ML20247H107
| ML20247H107 | |
| Person / Time | |
|---|---|
| Issue date: | 07/17/1989 |
| From: | Perkins K Office of Nuclear Reactor Regulation |
| To: | Peebles T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| References | |
| NUDOCS 8907280280 | |
| Download: ML20247H107 (87) | |
Text
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UNITED STATES
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g NUCLEAR REGULATORY COMMISSION pp WASHINGTON, D. C. 20555
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JUL 17 198g MEMORANDUM FOR: Thomas Peebles, Chief I
Operations Branch Division of Reactor Safety i
Region II
)
I FROM:
Kenneth E. Perkins, Jr., Chief Operator Licensing Branch i
]
Division of Licensee Performance and Quality Evaluation, NRR
SUBJECT:
RESULTS OF GENERIC FUNDAMENTALS EXAMINATION SECTION (GFES) 3 0F THE WRITTEN LICENSING EXAMINATION FOR REGION 3I i
On June 28, 1989, NRC administered the PWR and BWR Generic Fundamentals Examination Section (GFES) of the NRC written examination to fourteen (14) facilities in your region. Enclosed with this memorandum are the results of the graded examinations for your region, copies of the PWR and PVR 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 examint,ticn results of individual participants are exempt from public disclosure, therefore enclosure (6) will not be placed in NRC's Public Document Room.
For licensee applicants scheduled to take an NRC written examination prior to October 1,1989, the regions are delegated 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 R0 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 an NRC examination on or after October 1,1989, the applicant will be required to provide documentation of 3roficiency in the material 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 writte.n licensing examination or the fundamentals section of an NRC l
administered written licensing examination administered between February 1, 1982 and October 1, 1980, resulting in the applicant receiving an R0 or SR0 license. After Octobe' I, 1989 the GFES results will not be numerically 1 1 i
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avo72eozeo evo717
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l averaged with site-specific sections of the written examination, but will be i
recorded as " passed" or " failed." The remaining two site specific sections of j
the written examination still requires a 70% per section, 80% overall average i
to pass the written examination.
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 NRC will not administer the fundamentals section (Section 1 for an R0 examination or Section 4 for an SRO examination in con;! unction with the i
site-specific written examination after October 1, 1989, except as neontiated
)
with the NRC regional offices up to but not beyond November 1, 1989.
Operator Licensing Branch (OLB) is in the process of issuing an Information Notice to all holders of PWR and BWR operating licenses and construction pemits and all holders of Peactor or Se11or Reactor Operator licenses, describing the implementation of the GFES. OLB is also revising the operator Licensing Examiner Standards (NUREG-1021) to implenent the GFES.
If you have any questions concerning this letter, please contact Dave Lange at FTS 492-3172.
I A
Kenneth E. Perkins, J
, Chief Operator Licensing Branch Division of Licensee Performance and Ouality Evaluation, NRR
Enclosures:
1.
GFES Examinations PWR and BWR (Forms "A":
and "B:) with answert 2.
Copy of Voluntary Background Information Feedback iorm 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 t
eterra
-i.es r
s' 1
Distribution for Memo to region branch chief RE: GFE 6 89 results dated JUL 111989 I
l l
i DISTRIBUTION (w/o Enclosure 6)
(
OLB R/F TCENTP4(FIIEN[
' "NP4PUBLIC DOCUMENT ROOM l
1 Malcolm L. Ernst, RII 4
Albert F. Gibson, RII Chuck Casto, RII Kenneth E. Brockman, RII i
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concurrence: C:\\DW4\\ REGIONAL. DOC
- SEE PREVIOUS CONCURRENCE
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Office: l OLB.:DLPQ l OLB:DLPQ l OLB:DLPQ /
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Name:
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Date:
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ENCLOSURE 1 l'
GENERIC FUNDAMENTALS EXAMINATION SECTION (GFES)
FORMS A AND B ENCLOSURE 1 l
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l-TEST. FORM A L
UNITED' STATES NUCLEAR REGULATORY COMMISSION l'
PRESSURIZED WATER REACTOR CENERIC FUNDAMENTALS EXAMINATION SECTION Please Print:
NAME FACILITY ID NUMBER INSTRUCTIONS TO CANDIDATE Use the ' answer' sheet provided.
Each question has equal point value. The passin5 grades require at least 70% on this part of the written licensing examination.
All' examination papers will be pic.ked 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 28 TOTALS 100 11 work done on this examination is my own.
I have neither given nor received aid.
Candidate's Signature TEST FORM A
. =
1 1 3,
+
1.
NRC RULES AND CUIDELINES FOR THE CENERIC FUNDAMENTALS EXAMINATION During the administration of this examination the following rules apply:
(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.
(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.
(B)
Cheating on the examination will result in the automatic forfeiture of this examination.
Cheating could also result in more severe penalties.
(9)
Restroom trips are limited. Only QEE examinee may leave the room at a 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 statement on the cover sheet indicating that the work is your own and you have not received or been given assistance in completing the examination.
(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 paper used during the examination.
(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.
't Y 4 4
PRESSURIZED WATER REACTOR CENERIC FUNDrWENTAIS EIANINATION 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 always:
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.
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'2.
A' correct statement regarding thermocoup1'es is that they:
A.
Will indicate low offscale with an open circuit at the sensing junction.
B.
are more accurate than resistance temperat'ure 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 engaging 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 rescat the clutch.
D.
fully stroke the valve electrically to ensure that it moves freely
)
with normal motor torque.
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FORM A 1
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Refer to Figure'2 for the following question.
-All, valves ara' identical and'are initia11y'50% open.. The temperature
- at point 7 is-exceeding operating limits, To MBER the temperature at l'
point 7, the operator should adjust valve in the open direction.
A.
A B.
B C.
C D.
D.
FROM TO SYSTEM SYSTEM O
$40*F gp2 9-A >
m 450*F
%b 1
m r w 122'F
-C 250*F e d v
5 90*F COOUNG '
6 WATER
% Ds m
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122*Fqp7 I
ION EXOHANGER FIGURE 2 FORK A 3
y c,
4 p
1
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5.
Tube;scalinglin a' parallel-flow heat. exchanger will cause heat transfer 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, 6.
A centrifugal pump is started and the following indications are l
observed:
l Oscillating flow l
Oscillating discharge pressure Oscillating amps This indicates that the pump is' experiencing:
A.
motor overload.
B.
cavitation.
