ML20247G995
| ML20247G995 | |
| Person / Time | |
|---|---|
| Issue date: | 07/17/1989 |
| From: | Perkins K Office of Nuclear Reactor Regulation |
| To: | Wright G NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| References | |
| NUDOCS 8907280248 | |
| Download: ML20247G995 (92) | |
Text
. _ _ _ _ _ _.
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[o UNITED STATES g
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NUCLEAR REGULATORY COMMISSION y,
- E WASHINGTON, D. C. 20555
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JUL 171989 MEMORANDUM FOR: Geoffrey C. Wright, Chief Operations Branch Division of Reactor Safety Pegion III FROM:
Kenneth E. Perkins, Jr., Chief Operator Licensing Branch Division of Licensee Performance and Quality Evaluation, NRR SUPJECT:
RESULTS OF GENEPIC FUNDAMENTALS EXAMINATION SECTION (GFES) 0F THE WRITTEN LICENSING EXAMINATION FOR REGION III On June 28, 1989, NRC administered the PWR and BWR Generic Fundamentals Examination Section (GFES) of the NRC written examination to seventeen (17) facilities in your region. Enclosed with this memorandum are the results of the graded examinations for your region, copies of the PWR and BWR Examinations as administered (forms a and b) with answers a.1d e copy of the cover letter sent to each of the Facilities in your region.
In accordance with 10 CFR 2.700 of the Commission's Regulations, a copy of this letter with enclosures (1) through (51 will be placed in the Public Document Room. The examination results of individual participants are exempt from public disclosure, therefore enclosure (6) will not be placed in NRC's Public Document 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)oftheexamination). 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 licersing examination.
If an applicant for either an RO or SRO license elects to use the GFES score, it will count for 2F% of the overall reactor operator examination score or 24% of the overall senior operator examination score. A condidate must still obtain an overall minimum score of 80% on his/her licensing examination to pass.
For license applicant.; scheduled to take an NRC examination on or after October 1,1989, the applicant will be required to provide documentation of proficiency in the material tested by the GFES. To do this the applicsnt will be required to submit the date that he or she " passed" either a GFES of the written licensing examination or the fundamentals section of an NRC administered written licensing examination administered between February 1, g fyl'h 1982 and October 1,1989, resulting in the applicant receiving an R0 cr SR0 license. After October 1,1989 the GFES results will not be numerically
).N'Y NRC RLE CENTE n'
8907280248 890717 q\\\\
' r averaged with site-specific sections of the written examination, but will be-recorded as " passed" or " failed." The remaining two site specific sections of the written examination still requires a 70% per section, 80% overall average to pass the written examination.
The NRC will edminister BWR and PWR GFESs three times annually, on the Wednesday of the first full week in February, June and October. The next GFES l
will be administered Wednesday October 4, 1989, in five reoional locations.
l The NRC will not administer the fundamentals section (Section 1 for an RO examination or Section 4 for an SRO examination) ir con.iunction with the site-specific written examination after October 1, 1089, except as negotiated-with the NRC regional offices up to but not beyond November 1,1089.
Operator Licensing Branch (OLP) is in the process of issuing an Information Notice to all holders of PWR and BWR operating licenses and construction permits ard all holders of Reactor or Senior Reactor Operator licenses, describing the implementation of the GFES. OLB is also revising the Operator Licensing Fxaminer Standards (NUREG-1021) to implement the GFES.
If you have any questions concernino this letter, please contact Dave Lange at l
FTS 492-3172.
Qtk6.f Kenneth E. Perkins, Jr., Chief Operator Licensino Branch
}
Division of Licensee Performance and Ouality Evaluation, NRR
Enclosures:
1.
GFES Examinations PWR and BVR (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 l
5.
Copy of Cover Letters for Region facilities 6.
Examination Results for Region facilities L
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Distribution' for Memo to region branch chief RE: GFE 6 89 results dated-v.' '
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NRC=PUBLIC DOCUMENT ROOM A'.
Bert Davis, RIII.
'Hubert J.. Miller,.RIII Thomas-Burdick,:RIII' Michael Jordan, RIII l
l'
. concurrence: C:\\DW4\\RECIONAL. DOC
- SEE PREVIOUS CONCURRENCE Office: i,OLB:DLPQ l OLB:DLPQ l OLB:DLPQ j
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- Date:
1-07/ /89 l 07/ /89 l 07/f1/89 l
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I4 ENCLOSURE 1 GENERIC FUNDAMENTALS EXAMINATION SECTION (GFES)
FORMS A AND B ENCLOSURE 1 fp
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TEST FORM A.
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~-UNITED STATES NUCLEAR REGUIATORY COB 0(ISSION W
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-Lpassing Brades 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.
I SECTION Questions
% OF TOTAL SCORE COMPONENTS 1
22 44 REACTOR THEORY 23 - 36 28 THERMODYNAMICS 50 28 TOTALS' 100 11 work done on this examination is my own.
I have neither given nor received aid.
Candidate's Signature e
TEST FORM A
V
- (
x NRC RULES AND CUIDEI.INES FDR THE CENERIC FUNDAMENTA13 EKANINATION 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 answerr, marked on this sheet.
Fo11cw 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.ider to avoid the appearance or possibility of chesting, avoid all contai i 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 sids - steam table booklets, Handouts and scrap paper used during the examination.
i (12)
After turning in your examination materials, leave the examination area, as defined by the examiner.
If after leaving you are found in j
the examination area while the examination is in progress, your examination may be forfeit.
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PRESSURIZED WATER REACTOR GENERIC FUNDAMENTALS EXAMINATION -
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.
t B.
remain at the previous position, j
C.
go to the fully closed position.
D.
go to the mid-position.
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- = _ - _ _ - -
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2.
.A correct statement regarding t.hermocouples is that they:
l l.-
A.
'will indicate low offscale with an open circuit at the. sensing -
junction.
B.
are more accurate than resistance temperature detectors, i
C.
are made up of two similar. metals 'in cor. tact at one end, called the hot junction.
l l
D.
are based on the following characteristic of metals:
a change in electrical resistance occurs when a change in temperature occurs.
1 1
3.
Prior to manually operating a motor-operated valve, it is good practice to:
i A.
stroke the valve electrically while depressing the manual clutch l
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 reseat the clutch.
D.
fully stroke the valve electrically to ensure that it moves' freely with normal motor torque.
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4 FORM A 2
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V t..
lA j
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- Refer to Figure 2 for the following question.
r All valves are identical and are initially 50% open.. The temperature.
l at point 7 is-exceeding. operating limits. -To IM ER the temperature at
{
point ~ 7.
the operator ' should adj ust salve in - the. open 1
direction,
'f 1
A.
A
~
'B.
B-t-
C.
C' D.
D' FROM SYSTEM SYS EM g -
- i 54D*F (>2 A
3 A /
f%
'450*F Y
,I 122'F C
250*F e d 5
l 80*F COQUNG 6
WATER
% Dj m
110'F 122*F(p7 3
ion ex: HANGER FIGURE 2 FORM A 3
= _ _
4:
4 5.
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.
6.
A centrifugal pump is started and the. following indications are observed:
1 Oscillating flow I
Oscillating discharge pressure Oscillating amps This indicates that the pump is. experiencing:
A.
motor overload.
B.
cavitation.
C.
pump runout.
D.
shutoff head.
7.
Closing the output breaker of a three-phase generator onto a deenergized bus can result in:
A.
an overvoltage condition on the bus.
B.
an overcurrent condition on the generator if the bus was not first unloaded.
C.
a reverse power trip of the generator circuit breaker if generator I
. frequency is low.
D.
a larEe reactive current in the generator.
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FORM A 4
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_ - _ = _ - - - - _ _ _ _ -
o d
a ' ;,
y :.1
's-p 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.
I 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 the height of liquid in the tank.
A.
known, directly B.
known, inversely C.
variable, directly D.
variable, inversely FORM A 5
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11.
Which of the following describes the ESI method for deenergizing a breaker control circuit?
i A.
Breaker in test position.
B.
Breaker fully racked out.
)
i C.
Control power fuses removed.
I D.
