundamentals Examination Section (GFES) of the NRC written examination to seven (7) facilities in your region. Enclosed with this memorandum are the results of the graded examinations for your region, copies of the PWR and BWR Examinations as administered (forms a and b) with answers and a copy of the cover letter sent to each of the Facilities in your region.
In accordance with 10 CFR 2.790 of the Commission's Regulations, a copy of this letter with enclosures (1) through (5) will be placed in the Public Document Room. The examination results of individual participants are exempt from public disclosure, therefore enclosure (6) will not be placed in NRC's Public Document Ponn.
For licensee applicants scheduled to take an NRC written examination prior to October 1,1989, the regions are delegeted authority to grant waivers for applicants requesting to substitute their GFES examination scores for the fundamentals portion of their licensing examination (section 1 (RO) or section 4 (SRO) of the examination). The waiver shall be granted if an applicant scored 70% or greater on the GFES. The GFES examination score is to be used in determining the overall results of the written licensing examination.
If an applicant for either an RO or SR0 license elects to use the GFES score, it will count for 25% of the overall reactor operator examination score or 24% of the overall senior operator examination score. A candidate must still obtain an overall minimum score of 80% on his/her licensing examination to pass.
For license applicants scheduled to take en NRC examination on or after October 1,1989, the applicant will be required to provide documentation of proficiency in the enterial tested by the GFES. To do this the applicant will be required to submit the date that he or she " passed" either a GFES of the written licensing examination or the fundamentals section of an NRC I )f y administered written licensing examination administered between February 1, r
1982 and October 1,1989, resulting in the applicant receiving an R0 or SR0 l.'
license. After October 1, 1989 the GFES results will not be numerically d'I NRC RE CEVTEPi COPY
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6 averaged with site-specific sections of the written examination, but will be recorded as " passed" or " failed." The remaining two site specific sections of the written examination still requires.a 70% per section, 80% overall average to pass the written examination.
The NPC will administer BWP and PWR GFESs three times annually, on the Wednesday of the first full week in February, June and October.
The next GFES will be administered Wednesday October 4, 1989, in five regional locations.
The NRC will not administer the fundamentals section (Section 1 for an R0 examination or Section 4 for an SR0 examination) in conjunction with the site-specific vritten examination after October 1, 1989, except as negotiated with the NRC regional offices up to but not beyond November 1,1989.
l Operator Licensing Branch'(OLB) is in the process of issuing an Information Notice to' all holders of PWR and BWR operating licenses and construction permits and all holders of Reactor or Senior Reactor Operator licenses, describing the implementation of the GFES. OLB is also revising the Operator Licensing Examiner Standards (NUREG-1021) to implement the GFES.
If you have any cuestions concerning this letter, please contact Dave Lange at FTS 492-3172.
l Kenneth E. Perkins, Jr., Chief Operator Licensing Branch l
Division of Licensee Performance and Quality Evaluation, NRR
Enclosures:
1.
GFES Examinations PWR and BWR (Forms "A":
and "B:) with answers 2.
Copy of Voluntary Packground Information Feedback Form for Examination Participants 3.
Copy of Voluntary Examination Feedback Form for examination participants 4.
Copy of Voluntary Examination Feedback Form for training department personnel 5.
Copy of Cover Letters for Region facilities 6.
Examination Results for Region facilities L
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Distribution f or Memo to region branch chief RE: GFE 6 89 results dated JUL41 1989 4
DISTRIBUTION (w/o Enclosure 6) l OLB R/F
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'NRf POBlIC D0d MENT ROOM Robert D. Martin, RIV James L. Milhoan, RIV John Pellet
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Date:
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.g ENCLOSURE 1 GENERTC FUNDAMENTALS EXAMINATION SECTION (GFES)
FORMS A AND B l
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TEST FORM A UNITED STATES NUCLEAR REGUIATORY COMMISSION PRESSURIZED WATER REACTOR GENERIC FUNDAL (ENTALS EKANINATION SECTION Please Print:
NAME FACILITY ID NUMBER INSTRUCTIONS TO CANDIDATE Use the answer sheet provided.
Each question has eoual point value. The passing grades require at least 70% on.this part of the written licensing
. examination. All examination papers will be picked up 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> after the-examination starts.
SECTION Questions
% OF TOTAL SCORE COMPONENTS 1
- 22 44 REACTOR THEORY 23 - 36 28 THERMODYNAMICS 37 - 50 26 TOTALS 10P i
11 work done on this examination is my own, I have neither given nor received aid, i
I Candidate's Signature TEST FORM A
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i NRC RULES AND CUIDELINES FOR THE CENERIC FUNDAMENTALS' EXAMINATION 1,
L Durin5 the administration of this examination the following rules apply:
L (1)
Print your name in the blank provided on the cover sheet of the examination.
(2)
Fill in the name of the facility you are associated with.
1 l
(3)
, Fill in the ID-Number you were given at registration.
(4)
Three handouts are provided for your use during the examination, an Equations and Conversions sheet, Instructions on fill out the answer sheets and Steam Table booklets.
(5)
Use only the answer sheet provided.
Credit will only be given for answers marked on this sheet.
Follow the instructions'for filling out the answer sheet.
(6)
Scrap paper will be provided for calculations.
(7)
Any questions about an item on the examination should be directed to the examiner only.
1 (8)
Cheating on the examination sill result in the automatic forfeiture of this examination, Cheating could also result in more severe penalties.
(9)
Restroom; trips are limited. Only QHE examinee may leave the room at a l
time. _ In order to avoid the appearance or possibility of cheating,.
avoid all contact with anyone outside the examination room.
(10)
After you have completed the examination, please sign the statemett on the cover sheet indicating that the work is your own and you have not i
received or'been given assistance in completing the examination.
J (11)
Please turn in your examination materials answer sheet on top followed by the exam booklet, then examination aids - steam table booklets, Handouts and scrap caper used during the examination.
,1 (12)
After turning in your examination materials, leave the examination area, as defined by the examiner.
If after leaving you are found in the examination area while the examination is in progress, your examination may be forfeit.
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PRESSURIZED WAT10t H.EACTOR GENERIC FUNDAMENTALS EXAMINATION COMPONENTS e
1.
Use the drawing of a spring-loaded valve (see Figure 1).
Following a loss <of system. pressure..the position of this valve will always:
A.
go to the fully open position.
B.
remain at the previous ~ position.
C.
go to the fully closed position.
D.
So to the mid-positioni O
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!t Discharge
(-'
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)
Pressure i
FIGURE 1 i
FDRM A 1
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4 2.
A correct statement regarding thermocouple is that they:
A.
Will indicate low offscale with an open circuit at the sensing junction.
B.
are more accurate than resistance temperature detectors.
C.
are made up of two similar metals in contact at one end, called the hot junction.
D.
are based on the following characteristic of metals:
a change in electrical resistance occurs when a change in temperature occurs.
3.
Prior to manually operating a motor-operated valve, it is good practice to:
A.
stroke the valve electrically while depressing the manual clutch er. gaging lever to smoothly engage the clutch.
B.
tag open the power supply to the valve motor.
C.
pull up firmly on the declutch hand lever to reseat the clutch.
l D.
fully stroke the valve electrically to ensure that it moves freely with normal motor torque.
FDRM A 2
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4.
Refer to Figure 2-for.the following question.
.All valves are identical and are initially 50% open. The temperature at point.7 is' exceeding operating limits.
To MHgg the temperature at point 7, the operator should adjust valve in ~ the open l
direction.
A.
A
'B' B
C, C
D.~
'D fROM TO SYSTEM SYSTEM O
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ION EXOMANGER FIGURE 2 FORK A 3
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i 5.
' Tube scaling in a parallel-flow heat exchanger will ca tse heat transfer to decrease because-A.
flow through the heat exchanger increases.
B.
surface area of the tubes decreases.
I C.
heat transfer coefficient decreases.
. i D.
inlet temperature of the cooling fluid increases.
6.
A centrifugal pump is started and the following indications are observed:
Oscillating flow f
Oscillating discharge pretsure oscillating amps This indicates that the pump is experiencing:
A.
motor overload.
B.
cavitation.
C.
pump runout.
D.
shutoff head.
7.
Closing the output breaker of a three phase generator onto a deenergized bus can result in:
A.
an overvoltage condition on the bus.
B.
an overcurrent condition on the generator if the bus was not first unloaded.
C.
a reverse power trip of the generator circuit breaker if generator frequency is low.
-D.
a large reactive current in the' generator.
FDRM A 4
4
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4 8.
The average starting current for an alternating current motor is approximately:
A.
the.same as its normal running current.
y i
B.
two to three times its normal running current, j
C.
five to seven times its normal running current.
D.
ten to fifteen times its normal running current.
-]
l 9.
The term " shutoff head" for a centrifugal pump indicates that it is j
pumping at capacity and discharge head.
.]
A.
maximum, minimum B.
maximum, acximum C.
minimum, maximum D.
minimum, minimum 10.
Please complete the following statement to describe the theory of operation of a differential. pressure level detector using a vet
)
reference leg.
The pressure differential between a height of liquid and the pressure sensed at the bottom of a tank is proportional to the. height of 1: quid in the tank.
l
.A.
known, dirac./
B.
known, inversely C.
variable, directly D.
variable, inversely FORN A i
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11.
- k'hich of the following describes the BEST method for deenergizing a breaker :ontrol circeit?
)
A.
Breaker in test position, i
B.
Breaker fully racked out.
C.
Control power fuses removed.
D.
Control switch in pull-to-lock.
(
12.
Using the drawing of an air-operated valve (Figure 3), identify the valve position following a loss of electrical power.
A.
Mid-position.
B.
Closed.
C.
As is.
D.
Open.
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4 13.
L'hich of the following liQST ACCURATELY describes the purpose of a demineralized?
/-
i j.
A.
To produce an exchange of ions in water.
' l B.
To. reduce the conductivity of water without affecting its pH.
C.
To increase the pH of water by reducing the number of positively '
i charged ions in it.
D.
To increase the conductivity of the water to greater than 1.0 I
microhms.
j
.l 14 L' hen - flow from a centrifugal pump is increased by throttling open the discharge valve, AVA11>3LE net positive suction head (NPSH) and REOUIRED NPSH 1
A.
decreases, decreases.
]
B.
decreases, increases.
)
C.
increases, increases.
D; increases, decreases.
15.
A generator is operating on the grid synchronized with other generators.
Concerning this generator, which of the following statements it correct?
A.
Increasing the excitation decreases the reactive power on the grid.
B.
Increasing the excitation will result in excessive circulating current, causing inefficient operation and unnecessary' heating of the generator.
C.
Decreasing the excitation on the generator sneans decreasing the excitation on all other generators on the grid to balance the negavar loading.
D.
Decreasing the excitation will cause the generator to act like a capacitor and supply positive lagging vars.
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16.
A break in' the FAEl@LE. le f a wet reference.' leg differential pressure type level detector will c
.s the indicated level to:
.'A.
be greater than actual level, u
~B.
be less than actual level.
C.
remain' constant at the actual level.