C.
pump. runout.
D, shutoff head.
I 7.
Closing the output breaker of a three-phase generator onto a deenergized bus can result in:
A.
an overvoltage condition on the bus, i
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.
FURM A 4
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Is 8.
The average ! starting current. for.an alternating current. motor is.
approximately.:
A.
the same as'its normal 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.
9.
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 10.
Please complete the following statement to describe the theory of-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 1
the height of. liquid in the tank.
A.
known, directly I
B.
known, inversely 1
C.
variable., directly D.
variable, inversely
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FORM A l
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11.
Which of the. following describes the AESI method for deenergizing a l
breaker control circuit?
A '.
. Breaker in test position.
.]
B.
Breaker fully racked out.
C.
Control power fuses removed.
4 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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FIGURE 3 l
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Which of. the following MOST ACCURATEIX describes the purpose of - a demineralized?
A.
To produce an exchange of ions in water.
B.
.To reduce the conductivity of water without affecting its'pH.
C.
To increase the pH of water by reducing the number of positively charged ions in it.
D.
To increase the conductivity of the water to greater than 1.0 microhms.
14 When flow from a centrifugal pump is increased by throttling open the discharge valve, AVATIABLE net positive suction head- (NPSH) and REOUIRED NPSH 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 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.
Decreasing the excitation on the generator means decreasing the excitation on all other generators on the grid to balance the negavar loading.
l D.
Decreasing the excitation will cause the generator to act like a i
capacitor and supply positive lagging vars.
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16.
A break in the VARIABLE leg of a wet reference leg differential pressure 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.
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.
low starting amps, remaining at a low equilibrium. running amperage.
C.
high starting amps, decreasing to t lower equilibrium running amperage.
D.
high starting amps, remaining at a high equilibrium running amperage.
18.
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 regardless of actual-breaker position.
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 spring following local tripping of the breaker.
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19.
Using the' drawing of'a centrifugal pump characteristic' curve'in-Figure-4, which point represents the pump's shutoff head.
m.
A..'
Point A.
t B.
Point B.
C.
Point C.
D.
Point-D.
a Pornt A
,/
FRESSUME Point D Point C
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FIGURE 4 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 s;ved is i
increased such that the current requirements are now 640 amperes?
A.
400.
B.
800.
C.
1,200.
5 D.
1,600.
FDRM A i
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4 21.
k'hich of the following is a,'DE!E 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 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.
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 appears.
D.
opening the pump suction vent valve just prior ' to starting the pump and then closing it after the pump is running, i
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REAC1DR THEORY 23.
In which of tne following conditions is the moderator temperature coefficient mest negative?
A.
BOL, high temperature.
B.
BOL, low temperature.
C.
EOL, high temperature.
D.
EOL,.Iow temperature.
24 L'hich 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 dowm 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 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 Tate, 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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FURN A 11 1
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-4 26.
Which one ' of the following conditions will initially result in a positive startup rate when the reactor is at power?
A.
Increase in turbine loading.
g B.
Unintentional'boration.
C.
Turbine runback.
I D.
Accidental closure of a main staan 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.
C.
by which the reactor is suberitical.
D, which would be inserted by shutdown bank rods.
28.
Consider the following information for performing a reactor startup (S/U) to full power; The process began five hours after a trip from full power equilibrium conditions.
A 2.06/ min ramp was used rather than a 0.St/ min ramp.
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 FURN A 12
p.,
4 4
29.
When does the power decrease rate initially stabilize at negative one-third decade per minute following a reactor trip?
L A.
When decay gamma heating starts adding negative reactivity.
B.
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 da.:ayed away.
30.
With Keff - 0.985, how much reactivity must be added to make the reactor i
critical?
A.
1.48%
AK/K.
B.
1.50%
AK/K.
l C.
I'52%
A K/K.
D.
1.54% A K/K.
31.
- Vhich one of the fo11owi'.1g statements concerning the ' power defect is correct?
'A.
The power defect necessitates the use of a ramped Tave progrcL 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.
Becetse of the higher boron concentration, the power defect is more negative at the beginning of core life.
D.
The power defee causn mntrol rods to be t,ithdrawn as reactor power is decreased.
FORK A 13
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32.
The magnitude of decay heat generation is determined primarily by:
(choose one)
A.
l Core. age B.
Power history C.
Final power at shutdown D.
Temperature of reaccor coolant i
33, Moderator temperature coefficient (MTC) is defined as the change in core
]
reactivity per degree change in:
A.
coolant temperature.
B.
reactor vessel temperature, t
1 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)?
A.
DRW is the area 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 location.
.D.
DRW is the square root of the IRW at that location.
FORM A 14 i
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.35.
A reactor is operating at a power level of 120 watts.- A control rod is.
l.
'. inserted, which results in a stable negative 80-second period. Which of I
the following is. the AFJiI estimate of the.' reactor power level two minutes after rod insertion?-
A.
27 watts.
B.
32 watts.
C.
49 watts.
D.'
54 watts.
36.
. If a reactor core wich' a neutron source is exactly critical at 1000 CPS -
in the source range, over the next few minutes the count rate shoold:
A.
remain constant.
B.
' increase linearly.
C.
increase geometrically.
Di increase exponentially.
MMtM A 15
o THERMODYNAMICS 37.
'Thich one of the statements below is CORFJECT if the power range instruments have been adjusted to 100%
based on a calculated calorimetric?
A.
If the feed water temperature used in the calorimetric calculation t
was higher than actual feedwater temperature, actual power will be les *, than indicated power.
h.
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.
38.
lib'.ch one of the following reactor coolant system QCS) parameters has i
t% t g.SI e f fec t or. margin to departure from nucleate boiling (DNB)?
consider each separately.
A.
Pressurizer level.
B.
Local power density.
C.
Cold leg temperature.
D.
Coolant flow rate.
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39.
Reactor Power is increased sufficiently to cause steam blanketing of several fuel rods. This condition is being caused by:
A.
departure from nucleate boiling.
B.
subcooled nucleate boiling, f
C.
saturated nucleate boiling.
D.
onset of nucleate boiling.
)
40.
Pressurized Thermal Shock (PTS) is a rapid cooldown of the RCS in l
combination with:
A.
high reactor power.
B.
low pressurizer level.
C.
high RCS pressure.
D.
low RCS flow.
41.
Given the following 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, FORM A 17 i
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22.
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.
B.