Control switch in pull-to lock.
i.
i 1
12.
Using. the drawing of an air-operated valve (Figure 2), identify the i
valve position following a loss of electrical power.
l A.
Mid-position.
B.
Closed.
'I C.
As is.
]
D.
- Open, k
FAILS 70 VENT POSITION N
AIR SUPPLY g
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FORM A 6
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13.
Which of the following MOST ACCURATELY 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 increaced by throttling open the discharge valve, AVAIIABJJ, net positive suction head (NPS11) and REQUIRFD NPSH _
i 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 balanwe the megavar loading.
D.
Decreasing the excitation will cause the generator to act like a capacitor and supply positive lagging vars.
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16.
A break in the yARIABLE leg of a wet reference leg differential pressure type level detector will cause the indicated level to A.
be greate2 than actual level.
)
)
1 B.
be less;than actual' level.
l C.
remain constant at.the actual level.
D.
fluctuate around the actual level.
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17.
When starting a centrift. gal pump, the response of motor current should be:
A.
low starting amps. increasing to a higher equilibrium running amperage.
B.
Iow starting amps,. remaining at a low equilibrium running amperage.
C.
high starting amps, decreasing to a lower equilibrium running amperage D.
high startin5 amps, remaining at a high equilibrima running amperage.
18.
Which of the following results from a loss of circuit breaker control power to a circuit breaker supplying e motor?
A.
Motor ammeter indication would 'be zero regardless of actual
-I breaker position.
B.
Breaker. position would remotely indicate closed regardlesh 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.
FORN A -
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- 19.
Using the-dtawing of'a centrifugal pump characteristic curve in' Figure 4, which point represents the pump's shutoff head.
'A.
' Point A.
B.
Point B.
C.
Point C.-
D.
Point D.
Pornt A
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20.
A pump is operating at 1800 rpm, pump head is 100 psid, and pump current is 10 amperes.
Wat will be the new value of pump _ head if this speed is
, increased such that the current requirements are now 640. amperes?
L A.
400.
B.
800.
C.
1,200.
D.
1,600.
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t 21.
Which of the following is a IEVE 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 heet transfer capabilities of a l
counter-flow heat exchanger.
B.
A parallel-flow heat exchanger must ha.ve more heat transfer area to. equal the heat transfer capabilities of. a counter-flow heat
{
exchanger.
C.
A perMhl-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.
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REACTOR THEORY j
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D23.
In ~which of the following conditions is the moderator. temperature I
coefficient most negative?
A.
BOL, high temperature.
B.
BOL, low temperature.
,.C.
EOL, high temperature.
D.
EOL, low temperature.
24 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.
F.CS boron concentration is increased by 100 ppm.
B.
One control rod (CD.) is fully withdrawn for a test.
C.
Xenon has decayed for 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> following shutdown.
.D.
RCS is cooled down by 300 degrees F.
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.)
A.
Final Tave greater than initial Tave, final power at POAH.
B.
Final Tave greater than initial Tave, final power above POAH.
j C.
Final Tave less than initial Tave, final power at POAH.
D.
Final Te.ve less than initial Tave, final power above POAH.
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".3 i-t 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.
B.
Unintentional boration.
.C.
Turbine runback.
D.
Accidental closure of a main steam isolation valve.
1 27.
Shutdown margin is the a.mtual amount of reactivity:
A.
inserted by burnable poisons at be5 nning of life, i
B due'to dissolved boron in the RCS.
C.
by which the reactor is suberitical.
D.
whic5 would be inserted by shutdown bank rods.
28.
Consider the following information for performing a reactor startup (S/U) ra full power:
The process began five hours after.a trip from fv11 power equilibrium conditions.
A 2.06/mi.n 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 ID3M A 12 4
EL 29.
When does the power decrease rate initially stabilize at negative one-third decade per minute following a reactor trip?
A.
- When decay gamma heating starts adding negative reactivity.
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 decayed away.
30.
With Keff - 0.985, how much reactivity must be added to make the teactor critical?
A.
1.48%
A KjT,
B.
1.50%
A K/K.
C.
1.52%
A K/K.
D.
1.54% A K/K.
l 31.
Which one of the following statementa concerning the power defect is correct?
A.
The power defect necessitates the use of a ramped Tave program to l:
maintain an adequate Reactor Coolant System subcooling margin.
B.
The power defect increases the rod height requirements necessery to maintain the desired shutdown margin following a reactor trip.
C.
Becau.se of the higher boron concentration, the power defect is more negative at the beginning of core life.
D.
The power defect causes control rods to be withdrawn as reactor power is decreased.
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FORM A i
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32.
.'The magnitude -of. decay heat generation is ' determined primarily ' by:
(cho.ose one).
?A.
. Core. age 10 Power history
'~
C.
Final power at shutdown D.
Temperature of reactor coolant
- 33.
Moderator temperature coefficient (MTC) is defined as the change in core q
reactivity per degree change in:
A.
coolant temperature.
B.
reactor vessel temperature.
C.
cladding temperature.
D.
fuel temperreure.
34 Which one. of the-following expresses the relationship between differential rod worth (DRW) and integral rod worth (IRW)?
A.
DRV is the area under th9 IRW curve at that location.
B.
DRV is the slope of the IRW curve at that location.
C.
DRW is the~IRW.at that location.
j D.
DRW is the square root of the IRW at that location.
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35.
-ALreactor is operating at's power level of.120 watts.
A' control' rod is-
. inserted,-whichtresults in a stable negative 80-second period. Which of--
. the following is ' the ~ ' AESI. estimate of the ' rsactor power level : two-
~ minutes after rod insertion?
.f 1:
A.
27 watts.
[
B.
- 32. watts..
C..
49 watts.
.o D.
54 watts.
-)
36.
If a react.or 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.
q
.r FORM A 15 i
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._m__m_.a__mm.a_.__-___---- - - - = - - - - - - -
-m------
- - -- - ^ - ------ -"-^-- - - - - - - - ^ - - - - - - ^ - - " - - " ' - " " " ' - - - - "
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'jg' THERMODYNAMICS 3
3 7..
k'hich one ' of the statements below is CORRECT if the power range f
instruments have been ' adj usted to 1006 based on
'a ' calculated J
calorimetric?
{
c A.-
If the. feed water temperature used in the calorimetric calculation'
.j was higher than actual feedwater temperature, actual power will be.
l less than indicated power,
]
B.
If th6 reactor coolant pump heat input used in the calorimetric calculation. is caitted, actual power will be less thkn 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.
L'hich ons of the following reector coolant system (RCS) ' parameters has the LEAST effect on margin to departure ' from nucleate boiling - (DNB)?
l Consider each separately.
1 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:
]
l' A.
' departure from nucleate boilingc
'B.
subcooled nucleate boiling.
l C.
saturated nucleate boiling.
l D,
onset of nucleate boiling.
.40.
Pressurized Thermal Sh96 (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.
' 41 '.
Given the'following'RCS parameters, determine the RCS subcooling margin.
RCS pressure - 22335 psig.
RCE hot 1eg temperature - 610' F.
~
- A.
25' F, 302 psi.
B.
31' F, 433 psi.
C.
.38' F, 505 psi.
D.
43' F, 588 pui.
FORM A 17
__- _. _: = _ _ _ - _
-4.
c,
+-
42.
Operating with which of the following conditions is LEAST EFF"CTIVE in preventing brittle fracture in the RCS?
A.
Operating within prescribed heatup and cooldown rate limitations.
B.
Operating with RCS temperature greater than Nil Duetility Temperature.
C.
Operating with RCS pressure low when RCS temperature is low.
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.
B.
brittle fracture.
C.
thermal gradients.
D.
pressurized thermal shock.
44 An adequate subcooling margin during a loss-of-coolant accident (LOCA) is the most direct indication that is being maintained.
A.
steam Senerator water level B.
pressure level C.
core cooling D.
suberiticality l
l l
FORN A 13 h
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e 45.
How does critical -- heat flux vary from ' the bottom to the top of the reacto'r 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.
occars to a
greater. extent in the pressurizer and eam 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 single 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.