D.
fluctuate around the actual level.
17.
When starting a centrifugal pump, the response of motor current should
.be:
A.
low starting amps, increasing to a higher equilibrium running-amperage.
B.
Iow starting. amps, remaining at a low equilibrium running
. amperage.
C.
high. starting amps, decreasing to a lower equilibrium running..
-amperage.
Di high starting,cmps, remaining at a high equilibrium running
- amperage, l
18.
Which'of the following results from a loss of circuit breaker. cont.rol power to a circuit breaker supplying a motor?
A.
Motor ammeter indication would be zero regardless of actual breaker position.
B.
Breaker position would remotely indicate c.losed regardless of l
actual position.
C.
Breaker would trip open due to the actuation of its protective trip device.
D.
Close spring charging motor would not charge spring following local tripping of the breaker.
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Using the - drawing of a centrifugal pump' characteristic curve Y
4, which point represente-the pump's shutoff head.
A,-
Point A.
s E
B.
Point B.
C.
Point C.
D.-
Point D.
i-Point A i
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20.
A pump is operating at 1800 rpm, pump head is 100 psid, and pump current is 10 amperes.
What will be the new value of pump head if the speed is I
increased such that the current requirements are now 640 amperes?
I A.
400.
'li B.
800.
C.
.1,200.
D.
1,600.
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.21-Vnich of the following is a IEJZE statement regarding parallel-flow and counter flow heat exchangers?
A.
A parallel flow heat exchanger must maintain a large DELTA-T throughout its length to equal the heat transfer capabilities of a counter-flow heat exchanger.
B.
A parallel flow heat exchanger must have more heat transfer area to equal the heat transfer capabilities of a counter-flow heat exchanger..
C.
A parallel-flow heat exchanger must heat the. cooling water to a
higher temper &ture than that to which the cooled medium is cooled.
D.
A parallel-flow heat exchanger must have a higher cooling-water inlet temperature to equal the heat transfer capabilities of a counter-flow heat exchanger.
l 22.
Air binding in a centrifugal pump is an undesirable condition which may' be AVOIDED by:
A.
throttling closed the suction valve prior to pump start, then opening it again.
B.
opening the discharge valve fully, then starting the pump to allow air,to be forced out.
C.
opening the pump casing vent valve, while priming the pump, until a steady stream of water rppears.
D.
opening the pump suction vent valve just prior to starting the pump and then closing it after the pump is running.
I FDRM A 10
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' REACTOR THEORY 23.
In which of the following conditions is the moderator temperature coefficient most negative?
A.
BOL, high' temperature.
B.
P0L,. low temperature.
,'C.
EOL, high te:nperature.
s'
.D.
EOL, low temperature.
24
. Which one of the following plant parameter changes will result in an.
incre.'se' in shutdown margin for. a shutdown reactor? Assume end cf life.
A.
RCS boron concentration is increased by.100 ppm.
' iL -
One control rod (CEA) is fully withdrawn for.a test.
C.
Xenon har decayed for 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> following shutdown.
D.
RCS is cosled down by 300 degrees F.
25.
The reactor is critical-at 10,000 cps when a S/G PORV (atmospheric relief' valve) fails shut. ' Assuming BOL conditions, no rod action. and no: reactor trip, choose the one answer below that best. describes the values of. Tave-and nuclear power for the resulting new steady state.
(POAH - point of adding heat.)
A.
Final Tave greater than initial Tave. final power at POAH.
B.
Final Tave greater than initial Tave, final power above POAH.
C.
Final Tave less than initial Tave, final power at POAH.
D.
Final Tave less than initial Tave, final power above POAH.
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26.
Which one of the following conditions will initially-result in a positive startup rate when the reactor is at power?
io
- g A.
Increase in turbine loading.
i B.
Unintentional boration.
C.
Turbine runback.
i D.
. Accidental closure of a main'stsam isolation valve.
27.
Shutdown margin is the actual amount of reactivity' A.
inserted by burnable poisons at beginning of life.
B.
due to' dissolved boron in the RCS.
l C.
by which the reactor is suberitical.
D.
which would be inserted by shutdown bank rods.
... z-
-28.
Consider ~ the following information for perforcing a-reactor startup (S/0) to full power:
i
- ! =
The process began five hours after a. trip from full power equilibrate conditions.
.A 2.0%/ min ramp was 'ased rather than a 0.St/ min rxmp.
I Thus, the xenon dip would occur _.
and the magnitude of the dip would be A.
sooner larger B.
sooner smaller C.
later larger
.D.
later smaller i
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' 29.
When does the power decrease rate initially stabilize at negative one-third decade per. minute following a reactor trip?
A.
When decay gamma heating, starts adding negative reactivity.
'3.
When the long-lived delayed neutron precursors.have decayed away.
C.
When the installed neutron source. contribution to the total neutron flux becomes significant.
D, When the short-lived delayed neutron precursors have. decayed away.
30.
With Keff - 0.985, how much reactivity must be added to make the reactor critica.17 A.
1 48%
4K/K.
B.
1.50%
e K/K.
C.
1.52%
A K/K.
D.
1.54%
A K/K.
31.
Which one of the following statements concerning the pouer defect is correct?
A'.
The power defect necessitates the use of a ramped Tave program to maintain an adequate Reactor Coolant System subcooling margin.
B.
The power defect increases the red height requirements necessary to maintain t.he desired shutdown margin'following a reactor trip.
C.
Because of the. higher boron concentration, the power defect is more negative at the beginning of core life.
D.
The power defect c'auses control rods to be withdrawn as reactor power is decreased.
a..
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I 32.
The magnitude of decay heat generation is determined primarily by:
l (choose one)
A.
Core age B.
Power history C.
Final power at shutdown D.
Temperature of reactor coolant 33.
Moderator temperature coefficient (MTC) is defined as the change in core reactivity per degree change in:
A.
coolant temperature.
B.
reactor vessel temperature.
C.
cladding temperature.
D.
fuel temperature.
34.
Which one of the following expresses the relationship between differential rod worth (DRW) and integral rod worth (IRW)?
i A.
DRW is the area under the IRW c*.trve at that location.
B.
DRW is the slope of the IRW curve at that location.
C.
DRV is the IRW at that location.
D.
DRV is the square root of the irk at that location.
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t 35.
.A' reactor is operating-at a' power level of 120 watts. A control rod is
/-
M
. inserted,'which results in a stable negative 80-second period. Which of
,g;.
the following is ' the ESI ' estimate of the reactor power. level two
-jy
>ainutes after rod insertion?
._ f'
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//,
'a '
A.
-- 27 watts.
B.
32 watts.
C.
49 watts.
7 z-
,f' D.
54 watts.
- i; 36.
If a reactor core with a neutron source is exactly critical at 1000 CPS in the source. range, over the next few minutes the count rate should:
A.
remain constant.
.B.
increr.se linearly.
C.
increase geometrically.
D.
increase exponentially.
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3 37.
Which one of the statements below is CORRECT if the power range instruments have been adjusted to 1006 based on a calculated calorimetric?
A.
If the feed water temperature used in the calorimetric calculation was higher than actual feedwater temperature, actual power will be less than indicated power.
B.
If the reactor coolant pump heat. input used in the calorimetric calculation is omitted, actual power will be less than indicated power.
C.
If the steam flow used in the calorimetric calculation was lower than actual steam flow, actual power will be less than indicated power.
D.
If the steam pressure used in the calorimetric calculation is lower than actual steam pressure, actual power will be less than indicated power.
36.
Which one of the following reactor coolant system (RCS) parameters has
.the LEAST effect on margin to departure from nucleate boiling (DNS)?
Consider each separately.
A.
. Pressurizer level.
B.
Local power density.
C.
Cold leg temperature.
l D.
Coolant flow rate.
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Reactor Power is increased sufficiently to cause sto.m blanketing of several fuel rods. This condition is being caused by:
A.
departure from nucleate boiling.
B.
subcooled nucleate boiling.
L'
.C.
saturated nucleate boiling.
1 D.
onset of nucleate boiling, 40.
Pressurized Thermal Shock (PTS) is a rapid cooldown of the - RCS in combination with:
A.
.high reactor power.
.a B.
low pressurizer level.
C.
high RCS pressure.
D.
Iow RCS flow.
-l 41.
Given_the-following RCS parameters, determine the RCS subcooling margin.
RCS pressure - 22335 psig.
J RCS hot leg temperature - 610' F.
f 1
A.
25' F,'302 psi.
-l' E.
31* F. 433 psi.
C.
38' F, 505 psi.
D.
43' F, 588 psi.
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42.
Operating with which of the following conditions is LEAST EFFECTIVE in preventing brittle fracture in the RCS?
A.
Operating within prescribed heatup and cooldown rate limitations.
- !J B.
Operating with RCS temperature greater than Nil Ductility Temperature.
C.
. Operating with RCS pressure low when RCS temperature is low.
D.
Operating with a ramped RCS temperature as power level varies, i
43.
Fast neutron irradiation adversely affects the reactor pressure vessel
- primarily bf causing, A.
metal embrittlement.
B.
brittle fracture.
C.
thermal grac' tents.
D.
pressurized thermal shock.
44.
An adequate subcooling ' margin during a loss of-coc,lant accident (LOCA) is the most direst indication that is being maintained.
A.
steam generator water level B.
pressure level C,
core cooling D.
suberiticality l
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45.
How does critical heat flux vary from the bottom to the top of the i
reactor core during normal full power operation?
I A.
Decreases continuously.
(
B.
Decreases then increases.
C.
Increases continuously.
D.
Increases then decreases.
j
.j 46.
As compared to saturated nucleate boiling (bulk boiling), subcooled l
nucleate boiling:
)
A.
occurs to a
greater. extent in the pressurizer and steam generators.
I B.
requires fewer BTU /lba to convert reactor coolant to steam at a given temperature, j
u C.
occurs less during normal plant cperation.
D.
results in a lower convective heat transfer coefficient.
l l
i l
l 47.
Placing two pumps in parallel alignment versus a single pump will result in:
A.
a large increase in system head and the sane flow rate.
I B.
a small increase in system heau ad a large increase in flow rate.
)
1 C.
the same systen head and a small increase in flow rate.
l l
l D.
a decrease in system head and a large increase in flow rate.
1 1
i l
l FORM A 19 i
f b ____ ___ - -
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1*l,.
1,.
l, c
'48.
The ' pressurizer power-operated relief _. valve has stuck in a partially.
opened position with the fluid-being discharged 'into. the pressurizer-relief tank.
The pressurizer pretsure.is 2200 psia and the relief. tank
'pressurecis 5 psig.-. What is the condition of the fluid downstream of-the relief valve?
A.
superheated steam.
B.-
subcooled liquid.
C.
dry saturated steam.
D.
wet vapor.
49.
Which'of the following is HQI an indication of cavitation?-
l A.
Fluctuating discharge pressure.
B.
Pump. vibration.
C.
Pump overheating.
1 D.
High discharge pressure.
J.
50.
Ac steam goes through a throttling process in a main steam header to atmospheric leak,-in which of the following parameters will there be an increase?