Operating with RCS temperature greater than Nil -Ductility-Temperature.
C.
Operating with RCS pressure low when RCS temperature is low, f
1 D.
Operating with a ramped RCS temperature as power level varies.
43.
Fast neutron irradiation adversely affects the reactor pressure vessel' primarily by causing:
A.
. metal embrittlement.
I i
B.
brittle fracture.
J C.
thermal gradients.
D.
pressurized thernal shocm.
44 An adequato subcooling margin during a loss-of-coolant accident (LDCA) is the most direct indication that is being maintained.
A.
steam generator water level B.
. pressure level C.
core cooling D.
suberiticality l
FORM A 18 J
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.h s_
- 45 How does critical heat flux vary from the bottom to the top of the reactor core during normal' full power operation?
A.
Decreases continuously.
B.
Decreases then increases.
C.
Increases continuously.
D.
Increases then decreases.
46.
As compared to saturated nucleate boiling (bulk boiling),. subcooled nucleate boiling:
A.
occurs' to-a greater. extent in the pressurizer and steam generators.
'B.
requires fewer BTU /lbm to convert reactor coolant to steam at a given temperature.
C.
occurs less during normal plant operation.
D.
results in a lower convective heat. transfer coefficient.
47.
Placing two pumps in parallel alignment versus a singic pump will result in:
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 rate, C.
the same system head and a small increase in flow rate.
D.
a decrease in system head and a large increase in flow rate.
1 FORM A 19
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48.
The pressurizer powet = c;creted relief valve has stuck in a partially opened position with the fluid being discharged into the pressurizer relief tank.
The pressurizer pressure is 2200 psia and the relief tank pressure is 5 psig, k'ha t is the condition of the fluid dcwnstream of the relief valve?
A.
superheated steam.
{
B.
subcooled liquid.
C.
dry saturated steam.
D.
wet vapor.
49.
L'hich of the following is El an indication of cavitation?
A.
Fluctuating discharge pressure.
B.
Pump vibration.
C.
Pump overheating.
D.
High discharge pressure.
50.
As ste m goes through a throttling process in a main sesam header to atmospheric leak, in which of the following pirameters will there be an increase?
A.
Enthalpy.
B.
Pressure.
C.
Specific Volume.
I D.
Temperature.
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,4, TEST FORM B h.F UNITED STATES NUCLEAR REGUIATORY CONNISSION PRESSURIZED WATER REACTOR CENERIC FUNDAMENTALS EIANINATION SECTION Please Print:
NAME FACILITY ID NUMBER INSTRUCTIONS TO CANDIDATE i
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 _
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 22 44 COMPONENTS 1
REACTOR THEORY 23 -
36 28 THERMODYNAMICS 37 -
50 28 TOTALS 100 All work done on this examination is my own.
I have neither given nor received aid.
l Candidate's Signature l
l l
TEST FORM B 1
4 i
l e
NRC RULES AND GUIDELINES FOR THE CFEERIC MJNDAMENTALS EXAMINATION During the administration of this examination the following rules apply:
]
(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.
(3)
Fill in the ID Number you were given at registration.
Three handouts are provided for your use during the examination, an (4) i 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 j
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.
(8)
Cheating on the examination will 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 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 si&n the statement on the cover sheet indicating that the work is your own and you have not received or been given assistance in completing the examination.
(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 paper used during the examination.
(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.
4 1.
PRESSURIZED WATER RREACTOR l
CENERIC FUNDAMENTALS EXAMINATION i
COMPONENTS i
1.
Use. the drawing of a spring-loaded valve (see Figure 1).
Following a j
i 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.
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5 J:l3 c::::::m:3 Spring p
C:::::#
1 li b
7 ll l !
Discharge Qs g
al r
y 9
r
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f System Pressure j
1 FIGURE 1 l
FORh B 1
l
2.
The average starting current for an alternating current motor is
)
approximately:
A.
ths same as its normal 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.
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f IVEM B 2
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3.
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 IDVFJ' the temperature at point 7, the operator should adjust valve in the open direction.
A.
A B.
B C.
C D.
D FROM SYS EM A
r I
540*F 92 A
I 1
~s n
450*F Y
322 F y
- b.
230 F.
L s
90*F COOLING 6
WATER O 5 110'F h
122'F g 7 l
ION EXOHANGER FIGURE 2 FORM B 3
i 1
s;c A break in the VARIABLE leg of a vet 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.
l C.
-remain constant at the actual level.
D.
fluctuate around the actual' level.
5.
Prior to. manually operating a motor operated valve,.it is good practice tc.
stroke the - valve electrically while depressing the manual clutch A.
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 reseat 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:
an overvoltage condition on the bus, A.
l i
an overcurrent condition on the generator if the bus was not fict.t B.
unloaded.
i C.
a reverse power trip of the generator circuit breaker if generator frequency is low.
I D.
a large reactive current in the generator.
FORM B f
I
_ _-= _
7.
When flow from a centrifugal pump is increased by throttling open the disc *aarge valve, AVAIIABLE net positive suction head (NPSH) and REQUIRED NPSH A.
decreases, decreases.
B.
decreases, increases.
C.
increases, increases.
D.
increases, decreases.
8.
Whie's 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 regardless of actual.
' breaker position.
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 shring charging' motor. would not charge spring following local tripping of the breaker.
9.
Ulien starting a centrifugal pump, the response of motor current should be:
A.
low starting amps, increasing to ' a higher equilibrium running amperage.
B.
low statting amps, remaining at. a low equilibrium running' amperage.
C.
hi h starting amps, decreasing to a lower equilibrium running S
amperage.
D.
high starting amps, remaining at a high equilibrium running amperage.
EDItM B 5
4.
1 j
i 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?
I A.
400.
1
)
B.
800.
C.
1,200.
D, 1.600.
11.
Which of the following MOST ACCURATEIX describes the purpose of a demineralized?
A.
To produce an exchange of ions in water.
B.
To reduce the conductivity of water without affecting its pH.
C.
To increase the pH of water by reducing the number of positively charged ions in it.
D.
To increase the conductivity of the water to greater than 1.0 i
microhms.
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 i
D.
minimum, minimum i
EDRM B 6
_m______.__-._-._~
4 a
13.