FORM A 19
l T
y w
h %-
-48; The pressuri::er power-operated ' 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.
What is, the ' condition of the ' fluid downstream of i-the'.. relief valve?.
A.
superheated steam.
'B.
subcooled liquid.
'C.
dry saturated steam.
D.
wet. vapor.
E-
- 49..
Which of the following is EQI an' indication of cavitation?
A.
Fluctuating discharge pressure.
p B.
Pump vibration.
C.
Pump. overheating.
D.
High discharge pressure.
50.
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.
FORN A 20 o-
TEST FORK B UNITED STATES NUCLEAR REGUIATORY Cole (ISSION 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 passing grades requirs 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.
i 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 j
received aid.
4.
i Candidate's Signature TEST FORM B i
m__
m_.__.___._____._
j
NRC RULES AND GUIDELINES FOR THE GENERIC 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 f.acility 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.
I (7)
Any questions ebout an item on the examination should be directed to i
the examiner only.
(B)
Cheating on the examination will result in the automatic forfeiture cf this examination.
Cheating could also result in more severe penalties.
(9)
Restroom trips are limited.,0nly QHE examinee may leave the room at a time.
In order to avoid the appearance or possibility of cheating, avoid all contact'vith 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 l
the examination area while the examination is in progress, your examit.ation may be forfeit, f
l i
l
PRESSURIZED UATER REEACTTR CENERIC FUNDAMElrLUS EIAKINATION C0KPONENTS 1.
Use the drawing of a spring-loaded valve (see Figure 1).
Following a loss of system pressure, the position of this valve will:
A.
go to the fully open position.
B.
remair, at the previous position.
C.
go to the fully closed position.
D.
go to the mid-position.
Yoke- :!'
]
N, Spring tN p
N#
O N
l oischarge l
V' n
yv r
p q
r i
System Pressure FIGURE 1 FORM B 1
u__z____..
I" 4
2.
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 cerrent.
D.
ten to fifteen times its normal running current.
a 1
FORM B 2
' s.:
I ; ' 9.;
Refer to Figure 2 for the following question.
b 3.
All valves are identical and are-initially 50% open. The temperature at point. 7 is exceeding operating-limits.
To ]ggE the temperature at point 7 the. operator should adjuat valve in the open
' direction.
A.
A B.
B-i C.
C l
D.
D FROM
- TO SYSTEM 3y EM O
640*F g2 A
3 A >
~
f%
w 460*F 1
N/
m.
< ~
w 122*F b*
2wF. 4 e
5 CCOUN3 6
WATER
%Ds
.m
^
ser swr g1 lON EXtHANGTR FIGURE 2 PORM B 3
/
I.
a-A break in the. VARIABLE leg of a wet reference-leg differential pressure 4.
type level detector will cause the indicated level to:
-A.
be greater than actual level.
B.
be less than actual level.
L C.
remain constant at the actual leval.
D.
fluctuate around the actual level.
5.
Prior to manually operating a motor-operated valve, it is good practice to:
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 ressat the clutch.
C.
fully stroke the valve electrically to ensure that it moves freely D.
with normal ~ motor torque.
Closing the output breaker of a three-phase generator onto a deenergized C..
1 bus'can result in:
an overvoltage condition on the bus.
A.
an overcurrent condition on the generator if the bus was not first B.
unloaded.
a reverse power trip of the generator circuit breaker if generator C.
frequency is low.
D.
a large ' reactive current in the gene 14 tor.
l 1
J l
l FORK B 4
--_,,u__.__
e -
w-When flow from a centrifugal pump is increased by throttling open the 7..
L discharge valve, AVATIABLE net positive suction head (NPSH) and REOUIRED NPSH
'A.
decreases,' decreases.
B.
decreases, increases.
.C.
increases, increases.
D.
increases, decreases.
8.
- Which of the following results from a loss of circuit breaker control power to a circuit br,eaker 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.
should 9.
.Wh'en starting a centrifugal pump, the response of motor current be:
A.
low starting amps, increasing to a higher equilibrium running.
amperage.
B.
Iow starting amps, remaining at a low equilibrium running amperage.
C.
high starting amps, decreasing to a ' lower equilibrium running ampera6e-high starting amps, remaining at a high equilibrium running amperage.
1 1
4 1
FORM B 5
i
,e, n.m. _-
' c t
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 currer.t requirements are now 640 amperes?
A.
400.
B.
300.
C.
1,200.
D.
1,600.
11.
Which of the following MOST ACCURATELY 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 cf the water to greatei-than 1.0 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 D.
minimum, minimum l'
FORM B 6
4
_____m__________
y
..s. -
3 p
f 13.
' Tube scaling in a parallel-flow heat exchanger will causa heat transfer
.to decrease because:
A.
flow through the heat exchanger increases.
l B.
. surface area of the tubes decreases.
C.
heat transfer coefficient decreases.
~
D.
' inlet temperature of the cooling fluid increases.
l.
14 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.
opening the pump casing vent valve, 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 running.
i 15.
,A centrifugal pump is started and the following. indications -are observed:
Oscillating flow Oscillating discharge pressure Oscillating amps This indicates that the pump'is experier_cing:
A.
motor overload.
B.
cavitation.
C.
pump runout.
I D.
shutoff head.
I 1
)
7
L..
' i 1
k
i 16.
Please complete the following statement to describe the theory of operation of a differential pressure level detector using a wet 3
reference leg.
The' pressure differential between.a height of liquM and the '
pressure sensed at the.. bottom of 'a tank is
-proportional to
-the height of liquid in the tank.
S A.
known, directly
\\
B.
known, inversely
)
C.
variable, directly i
D.
variable, inversely air-operated valve (Figure ' 3), identify the 17.
Using the' drawing of an valve position following a loss of electrical power.
A.
Mid position ~.
B.
Closed.
1 C.
.As is.
D.
Open.
F A!LS TO VENT POSITION S
AIR SUPPLY g
j [
VENT g
- . 3 h=eh FIGURE 3 MMtM B 8
e_
.\\.
4
.... ~
18 '.
A generator is operating on the grid synchronized with other generators.
Concerning this generator, which of the following statements is correct?
A.
Increasing the excitation decreases the reactive power on the-grid.
B.
Increasing. the excitation will result in excessive circulating causing inefficient operation and unnecessary heating of
- current, 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.
like a.
D.
Decreasing the excitation will 'cause the generator to act i
capacitor and,upply positive lag & ng vars.
19.
A correct statement regarding thermocouple is that they:
A.
will indicate low offscale with an open circuit at the sensing junction.
B.
are more accurate than resistance temperature detectors.
made" up of two siinilar metals in contact at one end, called C.
are the hot junction.
D.
are based on the following characteristic of metals:
a change in electrical resistance occurs when a change in temperature occurs.
FORM B 9
g.,.
(
N:
.j i
4 Q; pri-
. Using the drawing of. a : centrifugal pump characteristic curve in Figure.
l
~
- 20.
4, which. point' represents the' pump's shutoff head.
1
-A.
Point A.
1 B.,
Point B.
C.
Point C.
D.
Point D.
Potnt A
/-
1
-i
[
PomtB PRESSURE Point O PomtD
/d
/._
T FLOW FIGURE 4 i
14.
Which of the following describes the AESI method for deenergizing a breaker control circuit?
A.
Breaker in test position.
B.
Breaker fully racked out.
C.
Control power fuses removed.
D.
Control switch in pull-to-lock.
i
)
i l
l i
(
FORM B 10 1
i i
p
'22.
Which of the following is a IB]IE statement regarding parallel-flow and counter-flow heat exchangers?
l heat exchanger must' maintain a.large DELTA-T
- A.
A parallel-flow throughout its length to equal the. heat transfer capabilities of a counter-flow heat exchanger.
A' parallel-flow heat exchanger must have more hast transfer area B.
to : equal the heat transfer capabilities of a counter-flow heat exchanger.
A parallel-flow heat exchanger must heat the cooling water to a
C.
higher temperature than that to which the cooled medium is cooled.
D.
A parallel flow heat exc. hanger must have a higher cooling-wa ter inlet temperature to equal the heat transfer capabilities of a counter-flow heat exchanger.