A.
Enthalpy.
B.
Pressure.
C.
Specific Volume.
D.
Temperature, re b
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UNITED STATES NUCLEAR REGUIATORY COMMISSION PRESSURIZED' VATER REACTOR GENERIC FUNDAMENTALS SIANINATION SECTION I
Please-Print:
NAME f
FACILITY ID NUMBER 1
. INSTRUCTIONS TO CANDIDATE Use the' answer sheet.provided.
Each question has equal point value.
The passing grades require at least 70% on this part of the written licensing l
examination. All examination papers will be picked up 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> after the examination starts.
SECTION Questions t OF TOTAL SCORE l
22 44 COMPONENTS 1
kEACTORTHEORY 23 - 36 28 THERMODYNAMICS 37 - 50 28 TOTALS 100 All work done.on this examination is my own.-
I have neither given nor l
received aid.
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a ERC RULES AND GUIDELINES FDR THE GENERIC FUNDAMENTALS EXAMINATION During the administration of this examination the following rules apply:
qt (1)
Print your name in the blank provided on the cover sheet of the j
examination.
1 g
/
Fill in the name of the f.acility you are associated with.
(2)
(3)
Fill in the ID-Number you were given at registration.
Three handouts are provided for your use during the examination, an Equations and Conversions sheet, Instructions on fill out the answer
]
(4)
I sheets and Steam Table booklets.
(5)
Use only the answer sheet provided.
Credit will only be given for answers marked on this sheet.
Follow the instructions for filling out the answer sheet.
(6)
Scrap paper will be provided for calculations.
(7)
Any questions about an item on the examination should be directed to the examiner only.
Cheating on the examination will result in the automatic forfeiture of (8) this examination. Cheating could also result in more severe penalties.
(9)
Restroom trips are limited..Only QHE examinee may leave the room at a In order to avoid the appearance or possibility of cheating, l
time.
l avoid all contact'with anyone outside the examination room.
i After you have completed the examination, please sign the statement on (10) the cover sheet indicating that the work is your own and you have not received or been given assistance in completing the examination.
Please turn in your examination materials answer sheet on top followed by (11) the exam booklet, then examination aids - steam table booklets, Handouts and scrap paper used during the examination.
After turning in your examination materials, leave the examination (12) area, as defined by the examiner. If after leaving you are found in the examination area while the examination is in progress, your examination may be forfeit.
1 I
PRESSURIZED WATER RREACTOR GENERIC }TNDAMENTALS EEAKINATION COMPONENTS 1.
Use the drawing of a spring-loaded valve (see Figure 1).
Following a loss of system pressure, the position of this valve will:
A.
go to the fully open position.
B.
remain at the previous position.
C.
go to the fully closed position.
D.
go to the mid-position.
.- y
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hd Spnng p
_V a
f k
l};
l !
Dis::harge 1
1 l
7 J
p 9
r 1
System Pressure FIGURE 1 FORM B L_ _ _ r _ _
=
2.
The average starting current for an alternating current motor is approximately:
A.
the same as its norma 1 running current.
B.
two to three times its normal running current.
C.
five to seven times its normal running current.
D.
ten to fifteen times its normal running current.
1 e
FORM B l
2 1
l l
l
- -..=_
7 -.
L
..f -l
'h, r
s
~..:
7.
., s.:,
- s '
3.
' Refer to Figure 2 for the following question.
.All valves are identical'and are initially'50% open. The temperature at point 7' is exceedin6 operating limits.
To M5[EE the temperature at point 7, the operator should adjust - valve in the open
' direction.
A.
A B.
B-C.
C D.
D-FROM TO SYSTEM SYSTEM O
540*F g2 A.
3 C
l
~
460*F O
1 m
r w w
122'F.
b 250'F e 4 e
5 COOLING 6
WATER n Ds n
110'F 122'F gl 7 -
1 ION EXCHANGER FIGURE 2 i
FORM B 1
l 1
--.m.__- _ _ _. _ _.. _ _. _ _ _,.. _ _ _ _ _. _ _ _ _,
b
- i.
?
L
'4 A break in the VARIABLE leg of a wet reference leg differential pressure 4.
type level detector _will cause the indicated level to:
A.
be greater than actual level.
B.
be less than actual level.
C.
remain constant at the actual level.
D.
fluctuate around the actual level.
it is good practice l:
5.
Prior to manually operating a motor-operated valve, to:
the valve electrically while depressing the manual clutch A.
stroke engaging lever to smoothly engage the' clutch.
B.
tag open the power supply to the valve motor.
pull up firmly on the declutch hand lever to ressat the clutch.
C.
fully stroke the valve electrically to ensure that it moves freely D.
with normal motor torque.
Closing the output breaker of a three-phase generator onto a deenergized 6.
' bus can result in:
A.
an overvoltage condition on the bus.
an overcurrent condition on the generator if the bus was not first B.
unloaded.
a reverse power trip of the generator circuit breaker if generator C.
frequency is low.
D.
a large reactive current in the generator.
)
l
]
1 l
j FORM B 1
'b When' flow from a centrifugal pump is increased by throttling open the 7.
discharge valve, AVAILABLE net positive suction head (NPSH)-
and REOUIRED NPSH A.
decreases, decreases.
B.
decreases, increases.
C.
increases, increases.
D.
increases, decreases.
8.
Which of the' following results from a loss of circuit breaker control power to a circuit breaker supplying a motor?
A.
Motor ammeter indication would be zero cegardless of actual breaker posicion.
B.
Breaker position would remotely indicate closed. regardless of actual position.
C.
Breaker would trip open. due to the actuation of its protective trip device.
D.
Close spring. charging' motor would not charge sprin'g following local tripping of the breaker.
9.
.Wh'en starting a centrifugal pump, the response of motor current should be:
higher equilibrium running A.
low starting amps, increasing to a
' amperage.
B.
low starting amps, remaining' at a low equilibrium running-amperage.
C.
high starting amps, decreasing to a lower equilibrium running 1
amperage.
D.
high starting amps, remaining at a high equilibrium running amperage.
FORM B 5
1 2
10.
A pump is operating at 1800 rpm, pump head is 100 psid, and pump current is 10 amperes.
What will be the new value of pump head if the speed is increased such that the current requirements are now 640 amperes?
A.
400.
B.
800.
C.
1,200.
D.
1,600.
11.
Which of the following KOST ACCURATELY describes the purpose of a demineralized?
A.
To produce an exchange of ions in water.
To rede.ce the conductivity of water without affecting its pH.
B.
the pH of water by reducing the number of positively i
C.
To increase che.rged ions in it.
D.
To increase the conductivity of the water to greater than 1.0 microhms.
1 12.
The term " shutoff head" for a centrifugal pump indicates that it is pumping,at capacity and discharge head.
A.
maximum, minimum B.
maximum, maximum C.
minimum, maximum D.
minimum, minimum
\\
J FORM B 6
w.
a 7 ;..-,
.4.
i y'
s N,
,y-
.;, 7, -
Tube scaling.:in a parallel-flow heat exchanger will.cause heat transfer 13.
[
g e
to decrease because:'
A.
flow through the heat exchanger increases.
- B.
surface.' area of the tubes decreases.
C.
heat transfer coefficient decreases.
D.
' inlet temperature of the cooling fluid increases.
- Air binding 'in a centrifugal pump is an undesirable condition which may 14.
be AVOIDED by:
A.
. throttling-closed the suction valve prior to pump start, then openin5 it again.
opening the discharge valve fully, then starting the pump to allow B.
air to.be forced out.
' opening the pump casing vent valve, while priming the pump, until C.
a.stecdy stream of water appasrs.
D.
openin6 the pump suction vent valve just prior b. starting the
~
pump end then closing it after the pump is running.
.13..
-,A centrifugal pump is started and-the following indications are observed:
Oscillating flow Oscillating discharge pressure oscillating amps i
This indicates that the pump is experiencing:
1
~
motor overload.
A.
B.
cavitation.
C.
pump runout.
D.
shutoff head.
FORH B j
7 I
=.
16.
Please complete the following statement r.o describe the theory of l-operation of
- a. differential pressure level detector using a wet reference leg.
The pressure differential between a height of liquid and the pressure sensed at the bottom of-a tank is proportional to
'the height of liquid in the tank.
j A.
known, directly t
L B.
known, inversely C.
variable, directly D.
variable, inversely air-operated valve (Figure 3), identify the 17.
Using the drawing of an valve position following a loss of electrical power.
A.
Mid-position.
B.
Closed.
C.
As is.
D.
Open.
I FAfLS TO VENT POSfDON I
1 S
Tg AIR SUPPLY ff C:E _9 g
VENT
,e ',
m
'=2 l
FIGURE 3 FORM E 8
=
18.
A generator is operating on the grid synchronized with other generators.
Concerning this generator, which of the following statements is correct?
'A.
. Increasing the excitation decreases the reactive power on the grid.
B.
Increasing the excitation will result in excessive circulating current ' causing inefficient operation and unnecessary heating of the-generator.
C.
Decreasin5 the excitation on the. generator maans decreasing the excitation on all other generators on the grid to balance the megavar loading.
like a D.
Decreasing the excitation will cause the generator to act capacitor and supply positive lagging vars.
19.
A correct statement regarding ther:nocouples is that they:
A.
will indicate-low offscale with an open circuit at the sensing junction.
B.
are more accurate than resistance temperature detectors.
C.
are made" up of two similar metals in contact at one end, called the hot junction.
D.
are based on the following characteristic of metals:
a change in electric.a1 resistance occurs when a change in temperature occurs.
FORM B 9
l' t.
~, -.
. 1
,1 4
Using the drawing of a centrifugal pump characteristic curve in Figure
- 20.
'4, which point represents the pump's shutoff head.
'A.
Poir.t A.
B.
Point B.
1-C.
Point C.
1
)
D.
'Foint D.
Pornt A
/
I Point B PRESSURE g-Point C Por. D
/
.'/
FLOW FIGURE 4 14.
Which of the following describes the REEI method for deener5 zing a i
breaker control circuit?
A.
Breaker in test position.
B.
Breaker ful2y racked out.
C.
Control power fuses removed.
D.
Control switch in pull-to-lock.
MMtM B 10
v,.
4 a,.
k'hich of the following is a IEEE statement regarding parallel-flow and
~
22.
counter-flow heat exchangers?
'A.
A parallel-flow heat 2xchanger 'must maintain a large ' DELTA-T -
throughout its.. length to equal the heat transfer capabilities of a counter-flon heat exchanger.
B.
A parallel-flow heat exchanger. must have more heat transfer area
.to equal the heat transfer capabilities of a cronter-flow heat exchanger, C.
A parallel-flow heat exchanger must heat the cooling water ; to a -
higher temperature than that to which the cooled medium is cooled.
D.
. A parallel-flow heat exchanger must. have a higher cooling-water inlet temperature to equal the heat transfer capabilities of a counter-flow heat exchanger.
e e
FORM B 11
I
i
? b. [,_
g.
,+.
W
.e, 1
REACTOR THFmtY 23 :.