Tube scaling in a parallel-flow heat exchanger will cause heat transfer 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, i
14 Air binding in a centrifugal pump is an undesirable condition which may be AVOIDED by.:
A.
thrcttling closed the suction valve prior to pump start, then opening it again.
opening the discharge valre fully, then starting the pump to allow B.
air to be forced out.
opening the pump casing vent valys, while priming the pump, until C,
a steady stream of water appears.
D.
opening the pump suction vent valve just prior to starting the pump and then closing it after the pump is runnin5-15.
,A centrifugal pump is started and the following indications are observed:
Oscillating flow Oscillating discharge pressure 1
l Oscillating amps This indicates that the pump is experiencing:
A.
potor overload.
B.
cavitation.
C.
pump runout.
D.
shutoff head.
1 FDRM B I
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L_______.________.
V
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16.
Please complete the following statement to describe the theory of 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.
A.
known, directly B.
known, inversely C.
variable, directly D.
variable, inversely 17.
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.
I A:LS TO VENT PQG1 TION
^1-AIR SUPPLY 6
-:5 __f VENT M
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1 8
I FIGURE 3 I
FORM B 8
1 I
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a N 'q-r c.
4-
- A generator is operating on the grid synchronized with other generators.
18.
Concerning this generator. which of the following statements. is correct?
A.
Increasing the excitation decreases the reactive power on the grid.
B.
Increasin5 the excitation will result in excessive circulating current, causing inefficient operation and unnecessary heating of the generator.
C.
Decreasing the excitation on the, generator means decreasing the excitation on all other generators on the grid to-balance the megavar loading.
j like a D.
Decreasing the excitation will cause the generator to act capacitor and supply positive lagging vars.
19.
A correct statement regarding therm 9 couples 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.
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FultM B 9
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c20.
Using. the drawing of a centrifugal pump characteristic curve in Figure:
- t.
y3 4~, which point represents the pump's shutoff head.
A Point A.~
l~
B.'
Point B.
C.
Point C.
-D.
Point.D.
. Pornt A
/
i Point B PRESSURE Poin' D Point C
/
A_
FLOW FIGURE 4 14.
Which of the following describes the AESI method for deenergizing a breaker control circuit?
A.
Breaker in test position.
q B,
Breaker fully racked out.
C.
Control power fuses removed.
D.
Control critch in pull-to-lock.
i I
FORM B 10 J
'. f.
'22.
Which of 'the following 'is a 'DLUE. statement regarding parallel-flow and counter-flow heat exchangers7-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 temperature than chat to which the cooled medium is cooled.
D, A parallel-flow heat exchanger must have a higher cooling-water it tlet temperature. to' equal the. heat transfer capabilities o f ~ c.-
ecunter-flow heat exchanger.
J 0
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FaitM B 11 i
{is REACTOR THEORY 4
' 23.
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.
h D.
fuel temperature.
24.
The magnitude of decay heat generation' is determined' primarily by:
(choose-one)
A.
Core age-B.
Power history C.
Final power at shutdown D.
Temperature of reactor coolant l
23.
With Kegg 0.985, how auch reactivity. must be added to make the reactor critical?
.A.
1 ;,48 %
K/K.
B.-
1.50%
K/K.
C.
1.52%
K/K.
D.
1.54%
K/K.
PURN B 12 I
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26.
A reactor is operating at a power level or 120 watts.
.A control rod is inserte1, which results in a stable negative 80 second period. Which of the fr.'.owing is the BEST estimate of the reactor power level two minutes nfter rod insertion?
A.-
27 watts.
y
- B.
32 watts.
I C.
49 watts.
D, 54 watts.
27.
Which one of the following conditions will initially result in a positive startup rate when the reactor is at power?
A.
Increase in turbine loading.
B.
Unintentional boration.
C.
Turbine renback.
D.
Accidental clor e re 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.
B.
When the lor 5-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.
j 29.
The reactor is critical at 10,000 cps when a S/G PORV (atmospheric l
relief valve) fails shut.
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.)
A.
Final Tave greater than initial Tave, final power at POAH.
)
l B.
Final Tave greater than initi.nl Tave, final power above POAH.
C.
Final'Tave less than initial Tave, final power at POAH.
i D.
Final Tave less than initial Tave, final power above POAH.
FORM S 13
m j
3 0..
Which one of the following statements co1cerning the power defect is j
correct?
A.
The power defect necessitates the use af a ramped Tave program to maintain an adequate Reactor Coolant Synctem subcooling margin.
B.
The power defect increases the rod height requirements necessary j
to maintain the desired shutdown margin following a reactor trip.
j i
C.
Because of the higher boron concentration, the power defect is j
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?
f 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 ine reased 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.
l D.
RCS is cooled down by 300 degrees F.
33.
Shutdown margin is the actual amount of reactivity:
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.
IVRM B 14
i 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.
B.
increase linearly.
C.
increase geometrically.
D.
increase exponentially.
35.
Consider the following information for performing a reactor startup (S/U) to full power:
The process began five hours after a trip from full power equilibrium conditions, v
A 2.0%/ min ramp was used rather than a 0.5%/ min ramp.
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 36.
Which.one of the following expresses the relationship between differential rod worth (DRW) and integral rod worth (IRW)?
A.
DRW is the area 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 location.
i D.
DRW 1: the square root of the IRW at that location.
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FURN B 15 l
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D.. -
A
.IW BIODYNAMICS 37.
An adequate subcooling margin during a loss-of coolant accident (LOCA) is the most direct indication that is being maintained.
A.
steam generator' water level' B.
pressure level C.
core cooling '
D.
suberiticality 38.
Which one of the. ~ statements below is CORRECT if the ' power range instruments have been adjusted to.100%- based on-a calculated E
. calor hetric?
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.
'If the steam flow lused-in the calorimetric ~ calculation was lower C.
than actual steam flow.. actual power will be lessithan 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.
39, As. 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.
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l 1
Operating with which of the following conditions is LEAST EFFECTIVE in 40.
preventing brittle fracture in the RCS?
Operating within prescribed heatup and cooldown rate limitations.
A.
B.
Operating with RCS temperature greater than Nil Ductility Temperature.
l C.
Operating with RCS pressure low when RCS temperature is low, i
l l
D.
Operating with a ramped RCS temperature as power level varies.
i 41.
Fast neutron irradiation adversely affects the reactor pressure vessel primarily by causing:
A.
metal embrittlement.
B.
brittle fracture.
C.
thermal gradients.
W D.
pressurized thermal shock..
i 42.