O FORK B 11
l.
(
s
~,-
REAC1Dit THE0ELY 23 Moderator temperature coefficient (MTC) is defined as the change in core react!vity per degree change in:
A.
. coolant temperature.
B.
reactor vessel temperature.
C.
cladding temperature.
D.
fuel temperature.
24.
The. magnitude of decay heat generation is determined primarily by:
(choose one)
A.
Core age B.
Power history C.
Final power at shutdown D.
Temperature of reactor coolant 23.
With Keff - 0.985, how much 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.
FORM B 12
-3. - ' -
-g.
, w:
fg p
I 26.
A reactor.is operating at a power level.of 120 watts. A control rod is inserted,. which results in' a stable negative 80-second period. Which of the following. is the BEST estimate of the reactor power level two j
I l.
minutes after rod insertion?
f I
s
'A.
27 watts.
l B.
32 watts.
ir
.I l.
C.
49 watts.
~(
L D.
54 watts.
27.
Which one of the following conditions will initially result in a positive startup rate when the teactor is at power?
A.
Increase in turbine loading.
B.
Unintentional boration.
']
4 C.
Turbine runback.
D.
Accidental closure of a main steam isolation valve.
28.
When does the po:ser decrease rate initia'. ly stabilize at negative one-third decade per minute following a reactor. trip?
A.
M en 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.
j neutron flux becomes significant.-
D.
When the short-lived delayed neutron precursors have decayed away.
29, 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 answer below, that best describes the no reactor trip, choose the one values of Tave and nuclear power for the resulting new steady state.
(POAH - point of adding heat.)
A.
Final Tave greater than initial Tave, final power at POAH.
B.
Final Tave greater than initial Tave, final power above POAH.
C.
Final Tave less than initial Tavo, final power at POAH.
D.
Final Tave less than initial Tave, final power above POAH.
l FORM B 13 1
~ \\_f
^
2:
a 14 a
30.
Which one of the. following statements concerning the power defect is l
correct?
f The power defect necessitates the use of a ramped Tave program to A.
maincain an adequate Reactor Coolant System subcooling margin.
B.
The power defect increases the rod height requirements. nbeessary to maintain the desired shutdown margin following a reactor trip..
C.~
Because of the higher boron concentration, the power defect is more negative at the beginning of core life.
D.
The power defect causes control rods to be withdrawn as reactor 1
power is decreased.
1g 31.
In which of the following conditions is the moderator temperature coefficient most negative?
A.
BOL, high temperature.
B.
BOL, low temperature.
C.
EOL,' high temperature.
D.
EOL, low temperature.
32.
Which one of the following plant parameter. changes will rerult in an
-increase in shutdown margin for a shutdown reactor? Assume end of life.
A.
RCS boron concentration is increased by 100 ppm.
B.
One control rod (CEA) is fully withdrawn for a test.
.C.
Xenon has' decayed for 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> following shutdown.
-D.
RCS is cooled down by 300 degrees F.
33.
Shutdown margin is the actual amount of reactivity:
A.
inserted by burnable poisons at beginning of life.
B.
due to dissolved boron in the RCS, C.
by which the reactor is suberitical.
~
D.
which would be inserted by shutdown bank rods.
FORM B 14 lu_____________
l
}1 L
c.
i
- h m
.l
~
0*
.e -
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.
1 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.
A 2.0%/ min ramp was used rather than a 0.54/ min ramp.
Thus, the xenon dip would occur and the magnitude-of the dip would be A.
sooner larger smaller B.
sooner C.
later la'rger D.
later smaller 36.
Which one of the follouing 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 is the square root of the IRW at that location.
FORM B 15 I
'e l
l TIIERMODYNAMICS l
subcooling margin during a loss of-coolant accident (LOCA)
L 37.
'n adequate is the most direct indication that is being maintained.
A.
steam genera r 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 calorimetric?
If the feed water temperature used in the calorimetric calculation A.
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 cciorimetric calculation is omitted, actual power will be less than indicated powe't, C.
If the steam flow used in the calorimetric calculation was lower than actuti 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.
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?
j A.
Enthalpy.
B.
Pressure.
C.
Specific Volume.
ti D.
Temperature.
1
}
]
FORM B 16 l
1 I
m.
l' I
40 '.
Operating with which of the following conditions is LEAST EFFECTIVE ' in r
r preventing. brittle fracture in the ECS?
l
. Operating within prescribec heatup and cooldown rate limitations.
A.
B.
Operating with RCS temperature Breater than Nil Ductility Temperature.
Operating with RCS pressure low when RCS temperature is low.
C.
D.
' Operating with a ramped RCS temperature as power level varies.
neutron irradiation adversely affects the reactor pressure vessel-41.
Fast primarily by causing:
A.
metal embrittlement.
B.
brittle fracture.
C.
thermal bradients.
D.
. pressurized thermal shock.
42.
Which one-of the following reactor coolart system (RCS) parameters has the LEAST effect on 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.
i l
1 FDEN B 17 I
s q.
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.
B.
Decreases then increases.
6 l
C.
Increases continuously.
D.
Increases then decreases.
W 44.
The pressurizer power-operated relief ' valve has stuck in a partially I
opened position with the fluid being discharged into the pressurizer relief tank.
The pressurizer pressure in 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 saturated steam.
D.
wet vapor.
45.
Reactor Power is increased sufficiently to cause steam blanketing of several fuel rods. This condition is being caused by:
'A.
departure from nucleate boiling.
B.
.:~2bcooled nucleate boiling.
C.
saturated nucleate boiling, i
D.
onset of nucleate boiling.
l l
1-PORM B 18 I
_. h b
i q
,o by; x
i N
H_ s 46.
Which of the following is HQI an indication of cavitation?-
4-
<j-,
g A,
' Fluctuating discharge pressure.
a
'B.
Pump vibration.
C.
Pump overheating.
J D.~
High discharge pressure.
1 47.
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.
48.
Given the foll'owing RCS part. meters, determine the RCS subcooling rsrgin.
RCS pressure - 22335 psig.
RCS hot leg temperature - 610' F.
A.
25' F, 302 psi.
B.
31' F, 433 psi.
C.
3d* F, 505 psi.
D.
43' F, 588 psi.
FORM B 19
F:-
.c O
- W
J h 49,
~ Placing!two pumps in' parallel' alignment versus a single pump.will. result
.in:
A a large increaseuin 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.
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.
i i
I i
FORM B I
i 20 i
I i
PRESSURIZED VATER REACTOR FORM A QUESTION ANSWER QUESTION ANSWER NUMBER NUMBER 1
C 12 B
i i
2 A
13 A
3 B
14 B
i 4
D 15 B or M 5
C 16 B
6 B
17 C
7 B
18 D
i 8
C 19 A
l 9
C 20 D
10 B
21 B
11 C
22 C
i QUESTION ANSWER QUESTION AMSWER NUMBER NUMBER 23 C
30 C
24 A
31 B
25' D
32 B
26 A
33 A
27 C
34 B
28 A
35 A
29 D
36 A
QUESTION ANSWER QUESTION ANSWER NUMBER NUMBER
- 1 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
l l
l l
1 1
I
]
i PRESSURIZED WATER REACTOR FORM B
.{
QUESTION ANSWER QUESTION ANSWER NUMBER NUMBER 1
C 12 C
2 C
13 C
3 D
14 C
1 4
B 15 B
5 B
16 B
6 B
17 B
7 B
18 B o, /)
6 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
.i t
QUESTION ANSWER QUESTION ANSWER NUMBER NUMBER 37 C
44 D
38 B
45 A
39 C
46 D
40 D
47 D
41 A
48 D
l 42 8
49 B
43 A
50 C
1 I
i i
l 1
I l
j i
f
.a.
o
,..c t-
~
ENCLO3URE 2 p.;
COPY OF VOLUNTARY PARTICPANT BACKGROUND INFORMATION FORM GENERIC FUNDAMENTALS EXAMINATION SECTION (GFES) l ENCLOSURE 2
g.
q i
a
~e E
PILOT TEST PARTICIPANTS' BACKGROUND INFORMATION FORM l
l l
Name Student ID
. Reactor Type Form of Exam (Circle One): PRR BWR Completed (Circle one): A B
i On this form, we ask you to provide some background information about yourself.
