ML20141H796

NRC Operator Licensing Initial Exam Rept 50-288/OL-97-01 Administered on 970505-07.Four ROs & Two SROs Administered Exam.All Six Candidates Passed Respective Exams

ML20141H796
Person / Time
Site:	Reed College
Issue date:	05/15/1997
From:	Isaac P NRC (Affiliation Not Assigned)
To:
Shared Package
ML20141H766	List: ML20141H796
References
50-288-OL-97-01, 50-288-OL-97-1, NUDOCS 9705270126
Download: ML20141H796 (29)

Text

.,

Reed College Docket No. 50-288 cc:

Director, Oregon Department of Energy 528 Cottage Street, N.E.

Salem, Oregon 97310 Mayor of City of Portland

.1220 Southwest 5th Avenue Portland, Oregon 97204 Administrator Siting and Regulation Oregon Department of Energy Labor and Industries Building Room 111 Salem, Oregon 97310 t

9705270126 970519 PDR ADOCK 05000288 V PDR -s l

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I REPORT DETAILS

1. Examiners:

Patrick Isaac, Chief Examiner l Paul Doyle, Examiner -

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2. Results:

RO PASS / Fall SRO PASS / Fall TOTAL PASS / Fall .

Written 4/0 0/0 4/0 Operating Test 4/0 2/0 6/0 Overall 4/0 2/0 6/0

3. Exit Meeting:

Personnel attending:

Mr. Stephen Frantz, REED College, Facility Director Patrick Isaac, Chief Examiner  :

Paul Doyle, NRC Examiner The NRC examiners commented on the readiness and excellent performance of the i candidates.  !

Following their review of the written examination, the REED reactor staff requested that two correct answers be accepted for questions A.3 and C.6 of the written examinatio7 ,

The NRC examiners agreed with the request and the examination answer key was l modified accordingly. ]

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1 U. S. NUCLEAR REGULATORY COMMISSION NON-POWER INITIAL REACTOR LICENSE EXAMINATION I I

FACILITY: REED College REACTOR TYPE: TRIGA  !

DATE ADMINISTERED: 1997/05/06 REGION: IV l CANDIDATE:

INSTRUCTIONS TO CANr2DATE.

Answers are to be written ort the answer sheet previded. Attach the answer sheets to  !

the examination. Points for each question are indicated in paren-theses for each  !

question. A 70% overaliis required to pass the examination. Examinations will be picked up three (3) hours after the examination starts.

% OF CATEGORY % OF CANDIDATE'S CATEGORY VALUE TOTAL SCORE VALUE CATEGORY 20.00 33.3 A. REACTOR THEORY, THERMODYNAMICS AND FACILITY OPERATING CHARACTERISTICS 20.00 33.3 B. NORMAL AND EMERGENCY OPERATING PROCEDURES AND RADIOLOGICAL CONTROLS 20.00 33.3 C. PLANT AND RADIATION MONITORING SYSTEMS 60.00  % TOTALS FINAL GRADE All work done on this examination is my own. I have neither given nor received aid.

Candidate's Signature ENCLOSURE 2

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o c uu vii n o ieic uiv. iiiciniv u e auiity vucian iu unaimuensuus rags z OUESTION (A.1) [1.0]

As power level increases, the Prompt Negative Temp. Coefficient (PNTC) causes:

a. 23eu to absorb neutrons over a wider range, thus decreasing the number of neutrons available for fission with 23sU.-

b. Doppler resonance effects to decrease.

c. The hydrogen atoms in the ZrH2 to slow down more neutrons.

d. More thermal neutron absorption by the moderator.

QUESTION (A.2) [1.0]

What is the stable Rx period which produces a power rise from 1 watt to 5 KW in 186 seconds?

a. 10 seconds.

b. 22 seconoo.

c. 30 seconds.

d. 116 seconds.

QUESTION (A.3) [1.0)

Which one of the following indicates the response of zirconium hydride-uranium mixture used in the fuel to a rapid power excursion?

a. Power is rapidly turned by the increased Doppler broadening of the zirconium.

b. Power is rapidly turned by the increased Doppler broadening of the uranium.

c. Fuel temperature increase will increase the moderation length of neutrons.

d. Fuel temperature increase will increase :he absorption cross section of the fuel.