Which one of the following reactor coolant system (RCS) parameters has a
the IIAST effect on margin to departure from nucleate boiling (DNB)?
f Consider each separately.
A.
Pressurizer level.
j t
B.
Local power density.
J i
C.
Cold leg temperature, l
J D.
Coolant flow rate.
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I FORM E l
17
a.
.i
- 43.
. How does critical heat flux vary from the bottom to the top of the reactor core during normal full power operation?
A.
Decreases continuously.
LB.
Decreases then increases.
C Increases continuously.
D.
Increases then decreases.
44.
The pressurizer power-operated relief valve has. stuck in a partially j
opened position with the fluid being discharged into the pressurizer relief tanh.
The pressurizer pressure is 2200 psia and the relief; tank pressure is 5 psig.
What is the condition of the fluid downstream of the relief valve?
A.
superheated steam.
B.
subcooled liquid.
C.
dry satureted 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 nucleate boiling.
B.
subcooled nucleate boiling.
C.
saturated nucleate boiling.
D.
onset of nucleate boiling.
FORM B 18 I
.)
46.
Which of the following is EDI an indication of cavitation?
1 A.
Fluctuating discharge pressure.
' B.
Pump vibration.
f C.
Pump overheating.
D.
High discharge pressure, l.
l' 47..
~ As compared to saturated nucleate boiling (bulk ' boiling), subcool'd e
.nuc eate boiling:
l a.
occurs to a
greater. extent in' the pressurizer and steam generators.
B.
requires fewer' BTU /lbm to convert reactor coolant to steam at. a given temperature.
C.
occurs less durinE normal pL.nt operation.
D.
results in a lowsc convective heat transfer coefficient.
'8.
Given the fo1 Towing RCS parameters, determine the RCS subcooling margin.
l RCS pressure - 22335 psig.
l l.
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
I FORM B 19
- a s-49.
Placing two pumps in parallel alignment versus a single pump will~ result l
in:
A.
a'large increase in system head and the same' flow rate.
B.
a small increase in system head and a lar6e increase in flow rate.
C.
the same system head and'a small increase in flow rate.
f D.
- a decrease in system head and a large increase in flow rate.
50.
Pressurized Thermal Shock (PTS) is a rapid cooldown of the RCS in combination with:
A.
high reactor power.
B.
low pressurizer level.
~
C.
high RCS pressure.
D.
low RCS flow.
9 9
4 9
FORM B 20
s PRESSURIZED WATER REACTOR FORM A QUESTION ANSWER QUESTION ANSWER NUMBER NUMBER 1
C 12 B
2 A
13 A
3 B
14 B
4 D
15 B or M 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
i 27 C
34 B
26 A
35 A
29 D
36 A
J QUESTION ANSWER QUESTION ANSWER
]
NUMBER NUMBER 37 B
44 C
38 A
45 A
39 A
46 D
40 C
47 B
41 D
48 D
42 D
49 D
43 A
50 C
9 PRESSURIZED WATER REACTOR FORM B
' QUESTION ANSWER QUESTION ANSWER NUMBER NUMBER 1
C 12 C
2 C
13 C
3 D
14 C
4 B
15 B
5 B
16 B
6 8
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 QUESTIGN ANSWER NUMBER NUMBER 37 C
44 D
38 B
45 A
39 C
46 D
40 D
47 D
{
41 A
48 D
I 42 A
49 B
43 A
50 C
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.c-ENCLOSURE 2 COPY OF VOLUNTARY PARTICPANT BACKGROUND INFORMATION FORM GENERIC FUNDAMENTALS EXAMINATION SECTION (GFES) t I
I h
i ENCLOSURE 2 l
T r
l' L
4 PILOT-TEST PARTICIPANTS' BACKGROUND INFORMATION FORM Name Student ID Reactor Type Form of Exam (Circle One): PWR BL'R Completed (Circle one): A B
l l
On this form, we ask you to provide some background information about yourself.
Pleese note that your participation is strictly voluntary.
The information you provide will be used to determine whether or not scores on the Fundamentals Examination serve as useful indicators of operator training l
program experience and/or background.
l This request was approved by the Office of Mansgement 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 Bldg., Washington, D.C. 20503, I
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 Page 4.
1 The following questions ask for information about your education, train-ing, and job experience.
Please read each question and answer by circline the one response that describes you best or filling in the blanks where indicated.
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EDUCATION 1.
L' hat is your highest level of education?
a.
High School GED 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 g.
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 ide..tify 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.
j Month Year 4
Ha e 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 1
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! Continued Next Page i
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MILITARY TRAINING EXPERIENCE 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 f.
Coast Guard 6.
If you served in the Navy, did you work in the Nuclear Propulsion Program?
l a.
Yes If yes, indicate how long you served:
Years Months b.
No 7.
If you served in the U.S Navy Nuclear Pronulsion Procram, please answer questions A and B below.
A.
Indicate the highest position held in the nuclear propulsion
- program, a.
Propulsion Plant Watch Officer b.
Engineering Watch Supervisor c.
Engine Room Supervisor d.
Reactor Operator j
e.
Chief, Reactor Watch I
f.
Engineering Officer of Watch g.
Propulsion Plant Watch Supervisor h.
Other (please specify) j B.
Indicate the time period in which you served in the position identified in Item A above.
From:
Month Year To:
Month Year l
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-U :
LICENSED OPERATOR TRAINING PROGRAM EXPERIENCE
~
gh,.
~
- k 8.
Plea 6' answer questions A,1B, 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
-weeks for the total training program.
C..
If you have already comnleted 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 Ples;e indicate the date completed:
Month Year b.
No C.
Have you completed a course in 7 thermodynamics?
a.
Yes Please indicate the date completed:
j l
Month Year b.
No D.
If you plan to begin the training program, please indicate j-i I
when:
Month Year
, _ _ _ Continued Next Page f{
e JOB EXPERIENSE 10.
What is your present job?
a.
Non-licensed /auniliary/ equipment operator 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 have you spent in your present job? Please answer this question even 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?