Please note that your participation is strictly voluTtary. The information you provide will be used to determine whether or not scores on the.
Fundamentals Examination serve as useful indicators of operator training program experience and/or background.
This request was approved by the Office of Management and Budget under clearance number 3150-0090. Clearance number. 3150-0090 expires on Nov 30, 1989;-Comments on burden and duplication may be directed to the Office of Management and Budget, Reports Management, Room 3208, New Executive Office 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 en Page 4.
The. following questions ask for information about your education, train-ing, and job experience, riease read each question and answer'by circline the-one response that describes you best or filling in the blanks where indicated i
i
}
i j
l Continued Next Page
\\
1
L L.
EDUCATION l
1.
What is ycur 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 1.
Completed a graduate program.
2.
If you completed college (2-or 4-year program), please identify your major program.
a.
Nuclear Engineering b.
Other Engineering (please specify)
Physical Sciences (please specify) c.
d.
Mathematics and Computer Sciences e.
Other (please specify) 3.
If you completed college, please indicate when you graduated.
Month Year 4.
Have you taken college course (s) in nuclear energy?
(Do not include the licensed operator training program when answering this question.)
a.
Yes if yes, indicate the number of courses:
b.
No l
I Continued Next Page
~
,.c
.e, 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?
a.
Yes If yes, indicate how long you served:
Years Months-b.
No 7.
If you-served in the U.S-Navy Nuclear Procuision Procram, please
-answer questions A and B below.
A;
-Indicate the highest position held in the nuclear propulsion
- program, Propulsion Plant Watch Officer a.
b.
Engineering Watch Supervisor.
c Engine Room Supervisor d.
Reactor Operator-e.
Chief, Reactor Watch f.
Engineering Officer of Watch g.
Propulsion Plant Watch Supervisor h.
Other (please specify) 3.
Indicate the time period in which.yau served in the' position identified in Item A above.
From:
Month
'le a r,_ _
To:
Month __
Year l
i I
3 Continued Next Page
~, -
y,.
ca.
LICENSED OPERATOR TRAINING PROGRAM EXPERIENCE-8
- Please' answer questions A, h, 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 i
9.
Below, please answer questions about specific licensed operator training. courses that you have completed.
A.
Have.you completed a course in Reactor Theory?
~
a.
Yes Please indicate the date completed:
Month Year b.
No
-B.
Have you completed a course in Components?
a.
Yes Please indicate the date completed:
Month Year b.
No C.
Have you completed a course in Thermodynamics?
n.
Yes Please indicate the date completed:
j-Month Year b.
No D.
If you plan to begin the training program, please indicate when:
Month Year Continued Next Page I
JOB EXPERIENCE 10.
What is your present job?
a.
Non-licensed / auxiliary / equipment operator b.
Reactor operator c.
Senior reactor operator d.
Shift technical advisor (STA) e.
Shift super /isor f.
Other (please specify) j 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 l
13.
What is the total time you have worked in a commercial nuclear power plant?
Months Years i
i l
Thank you for taking the time to compiere this form.
Please mail this, along with the Examination Feedbeck Questivenaire to:
David J. Lange U.S. Khc Mail Stop OWFN 10-D 18 Washington, DC 20555
.s.
~
(-
c;
'b I
.6 ENCLOSURE 3 COPY OF VOLUNTARY PARTICPANT EXAMINATION FEEDBACK FORM GENERIC FUNDAMENTALS EXAMINATION SECTION (CFES) l l
l ENCLOSURE 3 i-
VOLUNTARY FUNDAMENTALS EXAMINATION FEEDBACK QUESTIONAIP.E Participant's Form Name:
Student ID Reactor Type Form of Examination (Circle One):
PWR BWR completed: (Circle One)
A B
INSTRUCTIONS The Fundamentals Examination contains 22 questions related to 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 complete the feedback form.
Please refer to the copy of the Fundamentals Examination included in your packet of test materials to complete the feedback form. Your specific feedback is greatly appreciated. 'Please return this form, along with the background Information Form, to the address provided on page 7.
Please evaluate each of the examination questions as shown in the following example:
Question Single Item Familiar With Very V+ry Clearly Correct Number Content?
Easy Average Difficult Stated?
Response?
If No, I
l l
Yes/No Reason 1 2 3 4 5 6 7 Yes/No Yes/No hNo Yes@
l 1
Yes h @ b, c 1 2 3 4 5 6 7 In this example, the examinee evaluated qwestion number 1 as follows:
He was not familiar with the test content (No) because it was not covered in the training program (Reason a).
He rated the f. tem as difficult (6).
i i
l The question is clearly stated (Yes).
j The question does not have a single correct response (No).
=
Explanations of each of these categories are provided on the following page.
1 Continued Next Page
l
~
VOLUNTARY FUNDAMENTALS EXAMINATION FEEDBACK QUESTIONNAIRE j
Participant's Form i
i I
Familiar with Content? Answer YES if you were familiar with the question j
content.
If your were D2r familiar with the content, please tell us the j
Brassa why, using the following codes:
l 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 nuestion on a 1 through 7 scale:
Very Easv:
A question that can be answered correctly by someone who has not completed the fundamentals portion of the training program.
Average:
A question that is not too easy, but not too cifficult.
Very Difficult:
A question that cannot be s.nswer 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.
Sinnie 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 respense appears correct, circle No.
The form for your individual questicn evaluations begins on the next page, followed by the general questions about the examination. Continued Next Page
' VOLUNTARY FUNDAMENTALS EXAMINATION FEEDBACK QUESTIONNAIRE i --
Participant's 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
Yes/No Reason 1 2 3 4 5 6 7 Yes/No Yes/No 1
Yes/No a, b, c 1 2 3 4 5 6 7 Yes/No Yes/No 2
Yes/No a, b, c 1 2 3 4 5 6 7 Yes/No Yes/No 3
Yes/No 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
5 Yes/No a, b, c 1 2 3 4 5 6 7 Yes/No Yes/No 6
Yes/No a, b, c 1 2 3 4 5 6 7 Yes/No Yes/No 7
Yes/No a, b, c 1 2 3 4 5 6 7 Yes/No Yes/No 8
Yes/No a, b, c 1 2 3 4 5 6 7 Yes/No Yes/No 9
Yes/No a, L, 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/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 Yer/No 18 Yes/No a, b, c 1 2 3 4 5 6 7 Yes/No Yes/No 19 Yes/No a, b, c 1 2 3 4 5 6 7 Yes/No Yes/No 20 Yes/No a, b, c 1 2 3 4 5 6 7 Yes/No Yes/No j
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 Yer/No 24 Yes/No a, b, c 1 2 3 4 5 6 7 Yes/No Yes/tdo 25 Yes/-.
a, b, c 1 2 3 4 5 6 7 Yes/No Yes/No 26 Yes/No a, b, c 1 2 3 4 5 6 7 Yes/No Yes/No
{
l l
J Continued Next Page L1__ __ _ __
1
VOLUNTARY FUNDAMENTALS EXAMINATION FEEDBACK QUESTIONNAIRE j
4 L
1 l
Participant's Form EVALUATIONS OF EXAMINATION OUESTIONS l
Question Single Item Familiar With Very Very Clearly Correct Number Content?
Easy Average Difficult Stated?