Moderator temperature' coefficient (MTC) is' defined as the change in core reactivity per deBree change in:
A.
coolant temperature.
B.
reactor vessel temperature.
C.
cladding temperature.
D.
fuel'. temperature.
24.
The magnitude of decay heat generation is determined primarily by:
.- (choose. ene )
.]
A.
Core age B.
Power history C.
Final power at shutdown D.
Temperature of reactor coolant
'23.
1Jith K,ff - 0.985, how much reactivity must be added to make the reactor
~'
critical?
1 l
.A.
1.48%-
K/K.
B.
1.50%
K/K.
C.
1,524 K/K.
D.
1.54%
'K/K.
1 FORM B 12 l=L-_-_---_______
o
j
-26.
A reactor is operating at a power level of 120 watts. A control rod is inserted, which results in a stable negative 80-second period. Which of the following is the BEST estimate of the reactor power level two minutes after rod insertion?
l A.
27 watts.
B.
32 vatts.
i C.
49 watts.
D.
54 watts.
27.
Which one of the following conditions vill initially result in a positive startup rate when the reactor is at power?
A.
Increase in turbine leading.
B.
Unintentional boration.
J l
C.
Turbine runback.
I D.
Accidental closure of a main steam isolation valve.
28.
When does the power decrease rate initially stabilize at negative one-third decade per minute following a reactor trip?
When decay gamma heating starts adding negative reactivity.
A.
When the long-lived delayed neutron precursors have decayed away.
B.
C.
When the installed neutron source contribution to the total ner. tron flux becomes significant.
When the short-lived delayed neutron precursors have decayed away.
D.
29.
The reactor is critical at 10,000 cps when a S/G PORV (atmospheric relief valve) f!tils shuc.
Assuming BOL conditions, no rod motion, and no reactor trip, choose the one answer below that best describes the values of Tave and nuclear power for the resulting new steady state.
(POAH - point of adding heat.)
i Final Tave greater than initial Tave, final power at POAH.
A.
Final Tave greater than initial Tave, final power above POAH.
l B.
C.
Final Tave less than initial Tave, final power at POAH.
D.
Final Tave less than initial Tave, final power above POAH, IURM B 13
[. s 3<
1, m,
c.
30 '.
Which one of the following statements concerning the power defect - is correct?
A.
The power defect necessitates the use of a ramped Tave program to-maintain an adequate Reactor Coolant System'subcooling margin.
B.
The power defect increases the rod height requirements necessary to maintain the' desired shutdown margin following'a reactor trip.
C.
Because of the higher boron concentration, the power defect is.
~
more negative at the beginning of core life.
D.
The power defect causes control rods to be withdrawn as reactor power is decreased.
31.
In which of the following conditions is the moderator temperature -
coefficient most negative?
A.
BOL, high temperature.
B.
BOL, low temperature.
C.
EOL,' high temperature.
D.
EOL, low temperature.
32.
Which one of the following plant parameter changes will result in an
-increase in shutdown margin for a shutdown reactor? Assume end of life.
A.
RCS boron concentration is increased by 100 ppm.
B.
One control rod (CEA) is fully withdrawn for a test.
C.
Xenon has decayed for 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> following shutdown.
D.
RCS is cooled down by 300 degrees. F.
33.
Shutdown margin is the actual amount of reactivity:
A.
inserted by burnable poisons at beginning of life.
B.
due to dissolved boron in the RCS.
C.
by which the reactor is suberitical.
D.
which would be inserted by shutdown bank rods.
I FORM B 14 i
g 1
'B t
'I
~s,
- s 34 If a reactor core with a neutron source is exactly critical at 1000 CPS
.in the source range, over the next few minutes the count rate should:
A.
remain constant.
l
'~
B.
inercase linearly.
j i
.C.
increase geometrically.
D.
increase exponentially.
35.
Consider the following information for performing a reactor startup l
(S/U) to full pewer:
ia.
The process began five hours after a trip from full power.
equilibrium conditions.
A 2.0%/ min ramp was ised rather than a 0.St/ min ramp.
Ihus, the xenon dip would occur and the magnitude of the' dip would be A.
sooner larger B.
sooner smaller C.
later la'rger D.
later smaller-36.
.Which.one of the following expresses the relationship between differential rod worth (DRW) and integral rod worth (IRW)?
A.
DRV is the aree.under the IRW curve at that location.
B.
DRW is the slope of the IRW curve at that location.
C.
DRW is the IRW at that loc ation.
D.
DRV is the square root of the IRW at that location.
FORM B 15
e 4 '
THERMODYNAMICS i'
l l
' 37.
' An adequate subcooling margin during a loss-of-coolant accident (LOCA) is the most direct indication that is being maintained.
1 A.
steam generator water level t
f B.
. pressure level C.
core cooling D.
suberiticality l-l 38.
k'hich. one of the statements - below is CORRECT if the power range instruments have been adjusted to 100%
based on a calculated calorimetric?
If the feed water temperature used in the caloristetric calculation A.
was higher than actual feedwater temperature, actual power will be less the indicated power.
B.
If the reactor coolant pump heat input used in the calcrimetrie calculation is omitted, actual power will be less than indicated power.
C.
If the steam flow used in the calorimetric calculation was lower than actual steam flow, actual power will be less than indicated power.
'D.
'If the steam pressure used in the calorimetric calculation is lower than actual steam pressure, actual power will be less than indicated power.
through a throttling process in a main steam header to 39.
As steam goes atmospheric leak, in which of the following parameters will there be an increase?
4 A.
Enthalpy.
B.
Pressure.
C.
Specific Volume.
D.
Temperature.
PORK B 16
" f-, g*'
- ,Q
' ' '. =...
n.
- 1, 4D.
Operating-with. which of the following conditions is ThMT EFFECTIVE in preventirg brittle fracture'in the ECS7 Operating within. prescribed.heatup and cooldown rate. limitations.
A.
B.
Operating with RCS temperature greater than Nil Ductility-Temperature.
C, Operating with RCS pressure low when RCS temperature' is low.
D.
Operating with a ramped RCS temperature as power level varies.
41.
Fast neutron ' irradiation adversely affects the reactor pressure vessel primarily by causing:
A.
metal embrittlement.
B.
brittle' fracture.
C.
thermal gradients.
D.
pressurized thermal shock.
42.
Which one of the following reactor coolant system'(RCS) parameters has the LE&EI effect on margin to departure from nucleate boiling (DNB)?
Consider each separately.
A.
pressurizer level.
"E..
Local power density.
1 C.
Cold leg temperature.
D.
Coolant flow rate.
1 FORM B 17 i
j
._=___:.-____--.
10 r
~
Pow does critical heat J flux vary from the bottom'to the top of the 43.
. reactor.: core during normal full pover operation?
A.
Decreases continuously.
B.
Decreases then increases.
C.
Increases continuously.
D.
Increases then decreases.
44 The pressurizer power-operated relief valve has stuck in a partially opened position with the iluid being discharged into the pressurizer
. relief tank.
The pressurizer pressure is 2200 psia and the relief tank pressure.is4 5 psig.
What is the condition of the fluid downstream of the relief valve?
A.
superheated steam.
.B.
subcooled liquid.
C.
dry saturated steam.
D.
wet vapor.
45.
Reactor Power is increased sufficiently to cause steam blanketing of several fuel rods. This condition is being caused by:
'A.
departure from nucleata boiling.
B.
subcooled nucleate boiling.
C.
saturated nucleate boiling.
D.
onset of nucleate boiling.
FORM 5 18 I
ar__-----____________--
k,
(.
. * ~ * -
46; Which of'the.following'is HQI an indication of cavitation?
A.
-Fluctuating discharge pressure.
B.
Pump vibration.
C.
Pump overheating.
D.,
High discharge pressure.
4 7..
As compared to saturated nucleate ' boiling (bulk boiling), subcooled nucleate boiling:
A.
occurs. to a greater extent in the pressurizer and steam generators.
5.
requires fewer BTU /lbm to convert reactor coolant to steam r.t a givet. temperature.
C.
occurs less during normal plant operation.
D.
results in a lower convective heat transfer coefficient.
48.
Civen the folfowin5 RCS parameters, determine the RCS subcooling margin.
RCS pressure '- 22335 psig.
RCS hot leg temperature - 610' F.
A.
25' F, 302 psi.
B.
31' F, 433 psi.
C.
38' F, 505 psi.
D.
43' F, 588 psi.
l l
l 1
NB 19 1
______.__-_____.i._i._.._..____m_..m__. _. _ _ _ _ _ _
/OTy
~
. Placing' two pumps ' in. parallel' alignment versus a single pump will. result 49 l'
in:
l.
A.
a large increase in system head and the same flow rate.
B.
a small increase,in system head'and a large increase in flow race.
C.
the same. system head and a small increase in flow rate.
J D.
a decrease in system head and a large increase in flow rate.
rapid. cooldown of the RCS in 50.
Pressurized Thermal Shock (PTS) is a combination with:
A.
high reactor power.
B.
low pressurizer level.
C.
high RCS pressure.
D.
lov RCS flow.
i j
l FORM B 20 1
i
t l
PRESSURIZED WATER REACTOR FORM A QUESTION ANSWER QUESTION ANSWER NUMBER NUMBER 1
C 12 B
2 A
13 A
3 3
14 B
4 D
15 B wM S
C 16 B
6 B
17 C
7 B
18 D
8 C
19 A
9 C
20 D
10 B
21 B
11 C
22 C
QUESTION ANSWER QUESTION ANSWER NUMBER NUMBER 23 C
30 C
24 A
31 B
25 D
32 B
26 A
33 A
27 C
34 B
28 A
35 A
29 D
36 A
QUESTION ANSWER QUESTION ANSWER NUMBER NUMBER 37 3
44 C
38 A
45 A
39 A
45 D
40 C
47 B
41 D
48 D
42 D
49 D
43 A
50 C
0 o',.,
PRESSURIZED WATER REACTOR FORM B QUESTION ANSWER QUESTION ANSWER NUMBER NUMBER 1
C 12 C
2 C
13 C
3 D
14 C
a
.B 15 B
5 B
16 B
6 B
17 B
7 B
18 B o, A 8
D 19 A
9 C
20 A
10 D
21 C
11 A
22 B
QUESTION ANSWER QUESTION ANSWER NUMBER NUMBER 23 A
30 B
24 B
31 C
25 C
32 A
26 A
33 C
27 A
34 A
28 D
35 A
29 D
36 B
QUESTION ANSWER QUESTION ANSWER NUMBER NUMBER 37 C
44 D
38 B
45 A
l 39 C
46 D
40 D
47 D
41 A
48 D
42 A
49 B
l 43 A
50 C
1 ll' l
,m.wm-,#-.
yo, r
5
- 4,
,4 S i.1 e 3
ENCLOSURE 2 l
COPY OF VOLUNTARY PARTICFANT BACKGROUND INFORMATION FORM GENERIC FUNDAMENTALS EXAMINATION SECTION (GFES)
I ENCLOSURE 2 1
1.
s t
PI1ET TEST PARTICIPANTS' BACKGROUND INFORMATION FORM 4
Name Student ID I
Reactor Type Form of Exam (Circle One):
PWR BL'R Completed (Circle one): A B
1 On this form, we ask you to provide some background Information about yourself.
Please note that your participation is strictly voluntary. The information you provide will be used tc determine Wh6ther or not scores on the Fundamentals Examination serve as useful indicators of operator training program experience and/or background.