3 Months Years Thank you for taking the time to complete this form.
Please mail this, along with the Examination Feedback Questionnaire to:
David J. Lange U.S. NRC Mail Stop OVFN 10-D 18 Washington, DC 20555 l
1 l
1 1 1
u_-_-_-
-.---_.-----__--,-_7,---,-,_,
y
. 4 ENCLOSURE 3 COPY OF VOLUNTARY PARTICPANT EXAMINATION FEEDBACK FORM GE!!ERIC FUNDAMENTALS EXAMINATION SECTION (GFES) l I
i ENCLOSURE 3 1
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l
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VOLUNTARY FUNDAMENTALS EXAMINATION FEEDBACK QUESTIONNAIRE Participant's Form Name:
Student ID I
Reactor Type Form of Examination (Circle One'):
PWR BWR completed: (Circle One)
A B
i INSTRUCTIONS i
The Fundamentals Examination ;ontains 22 questions related to Components, 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 minutes to couplete 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.
Please evaluate each of the examination questions as shown in the following example:
Question Single Item Familiar With Very Very Clearly Correct Numbe-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 i
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).
1 He rated 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 fol'1owing page.
]
1 1
) Continued Next Page
k l
l VOLUNTARY FUNDAMENTALS EXAMINATION FEEDBACK QUESTIONNAIRE Participant's Form 4
Fariller with Content? Answer YES if you were familiar with the question
)
c ot. tent.
If your were nor familiar with the content, please tell us the En Eqa 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.
Question 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 n21 completed the fundamentals portion of the i
training program.
Ayerage:
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 Clearly Stated? If an item is clearly stated, circle Yes.
If it is unclear or difficult to understand, circle No.
Sinr.le 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 one response appears correct, circle No.
The form fer your individual question evaluations begins on the next page, l
followed by the general questions about the examination. Continued Next Page
,n
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VOLUNTARY FUNDAMENTALS EXAMINATION FEEDBACK QUESTIONNAIRE 1
- 7 Participant's Form EVALUATIONS OF EXAM 1hATION OUESM QHS, 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 'S 6 7 Yes/No Yes/No' 1.
Yes/No a, b, c l'
2 3 4 56 7 Yes/No Yes/Ne 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
iYes/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 3 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 l
l 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 1
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/6o Yes/No 14 Yes/No-a, b, c -
1 2 3 4 5 6 7 Yes/No Yo/No 15 Yes/No a, b, e 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 I
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
)
i 19 Yes/No a, b, c 1 2 3 4 5 6 7 Yes/No Yes/No 20 Yet/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, c 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 1-2 3 4 5 6 7 Yes/No Yes/No 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 Yet,/No Yes/No
.; Continued Next Page
.s
f i
j VOLUNTARY FUNDAMENTALS EXAMINATION FEEDBACK QUESTIONNAIRE Participant's Form EVALUATIONS OF EXAMINATION OUESTIONS l
1 Question Single
{
Item Familiar With Very Very Clearly Correct i
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 l
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27 Yes/No a,b,c 1 2 3 4 5 6 7 Yes/No Yes/No l
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 1
35 Yes/No a,b,c 1 2 3 4 5 6 7 Yes/No Yes/No j
36 Yes/No a, b, e 1 2 3 4 5 6 7 Yes/No Yes/No i
l 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 4;
Yes/No a, b, c 1 2 3 4 5 6 7 Yes/No Yes/No l
42 Yes/No a,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 e,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 a 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 1
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 Yec/No Yes/No j
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)
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1 VOLUNTARY FUNDAMENTALS EXAMINATION FEEDBACK QUESTIONNAIRE Participant's Form GENERAL OUESTIONS ABOUT THE FUNDAMENTALS EXAMINATION In this section, we ark 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, j
j 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.
]
l Components Ouestions (Items 1 throurh 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 Compc.nents material presented in your training program?
Reactor Theory Ouestions (Items 23 throuch 36)
Yes No 3.
Do the 14 examination questions represent a good measure of basic Reactor Theory Knowledge?
1 Yes No 4 Do the 14 examination questions comprabensively sample Reactor f
Theory material presented in your training program?
Thermodynamics Ouestions (Itemt 37 throuch 50)
Yes No 5.
Do the 14 examination questions represent a good measure of
{
basic Thermodynamics Knowledge?
l l
Yes No 6.
Do the 14 examination questions comp.:ehensively sample Thermo-dynamics material presented in your training program?
I general Questions 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?
Yes No 8.
Should nore items be added to this examination to ensure comprehensive coverage?
I 5-Continued Next Page l
l
)
VOLUNTARY FUNDAMENTALS EXAMINATION FEEDBACK QUESTIONNAIRE Participant's Form GENERAL OUESTIONS ABOUT THE FUNDAMENTALS ELIMINATION (Continued)
Yes No 9.
Can these knowledge areas be comprehensively tested with fawer 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-licens*d 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.
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 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.)
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 sections appropriate for inis 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 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.?
l Yes Ne 18.
In general, do the scores on this examination represent good indicators of how well an individual will perform on the job as l
a lfcensed operator?
Ye-No 19.
Do you believe that your examination score represents your knowledge of the three areas?
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l l Continued Next Page
VOLUNTARY. FUNDAMENTALS EXAMINATION FEEDBACK QUESTIONNAIRE Participant's Form General Comments If you have additional comments that you would like to make about the Fundamentals Examination, please provide them below.
l M.4 9
l l
Thank you for your input.
Please return this questionnaire, along with the Background Information Form, to:
David J. Lange U.S. NRC Mail Stop OWFN 10 D-18 Washington, DC 20555 I l
=
n ENCLOSURE 4 COPY OF VOLUNTARY TRAINING DEPARTMENT EXAMINATION FEEDBACK FORM GENERIC FUNDAMENTALS EXAMINATION SECTION (GFES)
ENCLOSURE 4
1 VOLUNTARY FUNDAMENTALS EXAMINATION FEEDBACK QUESTIONNAIRE Training Department Personnel Form Name:
Student !3 Reactor Type Form of Examination (Circle One):
PWR BWR reviewed: (Cir<'te One)
A B
l INSTRUCTIONS j
The Fundamer.tsis Examination contains 22 questions related to components,14 related to Reactor Therrv, 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 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 j
greatly appreciated. Picase return this form, along with the Background Information Form, to the address provided on page 7.
Please evaluate each of the examination questions as shown in the example below. As a trainer or examiner, we would like you to consider how relevant each question is for non-licensed operators narticipatinc in the operator licensing training crorram.
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 Yes/No Yes/No In this example, the trainer evaluated question number 1 as follows:
Non licensed operators would not be familiar with tl'e test content (No),
because it was not covered in the training program (Reason a).
The item is rated as difficult (6).
l The question is clearly stated (Yes).
The question does not have a single correct response (No).