Response?
l If No,
[
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 7es/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 Ves/No 34 Yes/No a, b, c 1 2 3 4 5 6 7 Yes/No Yes/No 35 Yes/No a, b, c 1 2 3 4 5 6 7 Yes/No Yes/No 36 Yes/No a, b, c 1 2 3 4 5 6 7 Yes/No Yes/No 37 Yes/No a, b, c 1 2 3 4 5 6 7 Yes/No Yes/No 38 Yes/No a, b, c 1 2 3 4 5 6 7 Yes/No Yes/No 39 Yes/No a, b, c 1 2 3 4 5 6 7 Yes/No Yes/No 40 Yes/No a, b, c 1 2 3 4 5 6 7 Yes/No Yes/No 41 Yes/No e, 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, e 1 2 3 4 5 6 7 Yes/No Yes/No 48 Yes/No a,b,c 1 2 3 4 5 6 7 Yes/No Yes/No 49 Yes/No a,b,c 1 2 3 4 5 6 '/
Yes/No Yes/No 50 Yes/No a, b, c 1 2 3 4 5 6 7 Yes/No Yes/No
-L Continued Next Page
l av
i e
i=
VOLUNTARY FUNDAMENTALS EXAMINATION FEEDBACK QUESTIONNAIRE f
Participant's Form 1
CENERAL OUEST10NS ABOUT THE FUNDAMENTAL EXAMINATION-
.l l
.In th'is section, we ask you to answer specific questions about each of the l
three sections in the examination (Components, Reactor Theory, and Thermo-dynamics) and some general questions about the examination.
For each statement appearing below, please indicate your response by circling Yes or No.
If you want to provide comments about your responses to these items, please write them in the space below each item. You can also provide additional comments about the examination in the last section.
Comoonents Ouestions (Items 1 throuch 22)
Yes No 1.
Do the 22 examination questions represent a good measure of basic Component Knowledget Yes No 2.
Do the 22 examination questions comprehensively sample Components 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 Reector 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 examination questions comprehensively sample Thermo-dynamics material presented in your training program?
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 Fundamentals Examination in two hours or less?
l Yes No 8.
Should more items be added to this examination to ensure comprehensive coverage?
l Continued Next Page
[/
9 c
LVOLUNTARY FUNDAMENTALS EXAMINATION FEEDBACK QUESTIONNAIRE
<J*-
g j
Participant's Form j
-J CENERAL OUESTIONS ABOUT THE FUNDAMENTALS EXAMINATION (Continued)
Yes No 9.
Can these knowledge areas be comprehensively tested with fewer j
g' 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 scoreL of 70% or higher on this examination?
Yes No. 11, Do you think non-licensed t.perators currently participating in.
)
the operator training program need to study to obtain a. score 1
of 70% or higher on the examination?
-f Yes No 12.
Would you recommend that a passing score on this examination be required for al' aon-licensed operators prior to receiving an J
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 somacne who has no_t 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 materia 1' 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?
6-Continued Next Page e
i VOLUNTARY FUNDAMENT 4.LS EXAMINATION FEEDBACK QUESTIONNAIRE Participant's Form 1
General Comments If you have additional comments that you would like to make about the Fundamentals Examination, please provide them below.
w Thank you for your input.
Please return this questionnaire, along with the Background Information Form, to:
l David J. Lange U.S. NRC Mail Stop OWFN 10 D-18 Washington, DC 20555 _ _ - _ _ _ _ _ _ _ _ _ -...
l l
7 l
i i
ENCLOSURE 4
\\
COPY OF VOLUNTARY TR. TINING DEPARTMENT EXAMINATION FEEDBACK FORM GENERIC FUNDAMENTALS FIAMINATION SECTION (CFES)
ENC 14SURE 4 l
1
7, VOLUNTARY FUNDAMENTALS EXAMIN' TION FEEDBACK QUESTIONNAIRE-
. Training Departmen<, Personnel Form Name:
Student ID Reactor Type Form of Examination (Circle.One): _PWR BWR reviewed: (Circle One)
A B-INSTRUCTIONS The Fundamentals Examination contains 22 questions related to Comoonentg, 14 related to Reactor Theory, and 14 related to Thermodynamics. On this feedback form, you are arked to evaluate the examination questions in nach of these three' areas and to answer some general questions about the e';smination.
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 greatly appreciated.
Please return this form, along with the Background Information Form, to the adoress provided on page 7.
Please. evaluate cach 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 particioatine in the ooerator licensinr traininc crocram, 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 the test content (No),
because it was not covered in the training program (Reason a).
The item is rated as difficult (6).
The question is clearly stated (Yes).
The question does not have a single correct response (No).
Explanations of each of these categories are provided on the following page.
+1-Continued Next Page
o
'~
' VOLUNTARY 1 FUNDAMENTALS EXAMINATION FEEDBACK QUESTIONNAIRE
.:.1
~.
-Training'Departnent Personnel Form LEgriliar'with Content? Answer YES if non-licensed operators participating in the operator, licensing training pro $ ram would be familiar with the question content.
If you answer n2, than non-licensed operators would not be familiar
-j I
with the content, please tell us the Reason why, using the following codes:
.I
- a)'
itlwas not covered'in your training program.
b)-. question content is not relevant for your facility.
Question Difficulty, Use the following definitions to rate'the difficulty of each question on a 1 through 7 scale:
~~
Verv Easv:
A question that can be answered. correctly by someone who has D21 comp eted the fundamentals portion of the l
training program.
Averace:
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-
.uncient or difficult.to understand, circle No.
'Sincie Correct Resnonse? If there is EDg and.only one correct answer, circic 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 examir.ation.
l l
l 1 Continued Next Page L-___-----_-_--__--___--
iVOLUNTARY FUNDAMENTALS EXAMINATION FEEDBACK QUESTIONNAIRE Training Dep::rtmant Parsonn21 For:a EVALUATIONS OF EXAMINATION OUESTIONS Question Single Item Familiar Vith' 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 2
Yes/No a, b, c 1 2 34 5 6 7 Yes/No Yes/No 3
Yes/No a, b, c 1 2 3 4'5 6 7 Yes/No Yes/No 4
Yes/No a, b, c 1 2 3 4 5 6 7 Yes/No Yes/No 5
Yes/No' a, b, c 1 2 3 4 5 6 7 Yes/No Yes/No.
'6 Yes/No' a, b, c 1 2 3 4 5 6 7 Yes/No Yes/No 7
.Yes/No' a, b, c 1 2 3 4 5 6 7
.Yes/No
~Yes/No 8
Yes/No a, b, c 1 2 3 4 56 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-
'I 2 3 4 5 6 1 Yes/No Yes/No 12 Yes/No a, b, c 1 2 3 4 5 6 7 Yes/No Yes/No-13 Yes/No a, b,' c 1 2 3 4 5 6 7 Yes/No Yes/No 14 Yes/No a, b, c 1 2 3 4 5 6 7 Yes/No Yes/No 15 Yes/No a,b,c.
1 2 3 4 5 6 7 Yes/No
.Yes/No
-16 Yes/No a,b,c 1 2 3 5 6 7 Yes/No Yes/No 17 Yes/No a, b, c 1 2 3 4 5 6 7 Yes/No Yes/No
'18 Yes/No a,.b, c
1 2 3 4 5 6 7 Yes/No Yes/No 19 Yes/No a, b, c 1 2 3 4 5 6 7 Yes/No Yes/No 20 Yes/No
.a,b,c 1 2 3 4 5 6 7 Yes/No Yes/No 21 Yes/No a, b, c 1 2 3 4 5 6 7 Yes/No Yes/No 22' Yes/No-a, b, c 1 2 3 4 5 6 7 Yes/No Yes/No I
23 Yes/No a
h, 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 Yes/No Yes/No Continued Next Page
=_
VOLUNTARY' FUNDAMENTALS EXAMINATION FEEDBACK QUESTIONNAIRE
.v Training Department Personnel Form EVALUATIONS OF EXAMINATION OUESTIONS 1
1 i
Question Single
' Item Familiar With Very Very Clearly Correct
' Number Content?
Easy Average.. Difficult Stated?
Response?
If No, l
l l
'j Yes/No Reason 1 2 3 4 56 7 Yes/No Yes/No j
j 1
271 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 :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 56 7
'Yes/No Yes/No 1
31 Yes/No a, b, c 1 2 3 4 5 6 7 Yes/No Yes/No 32 Yes/No a, b, c
'l 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'
56 7 Yes/No Yes/No 36 Yes/No-a, b, c 1 2 3 4 5 6 7 Yes/No Yes/No 37 Yes/No a, b, c 1 2 3 4 5 6 7 Yes/No Yes/No
'38 Yes/No.
a,b,c 1 2 3 4 5 6 7 Yes/No
.Yes/No
.1 39
.Yes/No a, b, c 1 2 3 4 5 6 7 Yes/No Yes/No 40-Yes/No a,b,c 1 2 3 4 5 6 7 Yes/No Yes/No 41 Yes/No a, b, c 1 2 3 4 5 6 7 Yes/No-Yes/No 42.