This request was approved by the Office of Management and Budget under clearance number 3150-0090.
Clearance number 3150-0090 expires on Nov 30, 1989. Comments on burden and duplication may be directed to the Office of Management and Budget, Reports Management, Room 3208, New Executive Office B1dg., Washington, D.C. 20503.
If you have any questions about this form, please contact Mr. David Lange at NRC Headquarters (phone 301-492-3172).
Please mail this form, along with the Examination Feedback Questionnaire, to the address provided on Pege 4.
The following questions ask for information about your education, train-ing, and job experience.
Please read each question and answer by circline the one rer.ponse that describes you best or filling in the blanks Where indicated.
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I l Continued Next Page m__m_-_____
9 9
EDUCATION
.l.
k'ha t is your highest level of education?
High School GED a.
b.
High School graduate c.
' Attended Vocational-Technical school-d.
Graduated from a Vocational-Technical school e.
Some college course work f.
Graduate from a two-year college program 6
Graduate from a four year college program h.
Some graduate course work i.
Completed a graduate program.
2.,
If you completed college (2-or 4-year program), please identify your major program, a.
Nuclear Engineering b.
Other Engineering (please specify)
Physical Sciences (please specify) c.
d.
Mathematics and Computer Sciences Other (please specify) e.
3.
If you completed college, please indicate when you graduated.
Month Year 4
Have you taken college course (s) in nuclear energy?
(Do not include the licensed operator training program when answering this question.)
a.
Yes If yes, indicate the number of courses:
b.
No I Continued Next Page l
MIL 1TARY TRAINING EXPERIENCE t
5.
Please indicate if you have served in a branch of the U.S. military, Does not apply, did not serve in a branch of the military.
a.
b.
Army c.
Air Force d.
Marine Corps e.
Navy i
f.
Coast Guard l
l 6.
If you served in the Navy, did you work in the Nuclear Propulsion Program?
a.
Yes If yes, indicate how long you served:
Years Months b.
No 7.
If you served in the U.S Navy Nuclear Propulsion Procram, please answer questions A and B below.
A.
Indicate the highest position held in the nuclear propulsion program.
Propulsion Plant Watch Officer l
a.
l b.
Engineering Watch Supervisor l
c.
Engine Room Supervisor d.
Reactor Operator e.
Chief, Reactor Watch f.
Engineering Officer of Watch g.
Propulsion Plant Watch Supervisor h.
Other (please specify)
B.
Indicate the time period in which you served in the position identified in Item A above.
From:
Month Year To:
Month Year l Continued Next Page
LICENSED OPERATOR TRAINING PROGRAM EXPERIEMCE B.
Please answer questions A, B, C, and D about the licensed operator training program.
A.
Are you currently enrolled in the licensed operator program?
a.
Yes b.
No.
I have already completed the program, B.
If you are currentiv enrolled in the licensed operator course, please specify how much of the program you have completed to date.
weeks out of ____ veeks for the total training program.
C.
If you have already coroleted the training program, please indicate the date that you completed it.
Month Year 9.
Below, please answer questions about specific licensed operator training courses that you have completed.
A.
Have you completed a course in Reactor Theory?
a.
Yes Please indicate the date completed:
Month Year b.
No B.
Have you completed a course in Components?
a.
Yes Please indicate the date completed:
Month Year b.
No C.
Have you conpleted a course in Thermodynamics?
a.
Yes Please indicate the date completed:
Month Year b.
No D.
If you plan to begin the training program, please indicate when:
Month Year Continued Next Page
JOB EXPERIENCE
~
- 4+
10.
What is your present job?
a.
Non-licensed / auxiliary / equipment operacor b.
Reactor operator c.
Senior reactor operator d.
Shift technical advisor (STA) e.
Shift supervisor f.
Other (please specify) 11.
How long have you or did you work as a non-licensed / auxiliary / equipment operator?
a.
Months Years b.
Does not apply, have never worked as a non-licensed / auxiliary / equipment operator.
12.
How long haie you spent in your present job? Please answer this question e'. m if it is the same as answer #11 above.
Months Years 13.
What is the total time you have worked in a commercial nuclear power plant?
Months Years Thank you for taking the time to complete this form. Please mail this, along with the Examination Feedback Questionnaire to:
David J. Lar.ge U.S. NRC Mail Stop OWFN 10-D 18 Washington, DC 20555
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L.,
a s
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4 4
I ENCLOSURE 3 l
COPY OF VOLUNTARY PARTICPANT EXAMINATION FEEDBACK FORM GENERIC FUNDAMENTALS EXAMINATION SECTION (GFES)
I ENCLOSURE 3
- x Ja
.VOWNTARY FUNDAMENTALS EXAMINATION FEEDBACK QUESTIONNAIRE p
Participant's Form Name:
Student ID Reactor Type Form of Examination (Circle One):
PWR BWR completed; (Circle One)
A.
B INSTRUCTIONS The-Fundamentals Examination contains 22 questions related to fpmoonents, 14 related to Reactor Theory, and 14 related to Thermodynamics.
On this feedback form, you are asked to evaluate the examination questions in each of these three areas and to answer some general questions about the examination.
It should take you about 30 to 45 winutes to complete the feedback form.. Please refer to the copy of the Fundamentals Examination included in your packet of test matet!als to complete the feer 2%ack form. Your specific feedback is greatly appreciated. -Please rerun this form, along with the Background Information. Form, to the address premfged on page 7.
Please evaluate each of the examination questions as shown in the following example:
Question Single Item Familiar With Very Very Clearly Correct Number Content?
Easy Average Difficult Stated?
Response?
If No, I
l l
Yes/No Reason 1 2 _3 4 5 6 7 Yes/No Yes/No hNo Yes@
1 Yes $ @ b, c 1 2 3 4 5 6 7 In this example, the examinee evaluated question number 1 as follows:
He was not familiar with the test content (No) because it was not covered in the training program (Reason a).
He rattd the item as difficult (6).
The question is clearly stated (Yes).
The question does not have a single correct response (No).
Explanations of each of these categories are provided on the following page. Continued Next Page I
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A t
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f
. VOLUNTARY FUNDAMENTALS EXAMINATION FEEDBACK QUESTZONAIRE.
Participant's Form c.-
Familiar with Content? Answer YES if you were. familiar with the question-content. 'If your.were not familiar with the content, please.tell us the Reason why, using the following codes:
a) it was not covered in your training program.
b) question content is not relevant for your facility, c)
.you simply did not recall-the information at the time you took the examination.
'Ouestion Difficulty. Use the following definitions to' rate the difficulty of each question on a 1 through 7 scale:
Verv Easv:
A question that can be answered correctly by someone who has npqr completed the fundamentals portion of.the training program.
Average:
A question that is not too easy, but not too difficult.
I very Difficult:
A question that cannot be answer correctly by someone who has completed the fundamentals portion of the training program.
Question clear 1v stated? If an item is clearly stated, circle Yes.
If it is unclear or difficult to understand, circle No.
Sinele Correct Resnonse? If there is png and only one correct answer, circle Yes for that question.
If there is no clear correct answer, or if more than one response appears correct, circle No.
The form for your individual question evaluations begins on the next page, followed by the general que -ions about the examination. Continued Next Page
VOLUNTARY FUNDAMENTALS' EXAMINATION FEEDBACK QUESTIONNAIRE
~..
Participant's Form EVALUATIONS OF EXAMINATION OUESTIONS Question Single Item.
Familiar With Very Very-Clearly
-Correct c
Number Content?
Easy Average Difficult Stated?
Response?
If No, i
l l.
Yes/No-Reason 1 2 3 4 5 6 7 Yes/No Yes/No-1-
Yes/No a, b, c 1
'2 3 4 5 6 7 Yes/No Yes/No 2
Yes/No a,b.c 1 2 3 4 5 6 7
.Yes/No Yes/No 3'
Yes/No e, b, c
.1 2 3 4 5 6 7 Yes/No Yes/No 4
Yes/No a, b, c 1 2 3.4.5 6 7 Yes/No Yes/No
-5 Yes/No a, b, c 1 2 3 4 5 6 7 Yes/No Yes/No 6
Yes/No a, b, c
- 1. 2 3 4 5 6 7
-Yes/No Yes/No 7
Yes/No a, b, c 1 2 3 4 5 6 7 Yes/No Yes/No 8
Yes/No a, b, c 1 2 3 4 5 6 7 Yes/No-Yes/No 9
Yes/No a, b, c 1-2 3 4 5 6 7
'Yes/No Yes/No 10-Yes/No-a, b, c 1 2 34 5 6 7 Yes/No Yes/No 11 Yes/No a, b, c 1 2 3 4 5
- 6. 7 Yes/No Yes/No 12 Yes/No a, b, c 1 2 34 5 6.7 Yes/No Yes/Ne
'13 Yes/No a, b, e 1 2 3 4 5 6 7'
Yes/No Yes/No 14 Yes/No a,b,c 1 2 3 4 5 6 7 Yes/No Yes/No 15 Yes/No a,'b, c
1 2 3 4 5 6 7 Yes/No Yes/No-16 Yes/No a, b, c 1 2 3 4 5 6 7 Yes/No Yes/No 17 Yes/No a, b, c 1 2 3 4 5 6 7 Yes/No Yes/No 18 Yes/No a, b, c 1 2 3 4 5 6 7 Yes/No-Yes/No 19 Yes/No a, b, c 1 2 3 4 5 6 7 Yes/No Yes/No.
20 Yes/No a, b, c 1 2 3 4 5 6 7 Yes/No Yes/No 21 Yes/No a, b, c 1 2 3 4 5 6 7 Yes/No Yes/No 22 Yes/No a, b, e 1 2 3 4 5 6 7 Yes/No Yes/No 23 Yes/No a, b, c 1 2 3 4 5 6 7 Yes/No Yes/No 24 Yes/No a, b, c 1 23 4 5 6 7 Yes/No YesfNo
(
25 Yes/No a, b, c 1 2 3 4 5 6 7 Yes/No Yes/No 26 Yes/No a, b, c 1 2 3 4 5 6 7 Yes/No Yes/No
) Continued Next Page
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VOLUNTARY FUNDAMENTALS EXAMINATION FEEDBACK QUESTIONNAIRE Participant's Form j
j EVALUATIONS OF EXAMINATION OUESTIONS i
l Question Single Item Familiar With Very Very Clearly Correct Number Content?
Easy Average Difficult Stated?
Response?