)
l Explanations of each of these categories are provided on the following page. Continued Next Page l-
o VOLUNTARY FUNDAMENTALS EXAMIIVATION FEEDBACK QUESTIONNAIRE Training Department Personnel Form Familiar with Content? Answer YES if non-licensed operators participating in the operator licensing training program would be familiar with the question content.
If you answer D2, that non-licensed operators would not be familiar with the content, please tell us the Reason why, using the following codes:
a) it was not covered in your training program.
4 i
b) question content is not relevant for your facility.
Ouestion Difficulty. Use the following definitions to rate the difficulty of each question on a 1 through 7 scale:
Very Easy:
A question that can be answered correctly by someone vho has n21 completed the fundamentals portion of the i
training progtam.
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.
i i
Single Correct Response? If there is Eng 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 questions about the examination.
l l
l l
\\ Continued Next Page
- [
G.
. VOLUNTARY FUNDAMENTALS EXAMINATION FEEDBACK QUESTIONNAIRE Training Department Personnel Form EVALUATIONS OF EXAMINATION OUESTIONS
~i Question Single.
Item Familiar With Very Very Clearly correct-Number Content?
Easy. Average. Difficult Stated?-
Response?-
If No, j
j.-
l Yes/No Reason 1 2 3 4 5 6 7
-Yes/No Yes/No a
i 1-Yes/No a, b, c 1
2-34 5 6 7 Yes/No
.Yes/No i
g
[{
2 Yes/No a, b, c 4 1 2 3 4 5 6 7 Yes/No Yes/No j
l 3
Yes/No a,b,c 1 2 3 A 5 6 7 Yes/No Yes/No b
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 e, 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' 1
2 3 4 5 6 7 Yes/To Yes/No 12 Yes/No a, b, c 1 2 34 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 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 56 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, c 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 2 3 4 5 6 7 Yes/No Yes/No 25 Yes/No a, b, e 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 i
- =-_
VOLUNTARY FUNDAMENTALS EXAMINATION FEEDBACK QUESTIONNAIRE Training Department Parsonnel Form EVALUATIONS OF EXAMINATION OUESTIONS Question Single Item Familiar With Very Very Clearly Correct Number Content?
Easy Average Difficult Stated?
Response?
If No, l
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 3B 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 Yet,/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 a, 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 f
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 50 Yes/No a, b, c 1 2 3 4 5 6 7 Yes/No Yes/No l
l I Continued Next Page l
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VOLUNTARY FUNDAMENTALS EXAMINATION FEEDBACK QUESTIONNAIRE Training Department-Personnel Form j
CENERAL OUESTIONS 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. LIf 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.
I Components Ouestions (Items 1 throuth 22)
Yes No 1.
Do the 22 examination questions represent a good measure of basic Component Knowledge?
Yes No 2.
Do the 22 examination 4 -stions comprehensively sample Components material presented in your training program?
Feactor Theorv Ouestions (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 throuch 50)
Yes No 5.
Do the 14 examination questions represent a good measure of basic Thermodynamics Knowledge?
Yes No 6.
Do the 14 examinat,lon questions comprehensively sample Thermo-dynamics material presented in your training program?
i l
l' Continued Next Page
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h VOLUNTARY FUNDAMENTALS EXAMINATION FEEDBACK QUESTIONNAIRE
~
Training Department Personnel Form
+
General Ouestions About the Fundamentals Examination Yes No 7.
Is it reasonable to expect an individual with satisfactory knowledge of the subject areas to complete the Fundamen'als 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 the operator training program need to study to obtain a score of 70% 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 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.)
Yes No 14.
In general, is this examination too easy? (Eesy is defined as containin5 many items that can be answered correctly by someone who has D21 completed the fundamentals portion of the training program.)
Yes No 15.
Is the 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 complete 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
VOLUNTARY FUNDAMENTALS EXAMINATION FEEDBACK QUESTIONNAIRE Participant's Form General Comnients If you have additional comments that you would like to make about the l
Fundamentals Examination, please provide them below.
3 l
Thank you for your input.
Please return this questionnaire to:
David J. Lange j
U.S. hTC j
Mail Stop OWFN 10 D-18 Washington, DC 20555 )
"- r '
1(.
i. -
- r i ENCLOSURE 5 COPY OF COVER LETTER FOR REGION FACILITIES i
ENCLOSURE 5
[ i 31
- i iii i i i
37 _ ome
- 4
-4 UNITED STATES i[
y NUCLEAR REGULATORY COMMISSION-q g.
9 E WASHINGTON, D. C. 20555 4 "
\\,
/
Docket No.
50-380, 50-327, 50-328. 50-259, 50-260, 50-296 Mr. C. H. Fox Tennesee Valley Authority SN 157B Lookout Place
' Chattanooga TN 37401
Dear Mr. Fox,
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 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 GRO 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 reouired 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 examination is 80%, 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 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 l
of the two following examinations, listed on the next page, for the reactor l
type for which a license is sought.
l L
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1.
An NRC administered GFES for PWRs or BWRs.
2.
An NRC vritten licensing examination for PWRs or BWRs administered between February 1, 1982 and October 1, 1989, completion of which resulted in being licensed as a Reactor Operator or Senior Reactor Operator.
PLEASE NOTE:
This requirement does not include NRC-administered Instructor Certification Examinations or Requalification Examinations.
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 aust be enrolled in a facility-sponsored training program, 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 portion of the licensing process. Applicants for operator or senior operator licenses will be required to document successful completion of the GFES on their application, NRC Form 398 (date passed) or document the date he or she passed the fundamentals section of an NRC administered written licensing 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 NRC will not administer the fundamentals section (Section 1 for an RO examination or Section 4 for an SRO examination) in conjunction with the site-specific written examination after October 1, 1989, except as negotiated with the NRC regional offices up to but 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 section of the NRC written examination and improve the design of future examinations, we have included with this letter voluntary feedback forms and background information forms for both the participants and the training personnel, at your facility.
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' This request was approved by. the Office of Management.and Budget under clearance-number 13150-0090.' 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 i
Building, Washington, DC
- 20503..
Should you have.any questions concerning this examination, please contact-Mr.-Paul Doyle at (301) 492-1047.
Sincerely, i
Kenneth E. Perkins Jr., Chief '
Operator Licensing Bra.nch Division of Licensee Perfo E nce-and Quality Evaluation, NhR 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 L.
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Docket No.