Yes/No a, b, c l'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 l'
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/Ho Yes/No 47 Yes/No a,b,c 1 2 3 4 5 6 7 Yes/No Yes/No 48 Yes/No a, b, c 1 2 3 4 5 6 7 Yes/No Yes/No 49 Yes/No a, b, c 1 2 3 4 5 6 7 Yes/No Yes/No 50 Yes/No a, b, c 1 2 3 4 5 6 7 Yes/No Yes/No i Continued Next Page l
)
VOLUNTARY FUNDAMENTALS EXAMINATION TEELBACK QUESTIONNAIRE
{
Training Department Personnel form l
GENERAL 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-l dynamics) and some general questions about the examination, j
Some of the following questions assume that you have detailed information i
about the Operator Licensing Training Program.
If that is not true, please write "Do Not Know" for those questions.
i For each statement appearing below, please indicate your response by circling Yes or No.
If you want to provide com:nents about your responses to these items, please write them in the space bt '.ow each item. You can also provide additional comments about the examination in the last section.
Components Ouestiens (Items 1 throuch 22)
Yes No 1.
Do the 22 examination questions represent a good measure of basic Component Knowledge?
Yes Nr 2.
Do the 22 examination questions comprehensively sample i
Components material presented in your training program?
reactor Theorv Questions (Items 23 throuch 36) l 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?
I Yes No 6.
Do the 14 examination quest (ons comprehensively sample Thermo-dynamics material presented in your training program?
1
-S-Continued Next Page L- -__ _ _ _
4 i-
. VOLUNTARY: FUNDAMENTALS EXAMINATION' FEEDBACK QUESTIONNAIRE 1,
s Training Department Personnel. Form
' General Ovestions About the Fundamentals Examination
'Yes-
-No 7.
Is it reasonable to expect an individual with satisfactory V
knowledge of the subject areas to complete the Fundamentals 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 Ne 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.)
{
Yec No 14.
In general, is this examination too easy?. (Easy is defined es containing many items.that can be answered correctly by someone who has Der completed the fundamentals portion of the training prograu.)
l
.Yes No 15 Is the percentage of items for the three sections appropriate g
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 u
your training program,7 j
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?
j i
Yes No 19.
Do you believe that your examination score represents your knowledge of the three areas? Continued Next Page j
l l
l' l
4 VOLUNTARY FUNDAMENTALS EXAMINATION FEEDBACK QUESTIONNAIRE Participant's Form Eg.teral Comments If you have additional comments that you would like to make about the Fundamentals Examination, please provide them below.
Thank you for your input.
Please return this questionnaire to:
David J. Lange U.S. NRC Mail Stop OWFN 10 D-18 Washington, DC 20555 l.
__.___m..__
4,:.
G
.4 l
1l i.
I-ENCLOSURE 5 l
COPY OF COVER LETTER FOR REGION FACILITIES ENCLOSURE 5 l
1 1
= - - - - -
- y a
- s j#prio g'o u
UNITED STATES :
..g, NUCLEAR REGULATORY COMMISSION
. k. -
4 C
3' WASHINGTON, D. C. 20655
...e.
- Docker No. 155-Mr. Richard W. Buckner Comsumers Power. Company-Big Rock Point Nuclear Plant
?
) >x 591, Route 3 01 elevoix, MI 49720
Dear.Mr. Buckner:
on June 28..1989, the NRC administered a Generic Fundamentals Examination Sect. ion. (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 Efirst 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 For is requested the candidateLvill be reauired to take the entire SSES.
candidates. requesting a waiver, the results of the GFES will be totaled with the sections of tbs SSES to obtain an overall examination grade. GFES results.
will count for. 2% oit the total of an RO licensing examination and' 24 % of the-total of an SRO li ensing examination. The overall averaged passing grade for an NRC administered licensing examination is 804, includine the fundamentals section. The passing grade for each individual section including the.
Fundamentals Section, is 70%.
On October 1.,1989 the NRC will modify the steps to be taken to apply for an RO or an SRO licent) to operate a PWR or BUR 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 the material tested by the GFES prior to being administered the SSES.
4,pplicant will be able to demonstrate this proficiency by having passed either of the two following examinations, list.ed on the next page, for the reactor type for which a license is sought, b
i
4 1.
An NRC administered GFES for PWRs or EWRs.
2.
An NRC written licensing examination for PVRs or BWRs administered between Feuruary 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.
T.,e SRC will establish within the Operator Licensing Examiner Standards
(:wkEG-1021) eligibility requirements for taking the GFES.
Personnel wishing to register for the GFES must 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 CPR 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 vritten examination and improve the design of future examinations, we have included with this letter voluntary feedbeck forms and background information forms for both the participants and the training personnel, at your facility.
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l This' request was approved by the Office of Management and Budget under i
l f sarance number 3150-0090.
Clearance 3150 0090 expires November 30, 1989 Corments on burden and duplication may be directed to the Office of
- Management ind Budget,~ Reports Management, Room 3208, New Executive Office u
' Building, Washington, DC 20503.
[_
Should you have.any questions concerning this examination, please contact Mr.' Paul Doyle at (301) 492-1047.
l Sincerely, Kenneth E. Perkins Jr., Chief Operator Licensing Branch Division of Licensee Performance and Quality Evaluation, NRR, NRC
Enclosures:
j 1.
Examination Forms "A" and "B" with answers 2.
Copy of Voluntary Background Information Feedback Form for examination-participants-3.
Copy of Voluntary Examination Feedback Form for examination participants 4.
Copy of, Voluntary Examination. Feedback Form for training department
. personnel 5.
Examination Results Summary for facility (ies) 6.
Copies of participants individual answer. sheets 1
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Docket No.
50-461, 50 462 Mr. D. L. H01tzscher Illinois Power Company Clinton Power Stacion P. O. Box 678 Clinton, Illinois 61727
Dear Mr. Holtzscher:
On June 28, 1989, the NRC administered a Generic Fundamentals Examination i
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 Ig.quig d to take the entire SSES. For candidates requesting a vaiver, the results of the CFES 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 end 24 % of the total of an SRO licensing examination. The overall averaged passing grade for an NRC administered licensing examination is 80%, includinn the fund &mentals section. The passing grade for each individual section including the Fundamentals Section, is 70%.
r On Octob.
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 aflal 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 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 4 37, 50-249 Mr. E. D. Eenigenburg Commonwealth Edison-Dresden Nuclear Power Station R. R. # 3 horris, Illinois 60450 l
Dear Mr. Eenigenburg:
j On June 28, 1989, 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 j
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 en NRC administered reactor operator (RO) or l
senior reactor operator (SRO) written licensing examination prior to 0ctober
.)
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 J
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
'i her NRC form 398, based on the date he or she passed the CFES. 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. CFES 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' j
Fundamentals Section, is 70%.
On October 1, 1989 the NRC will modify the steps to be taken to apply for an RO or.an SRO license to operate a PVR or BVR reactor. Candidates scheduled to-i take an initital NRC administered RO or SRO written licensing examination on or aftet 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.
50-331 Mr.: Daniel L.;Mineck I
Iowa Electric and Power Company.
P. O. Box 351-q; Cedar Rapids, Iowa 52406
Dear.Mr. Mineck:
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 sheetc. A "P" in the column i
labeled Final Grade indicates a passing grade and an."F" in this column indicates'a failing grade for this examination.
4 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,' bas,ed on the date he or she' passed the GFES.
If no waiver j
is requested the. candidate will be recuired to take the entire SSES. For..
candidates requesting a waiver,.the results of the CFES will be totaled with
{
the sections, of the SSES to obtain an overell' examination grade. GFES results
]
will count for 25% of the total of an RO licensing examination and 24 % of the 1
total of an SRO licensfng examination. 'The overall averaged passing grade for
')
f an.NRC administered licensing. examination is 80%, includine the fundamentals section. The' passing grade for each individual section including the Fundamentals Section, is 70%.