If No, l
l l
Yes/No Reason 1 2 3 4 5 6 7 Yes/No Yes/No 1
I l
l 27 Yes/No a, b, c 1 2 3 4 5 6 7 Yes/No Yes/No i
28 Yes/No a, b, c 1 2 3 4 5 6 7 Yes/No Yes/No 29 Yes/No a, b, c 1 2 3 4 5 6 7 Yes/No Yes/No q
30 Yes/No a,b,c 1 2 3 4 5 6 7 Yes/No Yes/No 4
31 Yes/No a, b, c 1 2 3 4 5 6 7 Yes/No Yes/No i
32 Yes/No a, b, c 1 2 3 4 5 6 7 Yes/No Yes/No I
f 33 Yes/No a, b, c 1 2 3 4 5 6 7 Yes/No Yes/No
]
34 Yes/No a,b,c 1 2 3 4 5 6 7 Yes/No Yes/No j
f 35 Yes/No a, b, c 1 2 3 4 5 6 7 Yes/No Yes/No 36 Yes/No a,b,c 1 2 3 4 5 6 7 Yes/No Yes/No i
37 Yes/No a, b, c 1 2 3 4 5 6 7 Yes/No Yes/No 1
38 Yes/No a, b, c 1 2 3 4 5 6 7 Yes/No Yes/No j
1 39 Yes/No a,b,c 1 2 3 4 5 6 7 Yes/No Yes/No j
40 Yes/No a, b, c 1 2 3 4 5 6 7 Yes/No Yes/No 41 Yos/No a, b, c 1 2 3 4 5 6 7 Yes/No Yes/No 42 Yes/No a,b,c 1 2 3 4 5 6 7 Yes/No Yes/No j
i 43 Yes/No a, b, c 1 2 3 4 5 6 7 Yes/No Yes/No 44 Yes/No a, b, c 1 2 3 4 5 6 7 Yes/No Yes/No 45 Yes/No a, b, c 1 2 3 4 5 6 7 Yes/No Yes/No
)
46 Yes/No a, b, c 1 2 3 4 5 6 7 Yes/No Yes/No 47 Yes/No a,b,c 1 2 3 4 5 6 7 Yes/No Yes/No 48 Yes/No a, b, c 1 2 3 4 5 6 7 Yes/No Yes/No l
49 Yes/No a, b, c 1 2 3 4 5 6 7 Yes/No Yes/No i
50 Yes/No a, b, c 1 2 3 4 5 6 7 Yes/No Yes/No
)
4-Continued Next Page
,s VOLUNTARY FUNDAMENTALS EXAMINATION FEEDBACK QUESTIONNAIRE Participant's Form i
CENERAL OUESTIONS ABOUT THE FUNDAMENTALS EXAMINATION i
In this section, we ask you to answer' specific questions ibout each of the three sections in the examination (Components, Reactor Theory, and Thermo-dynamics) and some general questions about the examination.
For each statement appearing below, please indicate your response by circling Yes or No.
If you want to provide comments about your responses to these items, please write them in the space below each item. You can also provide additional comments about the examination in the last section.
Components Ouestions (Items 1 throuch 22)
Yes No 1.
Do the 22 examination questions represent a good measure of
(
basic Component Knowledge?
Yes No 2.
Do the 22 examination questions comprehensively sample Components material presented in your training program?
Reactor Theory Oufstions (Items 23 throuch 36)
Yes No 3.
Do the 14 examination questions represent a good measure of basic Reactor Theory Knowledge?
Yes No 4 Do the 14 examination questions comprehensively sample Reactor Theory material presented in your training program?
Thermodynamics Ouestions (Items 37 throuth 50) l Yes No 5.
Do the 14 examination questions represent a good measure of basic Thermodynamics Knowledge?
Yes No 6.
Do the 14 examination questions comprehensively sample Thermo-dynamics material presented in your training program?
j i
General Ouestions About the Fundamentals Examination i
Yes No 7.
Is it reasonable to expect an individual with satisfactory knowledge of the subject areas to complete the Fundamentals Examination in two hours or less?
i Yes No 8.
Should more items be added to this examination to ensure l
comprehensive coverage? Continued Next Page
)
7, VOLUNTARY FUNDAMENTALS EXAMINATION FEEDBACK QUESTIONNAIRE Participant's Form
{
j GENERAL OUESTIONS ABOUT THE FUNDAMENTALS EXAMINATION (Continued) f l
Yes No 9.
Can these knowledge areas be comprehensively tested with fewer 1
items?
Yes No 10.
Do you believe that it is necessary for someone to have
]
completed all or part of the training program to obtain a score l
of 70% or higher on this examination?
Yes No 11.
Do you think non-licensed operators currently participating in the operator training program need to study to obtain a score of 70% or higher on the examination?
Yes No 12.
Vould you recommend that a passing score on this examination be required for all non-licensed operators prior to receiving an NRC license?
Yes No 13.
In general, is this examination too difficult?
(Difficult is defined as containing many items that cannot be answered correctly by someone who has completed the fundamentals portion of the training program.)
i Yes No 14.
In general, is this examination too easy?
(Easy is defined as containing many items that can be answered correctly by someone who has not completed the fundamentals portion of the training program.)
Yes No 15.
Is che percentage of items for the three sections appropriate for this examination (i.e. Components - 44%, Reactor Theory -
28%, and Thermodynamics - 28%)?
Yes No 16.
Does this examination measure the knowledge required to successfully completc the Components, Reactor Theory, and Thermodynamics sections of the operator training program?
Yes No 17.
Was the material covered in this examination presented early in your training program.?
Yes No 18.
In general, do the scores on this examination represent good indicators of how well an individual will perform on the job as a licensed operator?
Yes No 19.
Do you believe that your examination score represents your knowledge of the three areas?
! Continued Next Page
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J VOLUNTARY FUNDAMENTALS EXAMINATION FEEDBACK QUESTIONNAIRE Participant's Form t
General Comments If you have additional comments that you would like to make about the Fundamentals Examination, please provide them below.
1 Thank you for your input.
Please return this questionnaire, along with the Background Information Form, to:
David J. Lange U.S. NRC l
Mail Stop OWFN 10 D-18 Washington, DC 20555 l
__s-_ _ _
a-t E
,,4
)
l ENCLOSURE 4 j
- 4 COPY OF VOLUNTARY TRAINING DEPARTMENT EXAMINATION FEEDEACK FORM GENERIC FUNDAMENTALS EXAMINATION.SECTION (GFES) i i
s Eh3LOSURE 4
I' tf
. VOLUNTARY FUNDAMENTALS EXAMINATION FEEDBACK QUESTIONNAIRE
'I n...
'l Training Department Personnel Form
)
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)
4 j
,+
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l Name:
Student ID l
l
' Reactor Type Form of Examination
{
(Circle One):
PWR BWR reviewed: (Circle One)
A B
j i
INSTRUCTIONS
{
l The Fundamentals Examination contains 22 questions related to Comoonents, 14 related to Reactor Theory, and 14 related to Thermodynamics. On this feedback form, you are asked to evaluate the. examination questions in each of these three areas and to answer some general questions about the examination.
It i'
should take you about 30 to 45 minutes to complete the feedback form. Please refer to the copy of the Fundamentals Examination included in your packet of test materials to complete the feedback form. Your specific feedback is greatly appreciated.
Please return this form, along with the Background Information Form, to the address provided on page 7.
i I
Please evaluate each of the examination questions as shown in the example I
below.
As a trainer or examiner,.we would like you to consider how relevant each question is for non-licensed operators carticioatinc in the operator licensine trainine crocram.
I Question Single Item Familiar With Very Very Clearly Correct Number Content?
Easy Average Difficult Stated?
Response?
If No, l
l l
Yes/No Reason 1 2 3 4 5 6 7 Yes/No Yes/No 1
Yes/No a,b,c 1 2 3 4 5 6 7 Ye s/IE, Yes/No In this example, the trainer evaluated question number 1 as follows:
Non-licensed operators would not be familiar with the test content (No),
because it was not covered in the training program (Reason a),
J The item is rated as difficult (6).
The question is clearly stated (Yes).
+
The question does not have a single correct response (No).
Explanations of each of these categories are provided on the following page. Continued Next Page
VOLUNTARY FUNDAMENTALS EXAMINATION FEEDBACK QUEST 20NNAIRE Training Department Personnel Form i
'amiliar with Content? Answer YES if non-licensed operators participating in j
F I
the operator licensing training program would be familiar with the question content.
If you answer E2, that non-licensed operators would not be familiar with the content, please tell us the Reason why, using the followin5 codes:
a) it was not covered in your training program, b) question content is not relevant for your facility.
Question Difficulty. Use the following definitions to rate the difficulty of each question on a 1 through 7 scale:
Very Easv:
A question that can be answered correctly by someone who has n21 completed the fundamentals portion of the training program.
Averare:
A question that is not too easy, but not too difficult.
Very Difficult:
A question that cannot be answer correctly by someone who has completed the fundamentals portion of the training program.
Question Clearly Stated? If an item is clearly stated, circle Yes.
If it is unclear or difficult to understand, circle No.
Single Correct Response? If there is one and only one correct answer, circle Yes for that question.
If there is no clear correct answer, or if more than ene response appears correct, circle No.
The form for your individual question evaluations begins on the next page, followed by the general questions about the examination.
{
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l l
1 Continued Next Page l
j
,e VOLUNTARY FUNDAMENTALS EXAMINATION FEEDBACK QUESTIONNAIRE Training Department Personnel Form 7.
EVALUATIONS OF EXAMINATION OUESTIONS Question Single Item Familiar With Very Very Clearly Correct Number Content?
Easy Average Difficult Stated?
Response?
If No,
[
l l
Yes/No Reason 1 2 3 4 5 6 7 Yes/No Yes/No 1
Yes/Ne a,b,c 1 2 3 4 5 6 7 Yes/No Yes/No 2
Yes/No a,b,c 1 2 3 4 5 6 7 Yes/No Yes/No 3
Yes/No a, b, c 1 2 3 4 5 6 7 Yes/No Yes/No 4
Yes/No a,b,c 1 2 3 4 5 6 7 Yes/No Yes/No 5
Yes/No e, b, c 1 2 3 4 5 6 7 Yes/No Yes/No 6
Yes/No a,
b, c 1 2 3 4 5 6 7 Yes/No Yes/No 7
Yes/No a, b, c 1 2 3 4 5 6 7 Yes/No Yes/No 8
Yes/No a,b,c 1 2 3 4 5 6 7 Yes/No Yes/No 9
Yes/No a, b, c 1 2 3 4 5 6 7 Yes/No Yes/No 10 Yes/No a, b, c 1 2 3 4 5 6 7 Yes/No Yes/No 11 Yes/No a,b,c 2 2 3 4 5 6 7 Yes/No Yes/No 12 Yes/No a,b,c 1 2 3 4 5 6 7 Yes/No Yes/No 13 Yes/No a, b, c 1 2 3 4 5 6 7 Yes/No Yes/No 14 Yes/No a, b, c 1 2 3 4 5 6 7 Yes/No Yes/No 15 Yes/No a, b, c 1 2 3 4 5 6 7 Yes/No Yer/No 16 Yes/No a, b, c 1 2 3 4 5 o 7 Yes/No Yes/No 17 Yes/No a,b,c 1 2 3 4 5 6 7 Yes/No Yes/No 18 Yes/No a, b, e 1 2 3 4 5 6 7 Yes/No Yes/No 19 Yes/No a, b, e 1 2 3 4 5 6 7 Yes/No Yes/No 20 Yes/No a, b, e 1 2 3 4 5 6 7 Yes/No Yes/No 21 Yes/No a,b,c 1 2 3 4 5 6 7 Yes/No Yes/No 22 Yes/No a, b, c 1 2 3 4 5 6 7 Yes/No Yes/No l
23 Yes/No a, b, e 1 2 3 4 5 6 7 Yes/No Yes/No 24 Yes/No a,b,c 1 2 3 4 5 6 7 Yes/No Yes/No 1
25 Yes/No a, b, c 1 2 3 4 5 6 7 Yes/No Yes/No
{
26 Yes/No a,b,c 1 2 3 4 5 6 7 Yes/No Yes/No j
l 1 Continued Next Page
Ir VOLUNTARY F')MDAMENTALS EXAMINATION FEEDBACK QUESTIONNAIRE
' Training Department Personnal Form EVALUATIONS OF EXAMINATION OUEST12EE t
l Question Single i
f Item Familiar With Very Very Clearly Correct Number Content?