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QUESTION (A.4) ['1.0) in a subcritical Reactor, K,is increased from 0.861 to 0.946. Which ONE of the following is the amount of reactivity that was added to the core?

a. 0.085 AK/K

b. 0.220 AK/K i

c. 0.104 AK/K d.' O.125 AK/K QUESTION (A.5) [1.0]  !

Delayed neutrons have a large effect on control of reactor power due to their longer generation time. .Which one of the below is the reason for the longer generation time?  !

a. Delayed neutrons have shorter half-lives. ,

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b. Delayed neutrons thermalize slower. i

c. The escape probability for delayed neutrons is higher. l I

d. Delayed neutrons are not a product of primary fission. j QUESTION (A.6) [1.0]

Assume the following rod worths: Safety and Shims are $4.25 each, Reg. is $1.75 and Core excess is $2.5.

Which one of the following is the Minimum Shutdown Margin?

a. $3.0

b. 53.5

c. $6.0

d. $7.25 1

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. QUESTION (A.7) [1.0]

Which of the following statements correctly describes the reactor operating characteristic of "Undermoderated"?

e. A decrease in core water temperature will cause a negative reactivity response.

b. Reducing the amount of moderation will cause a positive reactivity response.

c. An increase in core water temperature will cause a positive reactivity response.

d. A decrease in core water density will cause a negative reactivity response.

QUESTION (A.8) (1.0)

Assume that reactor power is 50% and equilibrium Xenon is attained. Reactor power is then increased to 100%. Which one of the following correctly describes the new equilibrium Xenon value?

2. The 100% equilibrium xenon is half the 50% value ,

b. The 100% equilibrium xenon is equal to the 50% value.

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c. The 100% equilibrium xenon is higher than the 50% value but not twice as high. I

d. The 100% equilibrium xenon is twice as high as the 50% value.

QUESTION (A.9) [1.0]

'Which ONE of the following is the type of heat transfer taking piace from the fuel cladding surface to the r actor upper pool when the reactor is operating at steady state 200 kW7

a. Conduction

b. Film boiling

c. Convection

d. Nucleate boiling l l

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QUESTION (A.10) [1.0)

Which ONE of the following describes how doubling the time a target nuclide is irradiated affects the activity level,

a. Less than doubles the activity.

b. More than doubles the activity.

c. Exactly doubles the activity,

d. Increases the activity by a factor of e.

QUESTION (A.11) [1.0]

Which of the following completes the statement?

The largest amount of recoverable energy from fission of uranium 235 is due to the kinetic energy of the:

c. fission neutrons.

b. fission gammas.

c. beta decay particles.

d. fission fragments.

QUESTION (A.12) [1.0]

A reactor startup is being performed. The reactor is supercritical and power is being raised to 200 kw. The period meter indicates 80 seconds. Select the expected time that it would take for power to double.

a. 30 seconds

b. 55 seconds

c. 80 seconds

d. 95 seconds

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QUESTION (A.13) [1.0]

If we assume that the core excess reactivity is worth $2.85, which one of the following is the amount of n;gative reactivity that must be inserted to assure that the reactor is " shutdown" as defined per Tech. Specs,

a. $2.85

b. $3.39

c. $3.55

d. $3.79 QUESTION (A.14) [1.0J If Keff equals 1.0, how much reactivity mur,t be added to make the reactor prompt critical?

a. The beta fraction.

b. The amount to make Keff equal to 1.1.

c. The amount to make the reactor period infinite.

d. The amount needed to increase the mean neutron lifetime to 0.080 seconds.