5 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'PVR 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 appifcant will be able to demonstrate this proficiency by having passed either i
of the two following examinations, listed on the next page, for the reactor j
type for which a license is sought.
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50-341 Mr. B. Ralph Sylvia Detroit Edison 6400 North Dixie Highway Newport, Michigan 48166
Dear Mr. Sylvia,
on June 28, 1989, the NRC administered a Generic Fundamentals Examination Section (GFES) of the writter. 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 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. 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%, includinc the fundamentals s;ction. 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 BVR 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.
50-373, 50-374 Mr..G. J. Diedrich 3
Commonwealth Edison LaSalle County Nuclear Station
' Rural Route #1,' Box 220 Marseilles, Illinois-61341
Dear Mr. Diedrich,
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 reauired to take the entire SSES.
For
't 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%.
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 BUR reactor.
Candidatee scheduled to p
take an initital NRC administered RO or SRO written licensing examination i
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, l
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l Docket No.
50-263 Mr.'Greg Holmstadt Monticello Training Center L
2100 West River Street l
Monticello, MN 55362
Dear Mr.-Holmstadt:
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 secticn 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 CFES 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 licenring 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.
.l 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.
50-254, 50-265 l
Mr. Jeffrey A. Neal Commonwealth Edison Quad Cities Nuclear Power Station 22710 206 Avenue North Cordova, Illinois 61242 i
Dear Mr. Neal:
On June 28, 1989, the NRC administered a Generic Fundamentals Examination I
Section (GFES) of the written licensing examination to employees of your facility.
Enclosed with this letter are the graded results and answer sheets i
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 I
first section of the site-Specific Examination Section (SSES) (section 1 of l
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 l
her NRC form 398, based on the date he or she passed the GFES.
If no waiver j
is requested the candidate will be reouired to take the entire SSES. For j
candidates requesting a waiver, the results of the GFES will be totaled with l
the :ections 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 s ection'.
The passing grade for each individual section including the i
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.
50-456, 50-457 Mr R. E. Querio Commonwealth Edison Braidwood Nuclear Power Station Route #1,. Box 84-Bracev111e, Illinois 60407 l
l
Dear Mr.'Querio:
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 exami.ation.
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 thir. 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 grado for an NRC administered licensing examination is 80%, includino the fundamentals section. The passing grade for each individual section including the Fundamentals Section, is 70%.
On October 1, 1969 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 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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50-454, 50-455 Mr. Alan J. Chernick Commonwealth Edison Byron Nuclear Station 4450 North German Church Road Byron, Illinois 61010
Dear Mr. Chernick:
On June 28, 1989, the NRC administered a Generic Fundamentals Examination Section (GFES) of the written licensing examinations 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 4
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 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 PRR or BWR reactor. Candidates scheduled to taka an initital NRC administered RO or SRO vritten licensing examination on or efter 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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4 Docket No.
50-483 Mr. G. L. Randolph
. Union Electric Callaway Plant P. O.. Box 620 Fulton, MO 65251
Dear Mr. Randolph:
On June 28, 1989, the NRC administered a Generic Fundamentals Examination i.
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 fciling grade for this examination.
Candidates scheduled to take an NRC administered reactor operator (RO) or senior reactor operator (SRO) writ' ten 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 To do the RO written examination or section 4 of the SRO vritten examination, this, he or she must request a waiver of this section of the SSES on his or-If no waiver her NRC. form 398, based on the date he nr she passed the CFES.
For is requested the candidate will be It2pired to take the entire SSES.
candidates requesting a waiver, the results of the GTES will be totaled with the sections of the SSES to obtain an overall examination grade. GFIS results will count for 25% of the total of an RO licensing examination and 24 % of the total of an SRO licensing examination. JThe 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 70s.
On October 1, 1989 the NRC will modify the steps to be taken to apply for an Candidates scheduled to RO or an SRO license to operate a PWR or BWR reactor.
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 the material tested by the GFES prior to being administered the SSES.
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.
'o UNITED STATES b,/
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Docket No.
50-315, 50-316 Mr. W. G. Smith Indiana Michigan Iewer Company Cook Nuclear Plant P.O. Box 458 Bridgman, M1 49106
Dear Mr. Smith:
on June 28, 1989, the NRC administered a Generic Fundamentals Examination Section (GFES) of the written licensing examination to employees of your facility. Enclosed "ith 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 grace 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 Sk0 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 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%, lasluding the fundamentals section. The passing grade for each individual section including the Fundamentals Section, is 706.
On October 1, 1989 the NRC will modify the steps to be taken to apply for an RO or an SRO license to operate a PWR or BWR reactor. Candidates scheduled to take an 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 ths 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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Dockt.c No.
50-346 Mr. Richard Simpkins Toledo Edison Company Davis-Besse Nuclear Station 5501 N. State, Route 2 Oak Harbor, Ohio 43449
Dear Mr. Simpkins,
On June 28, 1989, the NRC administered a Generic Fundamentals Examination Section (GFES) of the written licensing examination to employees of your facility. Er.cicised 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" la 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 CFES.
If no waiver is reouested 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. 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%, includinc the fundamentals section. The passing grade for each individual section including the Fundamentals Section, is 70%.
On October 1, 1989 the NRC will modify the steps to be taken to apply for an RO or an SRO license to operate a Pk'R or Bk'R reactor.
Candidates schedaled to take an initical NRC administered RO or SRO vritten 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.
50-255 Mr.-David Rogers Comsumers Power Company l
Palisades Nuclear Power Plant Route 2, Box 154 Covert, MI 49043
Dear Mr Rogers:
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 Fiz.al 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 y
is requested the candidate will be reouired to take the entire SSES. For candidates requesting a vaivar, the results of the GFES will be totaled with the sections of the SSES to obtain an overall examination grada, 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 l
an NRC administered licensing examination is 80%, includine the fundamentals section. The passing 7,rade for each individual section including the Fundamentals Section, is 70%.
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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 BUR reactor. Candidates scheduled to take an initical NRC administered RO or SRO written licensing examination
_q 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 J
type for which a license is sought.
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Docket No.
50-266, 50-301 Mr. J. J. Zack Wisconsin Electric Power Company Point Beach Nuclear Plant 6610 Nuclear Road Two Rivers, WI '54241
Dear Mr. Zack:
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 labelrd 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 examinati m 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 for'. 398, based on the date he or she passed the GFES.
If no waiver is reauerted 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 examina':.2.m and 24 % of the
'cotal of an SRO licensing examination. The-overall averagu $.assing grade for an NRC administered licensing examination is 80%, includine the fundamentals i
section. The passing grade for each individual section including the Fundamentals Section, is 70%.
i 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
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The the material tested by the CFES prior to being administered the SSES.
applicant will be able to demonstrate this proficiency by having passed either j
of the two following examinations, listed on the next page, for the reactor
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type for which a license is sought.
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Docket No.
50 282, 50-306 Mr. i. E. Amundson Northern States Power Company 414 Nicollet Mall Minneapolis, Minnesota 55401
Dear Mr. Amundson.,
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 resuits to the examinees along with copics 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 reaufred to take the entire SSES.
For candidates requestirg a waiver, the results of the GFES will be totaled with the sections of the SSES to obtain ao 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%, includinz the fundamentals section.
The passing grade fc r 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 3
RO or an SRO license to operate a FWR or BWR reactor. Candidates scheduled to
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take an initital NRC administered RO or SRO written licensing examination
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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 type for which a license is sought.
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Docket No.
50-295, 50-304
' Mr. Al J. Ockert Commonwealth Edison Zion Generating Station 101 Shiloh Blvd Zion, Illinois 60099
Dear Mr. Ockert,
F e 28, 1989, the'NRC administered a Generic Fundamentals Examination Section (CFES) of the written licensing examination to employees of your fatality.
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 failig grade for this examination.
Candidates scheduled to ts.ke an NRC administered reactor operator (RO) or senior reacter 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 Eite-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 requirs.d 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 of the two following examinations, listed on the next page, for the reactor type for which a license is sought.
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