Easy Average Difficult Stated?
Response?
l If No, l
l l
Yes/No Reason 1 2 3 4 5 6 7 Yes/No Yes/No 27 Yes/No a, b, c 1 2 3 4 5 6 7 Yes/No Yes/No 28 Yes/No a, b, c 1 2 3 4 5 6 7 Yes/No Yes/No 29 Yes/No a, b, c 1 2 3 4 5 6 7 Yes/No Yes/No 30 Yes/No a,b,c 1 2 3 4 5 6 7 Yes/No Yes/No 31 Yes/No a, b, c 1 2 3 4 5 6 7 Yes/No Yes/No 32 Yes/No a, b, c 1 2 3 4 5 6 7 Yes/No Yes/No 33 Yes/No a, b, c 1 2 3 4 5 6 7 Yes/No Yes/No 34 Yes/No a, b, c 1 2 3 4 5 6 7 Yes/No Yes/No 35 Yes/No a, b, c 1 2 3 4 5 6 7 Yes/No Yes/No 36 Yes/No a, b, c 1 2 3 4 5 6 7 Yes/No Yes/No 37 Yes/No a,b,c 1 2 3 4 5 6 7 Yes/No Yes/No 38 Yes/No a,b,c 1 2 3 4 5 6 7 Yes/No Yes/No 39 Yes/No a, b, c 1 2 3 4 5 6 7 Yes/No Yes/No 40 Yes/No a, b, c 1 2 3 4 5 6 7 Yes/No Yes/No 41 Yes/No a, b, c 1 2 3 4 5 6 7 Yes/No Yes/No 42 Yes/No c, b, c 1 2 3 4 5 6 7 Yes/No Yes/No 43 Yes/No a, b, c 1 2 3 4 5 6 7 Yes/No Yes/No 44 Yes/No a,b,c 1 2 3 4 5 6 7 Yes/No Yes/No 45 Yes/No a, b, c 1 2 3 4 5 6 7 Yes/No Yes/No 46 Yes/No a, b, c 1 2 3 4 5 6 7 Yes/No Yes/No 47 Yes/No a, b, c 1 2 3 4 5 6 7 Yes/No Yes/No 48 Yes/No a, b, c 1 2 3 4 5 6 7 Yes/No Yes/No 49 Yes/No a, b, c 1 2 3
'4 5 6 7 Yes/No Yes/No 50 Yes/No a, b, c 1 2 3 4 5 6 7 Yes/No Yes/No Continued Next Page
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. VOLUNTARY. FUNDAMENTALS EXAMINATION FEEDBACK QUESTIONNAIRE.
s-I' Training Department Personnel Form GENERAL OUEST10NS ABOUT THE FUNDAMENTALS EXAMINATION In this section, we-ask you to answer specific questions about each of the three sections in the examination (Components, Reactor Theory, and Thermo-dynamics) and some general questions about the examination.
'Some of the following questions assume that you have detailed information about the Operator Licensing Training Program.
If that is not true, please
~
write "Do Not Know" for those questions.
For each statement appearing below, please: indicate your response by circling Yes or No.
If you want to provide comments about your responses to these.
items, please " rite them in the space below each item. -You can also provide additional cotaents about the examination in the last section.
Comoonents Ouestions-(Items 1 throuch 22)
Yes No 1.
Do the 22. examination questions represent a good measure of basic Component Knowledge?
Yes No 2.
Do.the 22 examination questions comprehensively sample
' Components material presented in your training program?
Reactor Theorv Questions (Items 23 throuch 361 Yes No 3.
Do the 14 examination questions represent a good measure of basic Reactor Theory Knowledge?
Yes ' No. 4.
Do the 14 examination questions comprehensively sample R,2ctor Theory material presented in your training program?
Thermodynamics Ouestions (Items 37 through $0)
Yes No 5.
Do the 14 examination questions represent a good measure of basic Thermodynamics Knowledge?-
Yes No 6.
Do the 14 examination questions comprehensively sample Thermo-dynamics material presented in your training program? Continued Next Page
3 VOLUNTARY FUNDAMENTALS EXAMINATION FEEDBACK QUESTIONNAIRE Training Department Personnel Form I
General Ouestions About the Fundamentals Examination i
Yes No 7.
Is it reasonable to expect an individual with satisfactory knowledge cf the subject areas to complete the Fundamentals j
Examination in two hours or less?
Yes No 8.
Should more items be added to this examination to ensure
)
comprehensive coverage?
Yes No 9.
Can these knowledge areas be comprehensively tested with fewer items?
Yes No 10.
Do you believe that it is necessary for someone to have completed all or part of the training program to obtain a score of 70% or higher on this examination?
Yes No 11.
Do you think non-licensed operators currently participating in j
the operator training program need to study to obtain a score i
of 706 or higher on the examination?
Yes No 12.
Would you recommend that a passing score on this examination be required for all non-licensed operators prior to receiving an NRC license?
Yes No 13.
In general, is this examination tso difficult?
(Difficult is defined as containing many items that cannot be answered correctly by someone who has completed the fund.smentals portion of the training program.)
Yes No 14 In general, is this examination too easy?
(Easy is defined as containing many items that can be answered correctly by someone who has not completed the fundamentals portion of the training program.)
Yes No 15.
Is the percentage of items for the three sectiors appropriate for this examination (i.e. Components - 44%, Reactor Theory -
28%, and Thermodynamics - 28%)?
Yes No 16.
Does this examination measure the knowledge required to successfully complete the Components, Reactor Thcory, and Thermodynamics sections of the operator training program?
Yes No 17.
Was the material covered in this examination presented early in your training program.?
Yes No 18.
In ganeral, do the scores on this examination represent good indicators of how well an individual will perform on the job as a licensed operator?
Yes No 19.
Do you believe that your examination score represents your knowledge of the three areas? Continued Next Page
y l
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VOLUNTARY FUNDAMENTALS EXAMINATION FEEDBACK ^'!ESTIONAIRE 1
t Participant's Form 1
i General Comments I
I If you have additional comments that you would like to make about the Fundamentals Examination, please provide them below.
i l
l l
l i
)
T 4
1 l
1 l
l l
l Thank you for your input.
Please return this questionnaire to:
1
(
David J. Lange U.S. NRC Mail Stop OWFN 10 D-18
% hington, DC 20555 lL _ _- _--,-_ _
o' 1
B ENCLOSURE 5 COPY Of COVER LETTER FOR REGION FACILITIES i
ENCLOSURE 5 l
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. Docket No.
50-313, 50-314
- Mr. J. n. Levine Arkansas Nuclear One
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Rt. 3, P. O. Box 137G l
Russellville, Arkansas 72801
Dear Mr Levine:
a on June 28, 1989, the NRC administered a Generic Fundamentals Examination
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Section (GFES) of the written licensing examination to employees of your
-facility. Enclosed with this letter are the graded results and answer sheets for these examinations. You are requested to forward these results to the
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examinees along with copies of their answer sheets. A "P" in the column labeled Final Grade indicates a passing grade and an "F" in this column indicates a failing grade for this examination.
Candidates schedaled.to take an NRC adafnistered reactor operator (RO) or senior reactor operator (SRO) written licensing examination prior to October 1,.-1989 may elect to substitute the results of this pilot examination for the first section of the Site-Specific Examination Section (SSES) (siction 1 of the RO written examination or section 4 of the f"^ written examination.
To do
' this, he or she mur.t request a waiver of this ses : ion of the SSES on his or
.her NRC form 398, based on the date he or she passed the GFES.
If no waiver is requested.the candidate vill be reeutred to take the entire SSES.
For candidatec requesting a waiver, the results of the GFES will be totaled with the sections of the SSES to oMaia an overall examination grade. GFES results will count for 25% of the total of an RO licensing examination and 24 % of the-total of an SRO licensing examination..The overall averaged passing grade for an NRC administered licenstng examination is 80%, including the fundamentals section. The passing grade for each individual section including the Fundamentals Section, is 70%.
On October 1, 1989 the NRC will modify the steps to be taken to apply for an RO or su SRO license to operate a PWR or BWR reactor.
Candidates scheduled to take an initical NRC administered RO or SRO written licensing examination on or af.in October 1,1989, will be required to demonstrate proficiency in the material tested by the GFES prior to heing administered the SSES. The applicant will be able to demonstrate this proficiency by having passed either of the two following examinations, listed on the next page, for the reactor p
type for which a license is sought.
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An NRC' administered GTES for PWRs or BWRs.
2.
.An NRC written licensing examination for FWRs or BWRs administered-
'between February 1,1982 and October 1,1989, completion of which resulted in being licensod as a Reactor Operator or Senior Reactor i
Operator.
L flEASE NOTE:
This' requirement. does not include NRC-administered Instructor Certification Examinations or Requalification Examinations.
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The NRC will establish within the. Operator Licensing Examiner Standards (NUREG-1021) eligibility requirements for taking the GFES.
Personnel wishing to register for.the GFES must be. enrolled in a facility-sponsored training prograu, the completion of which will satisfy the eligibility requirements for a Reactor Operator or a Senior Reactor Operator. license.
The passing grade for the.GFES will remain at 70%, but will not be averaged into the SSES grade. The passing score for each section of the SSES will be 70% with an averaged overall score of 80%.
Implementation of the GFES will have no effect on the operating test port.on of the licensing process. ~ Applicants for operator or senior operator-licenses will be required to document successful completion of the GFES.>n their. application, NRC Form 398 (date passed) or document the date he or she passed the fundamentals section of an NRC administered written lia nsing l;
examination administered between February 1, 1982 and October 1, 1989, which-resulted'in the applicant receiving an RO or SRO license.