50-325, 50-324 Mr. John O'Sullivan Brunswick Steam Electric Plant P.O. Box 10429 Southport, NC 28461
Dear Mr. O'Sullivan:
On June 28, 1989, the NRC administered a Generic Fundamentals Examination Section (CFES) of the writt<.n licensin5 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 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) writtes 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 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%, includine the fundamentals section. The passing grcde for each individual section including the Fundamentals Sectfon, 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 initical 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 CFES prior to being administered the SSES.
The applicant will be able to demonstrate this proficiency by having passed either of the wo following examinations, listed on the next page, for the reactor I
type for which a license is sought.
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WASHINGTON, D. C. 20555 Docket No.
50-416. 50-417 Mr. Ted H. Cloninger System Energy Resources P. O. Box 23070 Jackson, Mississippi 39225-3070
Dear Mr. Cloninger:
On June 28, 1989, the NRC administered a Generic Fundamentals Examination Section (GFES) cf 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 s'iong with copies of their answer sheett. 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 licer.cing examination prior to October 1,1989 may elect to substitute the results of this pilot examinati./3 for the first section of the Site-Specific Examination Section (SSES) (sr.ct.on 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 reautred 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%, 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 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 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..50-321, 50-366 Mr. H. C. Nix'
' Georgia Power Company H
P.'O.. Box 439 Baxley, Georgia 31513
Dear Mr. Nix,
i On June' 28, 1969, the NRC administered a Generic Fundamentals Examination Section'(GFES) of the written licensing examination to employees of your I
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 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 reouired 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 NRG administered licensing examination is 80%, 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 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 of the two following examinations, listed on the next page, for the reactor l
type for which a license is sought.
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l Docket No.
50-413, 50 414 Mr. T. o Owen Duke Power Compr.ny Catawba Station-P.O. Box 256 Clover SC 29610
Dear Mr. Owen:
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 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 exartination 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 examination is 80%, includine the fundamentals 3
section. The passing grade for each individual section including the Fundamentals Section, is 70%.
)
s 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 f
take an initical NRC administered RO or SRO vritten licensing examination l
on or after October 1, 1989, will be required to demonstrate proficiency in j
the material tested by the GFES prior to being administered the SSES. The j
applicant will be able to demonstrate this proficiency by having passed either
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of the two following ex minations, listed on the next page, for the reactor type for which a license is sought.
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' Docket'No.
50 338, 50-339 Mr. W. R. Cartwright Virginia Electric and Power Company Richmond, Virginia 23261
Dear Mr. Cartwright,
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 i
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 reouired 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 examination is 80%, including the fundamentals section. The passing grade for each individual section including the Fundamentals Section, is 70%.
.2 On October 1, 1989 the NRC will modify the steps to be taken to apply for an t,
RO or an SRO license to operate a PWR or BWR reactor. Candidates scheduled to L
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 of the two following examinations, listed on the next page, for the reactor type for which a license is sought.
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50-269. 50-270, 50-87 1
Mr. Travis L. Farmer Duke Power Company
.0conee Training Center P.O. Box-1436 Seneca, SC 29679
Dear Mr. Farmer:
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 "F" 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 pacsed 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 examination is 80%, includine the fundamentals section. The passing grade for each individual section including the l
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 FWR or BWR reactor. Candidates scheduled to l
take an initical 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 I
applicant 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 type for which a license is sought.
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50-261 Mr. R. E. Morgan H. B. Robinson Seg Plant P. O. Box 790 Hartsville, South Carolina 29550
Dear Mr. Morgan:
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 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 Igouired 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. 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%, 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 PWR or BWR 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 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.
50-400 l
Mr. A. V. Powell Harris Training Unit P. O. Box 165 New Hill, North Carolina 27562
Dear Mr. Powell:
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 j
examinees along with copies of their answer sheets. A "P" in the column l
labeled Final Grade indicates a passing t,rade 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 q
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 vritten examination. To do this, he or she must request a waiver of this section of the SSES on his or l
f her NRC form 398, based on the date he or she passed the GFES.
If no waiver is requested the candidate will be reautred 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 t.n NRC administered licensing examination is 80%, includine the fundamentals j
rection. 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 take an initical NRC administered RO or SRO written licensing examination on or aftet October 1, 1989, will be required to demonstrate proficiency in j
the material tested by the GFES prior to being administered the SSES.
The i
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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50-395 i
l Mr. O. S. Bradham South. Carolina Electric 6 Cas' Company P. O.: Box 88 4
Jenkinsville, SC.29065 1
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Dear Mr. Bradham,
l i
on June 28, 1989, the NRC administered a Generic Fundamentals Examination
'i Section (GFES) of the written licensing examination to employees cf your facility. Enclosed with this letter are the graded results and answer shents for these examinations. You are requested to forward these reruits to the examinees along with copies of their answer sheets. A "P"
in the column J
1abeled 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
1, 1989 may elect to substitute the resvits of this pilot examination for the first section of the Site-Specific Examination Section (SSES) (section 1 of the RO written examination ot 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 reouired 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.
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%, includinz 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 SRO written licensing examination
.on or after October 1, 1989, will be required to demonstrate proficiency in the material tested by the CFES prior to being admin!stered the SSES. The applicant will be able to demonstrate this proficiency by having passed either of the two followin5 examinations, listed on the next page, for the reactor type for which a license is sought, l
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Docket No.
50-250, 50-251 Mr. W. F. Conway Florida Power and Light 1P. O. Box 14000 Juno Beach,'FL 33408-0420
Dear Mr. Conway:
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 section of the SSES on his or her NRC form 398, based on the date he or she passed the GFES.
If tio waiver is requested the candidate will be reouired 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. 'CFES reruits 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 Fundamental Section, is 70%.
On October 1, 1989 the NRC will modify the steps to be taken to apply for an RO on an SRO license to operate a PWR or B.R reactor. Candidates scheduled to take an initital NRC administered RO or SRO written licensing examination on or afteI October 1, 1989, will be required to demonstrate proficiency in i
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 ne.xt page, for the reactor l
type for which a license is sought.
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Docket No.
50-424, 50-425 l
Mr. W. G. Hairston III 3
40 Inverness Center Parkway P. O. Box 1295 Birmingham, Alabama 35201
Dear :
Mr. Hairston:,
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 reqvasted 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 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 reauired 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. CFES results will count for 25% of the total of an R3 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%, includinn 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 SRO written licensing examination j
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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