QUESTION (A.15) [1.0)

Assuming that you pull the safety rod at the maximum reactivity insertion rate allowed per Technical Specifications. How long would it take to add $2.00 worth of reactivity? (Assume a linear rod worth.)

a. 1.87 seconds

b. 12.5 seconds

c. 16.7 seconds

d. 17.5 seconds

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QUESTION (A.16)' [1.0]

The reactoris suberitical with a Keff of 0.95 and a source range count rate of 15 counts per second. Control rods are withdrawn until the source rcnge count rate equals 45 counts per second. j Which of the following is the Keff of the core after the control rod withdrawal?

a. 0.953

b. 0.970 '

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c. 0.983

d. 0.995 QUESTION (A.17) [1.0]

The reactor has been operating for 3 weeks at 230 KW, when a loss of cooling accident causes the reactor core to be completely uncovered. The core cannot be recovered with water and must remain cooled only by cir.

According to the Safety Analysis Report (SAR), the main radiation hazard will be produced by the

a. melting of the fuel cladding when its temperature exceeds the melting point of aluminum

b. rupture of the fuel cladding from the fission gas pressure buildup

c. - loss of shielding for the fuel elements in the reactor core

d. - activation of Argon-41 in the atmosphere of the reactor room QUESTION (A.18) [1.0]

Which one of the following is the reason for withdrawing the safety and shim control rods a comparable cmount during power operation?

a.' To reduce the effect of fission product poisons by reducing xenon and samarium buildup in the center of the core

b. To maintain comparable safety and shim rod worths by evenly burning out the poison in the rods

c. To increase the regulating rod worth by increasing neutron flux near the regulating rod  ;

d. To promote uniform fuel burnout by flattening the flux across the core f

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A reactor startup is in progress by withdrawing a control rod and then waiting until count rate stabilizes. The reactor is not critical. Assume that the control rod is being withdrawn in equal amounts each time and each control rod withdrawal adds equivalent amounts of reactivity.

Compare two consecutive control rod wi'hdrawals.

a. Time for power to stabilize will be equal for both withdrawals and the power increase will be the same for both withdrawals.

b. The power increase will be the same for both withdrawals but the time for power to stabilize will be less ,

for the second withdrawal.

c. The power increase will be the same for both withdrawals but time for power to stabilize will be longer for the second withdrawal. -

d. The power increase will be larger for the seco.id withdrawal and the time for power to stabilize will be longer for the second withdrawal.

QUESTION (A.20) [1.0]

The reactor is operating at 100 KW. The reactor operator withdraws the Regulating Rod allowing power to increase. The operator then inserts the same rod to its original position, decreasing power.

In comparison to the rod withdrawal, the rod insertion will result in:

a. a slower period due to long lived delayed neutron precursors.

b. a faster period due to long lived delayed neutron precursors. ,

c. the same period due to equal amounts of reactivity being added.

d. the same period due to equal reactivity rates from the rod.

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• "" END OF SECTION A *""

Covuvjiu ciut tif airr;ntetuct suv r s uveuuics u isou vvy t'agt! U QUESTION (B.1) [1.0]

A point source of gamma radiation measures 50 mr/hr at a distance of 5 ft.

What is the exposure rate (mr/hr) from the source at a distance of 10 ft.

a. 25 mr/hr

b. 12.5 mr/hr

c. 6.25 mr/hr

d. 17.5 mr/hr OUESTION (B.2) [1.0]

You are the RO on duty during an experiment. You discover that the Core Excess Reactivity Worth is 2.08%

AK/K. What actions should be taken?

Scram the Rx / Notify the Rx Supervisor,

b. Shutdown the Rx / Notify the Senior Health Physicist.

c. Shutdown the Rx / Record the time of the shutdown in the Purpose Stamp.

d. No action required. Technical Specifications have not been violated.

l QUESTION (B.3) [1.0] l Which one of the following does NOT require NRC approval for changes?

c. License

b. Requalification plan

c. Emergency implementation Procedures

d. Emergency Plan

decuan es Normavemeroency rroceuures a nau uun rege eu QUESTION (B.4) [2.0]

r Match the general area radiation levels in column A with the corresponding 10 CFR 20 radiation area definition from column B. (Note: Only one answer per item in column A. Items in column B may be used more than once, or not at all.)