The NRC'will administer BWR and PWR GFESs three times annually, on the Wednesday of the first full week in February, June and October. The next GFES will be administered Wednesday October 4, 1989, in five regional locations. The NEC will not administer the fundamentals section (Section 1 for an.R0 examination or Section 4 for an SRO examination) in conjunction with the site-specific written examination af ter October 1.,1989, except as negotiated with the NRC regional offices up to tot not beyond November 1, 1989.
In accordance with 10 CFR 2.790 of the Commission's Regulations, a. copy of this letter and enclosures (1) and (2) will be placed in the Public Documents Room. The examination results for individual examinees are exempt from public disclosure, therefore enclosures (5) and (6) will not be placed in NRC's Public Document Room.
In order to continue.to provide a highly reliable fundamentals examination i
section of tha NRC written examination and improve the design of future 3
examinctL*ns,, ce have included with this letter voluntary feedback forms and.
packground information forms for both the participants and the training' per
.inel, at your facility.
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- v This request was approved by the Office of Management and Budget under clearance number 3150-0090.
Clearance 3150-0090 expires November 30, 1989.
Comments on burden and duplication may be directed to the Office of Management and Budget Reports Management, Room 3208, New Executive Office Building, Washington, DC 20503.
Should you have any questions concerning this examination, please contact Mr. Paul Doyle et (301) 492-1047.
Sincerely, Kenneth E. Perkins Jr., Chief Operator Licensing Branch Division of Licensee Performance and Quality Evaluation, NRR, NRC
Enclosures:
1.
Examination Forms *A" and "B" with answers 2.
Copy of Voluntary Background Information Feedback Form for examination participants 3.
Copy of Voluntary Examination Feedback Form for examination participants 4.
Copy of Voluntary Examination Feedback Form for training department personnel 5.
Examination Results Summary for facility (ies) 6.
Copies of participants individual answer sheets 1
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Docket No.
50-285 Mr. K. J. Morris Omaha Public Power District
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1623 Harney Oms.ha, Nebraska 68102-2247
Dear Mr. Morris:
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On June 28, 1989, the NRC administered a Generic Fundamentals Examination Section (CFES) of the written licensing examination to employees of your facility.
Enclosed with this let.ter are the graded results and answer sheets for these examinations. You are roquested to forward these results to the examinees along with copies of their answer sheets. A "P" in the column f
Inbeled Final Grade indicates a passing grade and an "F" in this column indicates a failing grade for this examination.
Candidates scheduled to take an NRC administered reactor operator (RO) or senior reactor operator (SRO) written licensing examination prior to October 1, 1989 may elect to substitute the results of this pilot examination for the first section of the Site-Specific Examination Section (SSES) (section 1 of the RO written examination or section 4 of the SRO written examination.
To do this, he or she must request a waiver of this section of the SSEE on his or her NRC form 398, based on the date he or she passed the GFES.
If no waiver is requested the candidate will be recuired to take the entire SSES. For candidates requesting a waiver, the results of the GFES will be totaled with the sections of the SSES to obtain an overall examination grade. GFES results will count for 25% of the total of an R0 licensing examination and 24 % of the total of an SRO licensing examination. The overall averaged passing grade for an NRC administered licensing examination is 80%, including the fundamentals section. The passing grade for each individual section including the Fundamentals Section, is 70%.
On October 1, 1989 the NRC will modify the steps to be taken to apply for an RO or an SRO license to operate a Pk'R or Bk'R reactor. Candidates scheduled to take an initital NRC administered RO or SRO written licensing examination on or after October 1, 1989, will be required to demonstrate proficiency in the material tested by the GFES prior to being administered the SSES. The applicant will be able to demonstrate this proficiency by having passed either j
of the two following examinations, listed on the next page, for the reactor j
type for which a license is sought.
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50-498, 50-499 Mr. M. A. McBurnett Houston Lighting and Power P. O. Box 1700 Houston, Texas 77001
Dear Mr. McBurnett:
On June 28, 1989, the NRC administered a Generic Fundamentals Examination Section (CFES) of the written licensing examination to employees of your
' facility.
Enclosed with this letter are the graded results and answer sheets for these examinations. You are requested to forward these results to tha examinees along with copies of their answer sheets. A "P" in the column labeled Final Grade indicates a passing grade and an "F" in this column
. indicates a failing grade for this examination.
Candidates scheduled to take an NRC administered reactor operator (RO) or senior reactor operator (SRO) written licensing examination prior to October 1, 1989 may elect to substitute the results of this pilot examination for the first section of the Site-Specific Examination Section (SSES) (section 1 of the RO written examination or section 4 of the SRO written examination. To do this, he or she must request a waiver of this section of the SSES on his or her NRC form 398, based on the date he or she passed the GFES, if no waiver is requested the candidate will be recuired to take the entire SSES. For candidates' requesting a waiver, the results of the CFES vill be totaled with the sections of the SSES to obtain an overall examination grade. CFES results will count for 25% of the total of an RO licensing examination and 24 % of the total of an SRO licensing examination.. The overall averaged passing grade for an NRC administered licensing examination is 80%, includine the fundamentals section. The passing grade for each individual section including the Fundamentals Section, is 70%.
L on October 1, 1989 the NRC will modify the steps to be taken to apply for an RO or an SRO license to operate a PWR or BWR reactor. Candidates scheduled to l
take an initital NRC administered RO or SRO vritten licensing examination on or after October 1, 1989, will be required to demonstrate proficiency in 4'
the material tested by the CFES prior to being administered the SSES. The applicant will be able to demonstrate this proficiency by having passed either of the two following examinations, listed on the next page, for the reactor type for which a license is sought.
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Docket No.
50-445, 50-446 Mr. William J. Cahill TU Electric 400 North Olive Street 1.B 81 Dallas, Texas 75201
Dear Mr..Cahill:
on June 28,1989, the NRC administered a Generic Fundamentals Examination Section (GFES) of the written licensing examination to employees of your facility.
Enclosed with this letter are the graded results and answer sheets for these examinations _ You are requested to forward these.results to the examinees along with copies of their answer sheets. A "P" in the column labeled Final Grade indicates a passing grade and an "F" in this column indicates a failing grade for this examination.
Candidates scheduled to take an NRC administered reactor operator (RO) or senior reactor. operator'(SRO) written licensing examination prior to October _
1, 1989 may elect to substitute the results of this pilot examination for the first section of the Site-Specific Examination Section (SSES) (section 1 of the RO written examination or section 4 of the SRO written examination. To do this, he or.she must request a waiver of this sertion of the SSES on his or her NRC form 398, based on the date he or she. passed the GFES.
If no waiver is requested the candidate will be recuired to take the entire SSES. For candidates requesting a waiver, the results of the GFES will be totaled with the sections of the SSES to obtain an overall examination grade. GFES results will count for 25% of the total of an RO licensing examination and 24 4 of the total.of an SRO licensing examination. The overall averaged passing grade for an NRC administered licensing examination is 804, includine the fundamentals-section. The passing grade for each individual section including the Fundamentals Section, is 70%.
On October 1, 1989 the NRC will modify the steps to be taken to apply for an
. RO or an SRO license to operate a PWR or BWR reactor. Candidates scheduled to take an initital NRC administered RO or 3R0 written licensing examination on or after October 1, 1989, will be required to demonstrate proficiency in the material tested by the GFES prior to being administered the SSES. The applicant will be able to demonstrate this proficiency by having passed either of the two following examinations, listed on the next page, for the reactor type for which a license is sought.
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' Docket No. ~50-482 Mr. Bart D. Withers Wolf Creek Nuclear Operating Corp.
P. O. Box 411 Burlington, KS 66839
Dear Mr. Withers:
On June 28, 1989,- the NRC administered a Generic Fundamentals' Examination Section (CFES) of the, written licensing e.xamination to employees of your facility. Enclosed with this letter are the graded results and answer sheets for these examinations. You are requested to forward these results to the examinees along with copies of their answer sheets. A "P" in the column labeled Final Crade indicates a passing grade and an "F" in this column indicates a failing grade for this examination.
Candidates scheduled to take an NRC administered reactor operator-(RO) or senior. reactor operator (SRO) written licensing examination prior to October 1, 1989 may elect to substitute the results of this pilot examination for the first section of the Site-Specific Examination Section (SSES) (section 1 of the RO written examination or section 4 of the $RO written examination. To do this, he or she must request a waiver of this section of the S9ES on his or her NRC form 398, based on the date he or she passed the CFES.
If no waiver is requested the candidate will be reoufred to take the entire SSES. For candidates requesting a waiver, the results of the CFES will be totaled with the sections of the SSES to obtain an overall examination grade. CFES results will count for 25% of the total of an RO licensing examination and 24 % of the total of an SRO licensing examination. The overall averaged passing grade for an NRC administered licensing examination is 80%, includinc the fundamentals section. The passing grade for each individual section including the Fundamentals Section, is 706.
On October 1, 1989 the NRC will modify the steps to be taken to apply for an RO or an SRO license to operate a PWR or BWR reactor. Candidates scheduled to take an initical NRC administered RO or SRO vritten licensing examination on or after Octobet 1, 1989, will be required to demonstrate proficiency in the material tested by the CFES prior to being administered the SSES. The applicant will be able to demonstrate this proficiency by having' passed either of the two following examinations, listed on the next page, for the reactor type for which a license is sought.
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50-382 l
Mr. Charles Toth, Training Manager WF-3 Generating Station Louisiana Power and Light P. O. Box B K111ona, LA 70066
Dear Mr. Toth:
On June 28, 1989, the NRC administered a Generic Fundamentals Examination Section (GFES) of the written licensing examination to employees of your facility. Enciased with this letter are the Eraded results and answer sheets for these examinations. You are requested to forward thes* results to the examinees along with copies of their answer sheets. A "P".n the column q
labeled Final Grade indicates a passing grade and an "F" in this column indicates a failing grade for this examination.
Candidates scheduled to take an NRC administered reactor operator (RO) or senior reactor operator (SRO) written licensing examination prior to October 1, 1989 may elect to substitute the results of this pilot examination for the first section of the Site-Specific Examination Section (SSES) (section 1 of the RO written examination or section 4 of the SRO written examination. To do this, he or she must request a waiver of this section of the SSES on his or her NRC form 398, based on the date he or she passed the GFES.
If no waiver is requested the candidate will be recuired to take the entire SSES.
For candidates requesting a waiver, the results of the GFES will be totaled with the sections of the SSES to obtain an overall examination grade. GFES results will count for 25% of the total of an RO licensing examination and 24 % of the total of an SRO licensing examination. The overall averaged passing grade for an NRC administered licensing e.xamination is 80%, including the fundamentals section. The passing grade for each individual section including the 3
J Fundamentals Section, is 70%.
On October 1, 1989 the NRC will modify the steps to be taken to apply for an RO or an SRO license to operate a PWR or BWR reactor.
Candidates ncheduled to take an initical FRC administered RO or SRO written licensing examination l
on or after October 1, 1989, will be required to demonstrate proficiency in
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the material tested by the GFES prior to being administered the SSES. The l
arplicant will be able to demonstrate this proficiency by having passed either l
of the two following examinations, listed on the next page, for the reactor j
l type for which a license is sought.
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