Golumn A Column B

a. 5 mrem /hr 1. Unrestricted

b. . 15 mrem /hr 2. Radiation

c. 165 mrem /hr 3. High Radiation

d. 205 mrem /hr 4. Very High Radiation QUESTION (B.5)' [1.0]

Which one of the following scrams is NOT required by Technical Specifications?

a. Linear channel i

b. Percent Power channel

c. Manual l

d. Period  !

QUESTION (B.6) [1.0]

Your annual dose received to date is 900 mrem. You are preforming maintenance on the reactor, in an area with a average dose rate of 30 mReria/hr. Which of the following is the longest you may work without exceeding the 10 CFR 20 TEDE limit? (Assume no committed dose.)

a. 13 hours1.50463e-4 days <br />0.00361 hours <br />2.149471e-5 weeks <br />4.9465e-6 months <br />

b. 17 hours1.967593e-4 days <br />0.00472 hours <br />2.810847e-5 weeks <br />6.4685e-6 months <br />

c. 136 hours0.00157 days <br />0.0378 hours <br />2.248677e-4 weeks <br />5.1748e-5 months <br />

d. 166 hours0.00192 days <br />0.0461 hours <br />2.744709e-4 weeks <br />6.3163e-5 months <br /> l

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-QUESTION (B.7) [1.0]

Prior to performing SOP-01, The Startup Checklist, how far back is the reactor operator required to review the - i l Main Log?.

• l' a. One full shift.

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b. 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or to the last tog entry for that operator whichever occurs first.

l c. 48 ho' urs or until the last log entry for that operzJor whichever occurs first.

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d. To the last time he or she operated the reactor.

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QUESTION (8.8) [1.0]

Who has the responsibility for locating and properly marking off any "high radiation" areas found within RRF7

a. Any operator.

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b. Only the Health Physicist.

c. . Only the Director of RRF.  ;

d. Only the Director of RRF or the Health Physicist.

QUESTION (B.9) [2.0]

Match the requirements for maintaining an active operator license in column A with the correct time period from column B.

Column A Column B

a. Renewal of license 1. 1 year i D. Medical Examination 2. 2 years 1

c. Requalification Written examination . 3. 4 years  !

d. Requalification Operating Test 4. 6 yep ~  !

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Section B Normal /Emeraency Procedures & Rad Con Page12 QUESTION (B.10) [1.0]

Which one of the following approvals are necessary for the experiment type defined in the following paragraph?

Those (experiments) which may be performed under the Technl cal Specifications and are not routine or modified routine experiments.

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a. Performed at the discretion of the Director with no further review necessary.

b. Performed at the discretion of the Director providing no new hazards are present beyond those allowed in Tech. Specs.

c. Performed at the discretion of the Director providing any hazards present beyond those allowed by Tech. Specs are approved by the Reactor Operations Committee.

d. Performed at the discretion of the Director after approval from the Reactor Operations Committee.

QUESTION (B.11) [1.0]

The following paragraph is a Reed Facility Emergency Plan definition.

Area for which offsite emergency planning is performed to assure that prompt and effective actions can be taken to protect the public in the event of an accident.

Which one of the following terms matches the above definition?

a. Restricted Area.

b. Site Boundary.

c. Emergency Planning Zone (EPZ).

d. Offsite Geographical Area.

QUESTION (B.12) [1.0]

Argon-41 is produced by neutron absorption of argon-40. Argon-41 decays by:

c: a 1.3 M'ev gamma with a half life of 1.8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.

b. a 6.1 Mev gamma with a half-life of 7 seconds.

c. neutron emission with a half-life of 1.8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.

d. a 1.3 Mev beta with a half-life of 7 seconds.

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QUESTION (B.13) . [1.0) I The Total Effective Dose Equivalent (TEDE) is defined as the sum of the deep-dose equivalent and the committed effective dose equivalent. The deep-dose equivalent is related to: l

a. the dose to organs or tissues.

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b. the external exposure to the skin or an extremity.  ;

c. the external exposure to the lens of the eye.

d. the extemal whole-body exposure. I 1

QUESTION (8.14) [1.0]

Which one of the following is the limit above which an area is defined as " contaminated"? I

a. 5 x 104 pcuries/100 cm 2 I

b. 5 x 10-8 pcuries/100 cm 2 l

c. 5 pcuries/100 cm 2 1

d. 5 mcuries/100 cm2 i I

i QUESTION (B.15) [1.0]

During the weekly checks of the primary coolant system, you ootain a conductivity reading of 3.0 mho/cm.

The primary system had been operating for 15 minutes prior to taking the reading. Which one of the following cetions should you perform next? )

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a. Allow the primary system to operate for another 30 minutes, then take another reading.

b. Allow the primary system to operate for another 60 minutes, then take another reading.

c. Inform the SRO, make preparations to replace the primary filters.

d. Inform the SRO, make preparations to backflush the demineralizers. )

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OUESTION (B.16) [1.0]

Per Reed's Emergency Iraplementation Procedures, where do facility personnel assemble when the Reactor Facility must be evacuated due to a fire?

a. Chemistry Laboratory

b. Reactor parking area

c. Director's Office, Chem 102

' d. Chemistry building hallway QUESTION (B.17) [1.0]

Following an irradiation of a specimen in the rotary specimen rack, the resulting radioisotope is expected to cqual 2,000 curies. The radioisotope will decay by the emission of two gamma rays per disintegration with energies of 1.10 Mev and 1.29 Mev.

Which one of the following is the radiation exposure rate (R/hr) at one (1) foot from the specimen with no shielding?

a. 17,028 R/hr

b. 28,680 R/hr

c. 34,056 R/hr

d. 57,360 R/hr QUESTION (B.18) [1.0)

Which one of the following requires a Radiation Work Permit (RWP)?

a. Whenever a sample is being removed from the Lazy Susan.

b. When entering a potential contaminated area.

c. Whenever the expected whole body dose is in excess of 5 mR.

d. Whenever the person performing the operation deems it necessary.

(*** End of Section B ***)

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QUESTION ' (C.1) - [1.0)

The neutron absorber in Reed's reactor control rods is:

a. Aluminum oxide

.b. Zirconium hydride

c. ' Graphite powder.

d. Boron carbide >

- QUESTION (C.2) [1.0]  ;

During performance of a power calibration (SOP 44) indicated power differed from calculated power by 15 Kwatts. Which one of the following actions is required for the Linear Power and Percent Power channels?

i e. Adjust the detector high voltage on the detectors. i 1

b. Adjust the compensating voltages on the detectors.

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c. Adjust the detectors height. '

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d. No adjustment necessary

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i QUESTION (C.3) [1.0]

Which ONE of the following is the flow through the primary loop and the cleanup loop?

c. 110 gpm total flow with 10 gpm through the cleanup loop b.- 120 gpm total flow with 20 gpm through the cleanup loop  !

c. 110 gpm total flow with 20 gpm through tha cleanup loop i i

- d. 120 gpm total flow with 10 gpm through the cleanup loop  !

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- QUESTION (C.4) [1.0) .

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> In what region of the Pulse Size vs. Applied Voltage characteristic curve does the fission chamber operate?  ;

s. Geiger Muller j

> b.' Limited Proportionality i

c. Proportional  ;

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d. lonization .;

QUESTlON (C.5) . [1,0] l Which ONE of the following statements correctly describes the pneumatic transfer system path and operating  :

pressure?  !

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a. The pneumatic transfer system exhausts to the reactor room and maintains the transfer system at a j positive pressure.

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' b.~ The pneumatic transfer system exhausts to the building exhaust and maintains the transfer system at a [

. positive pressure, j

c. The pneumatic transfer system exhausts to the reactor room and maintains the transfer system at a negative pressure. l t

d.' The pneumatic transfer system exhausts to the building exhaust and maintains the transfer system at a

. negative pressure.

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QUESTION (C.6) [10] f VWUch ONE of the' following radiation monitoring systems will cause a ventilation conf;nement actuation?

a. Particulate stack monitor f bi RAM i

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c. GSM i

d. CAM.- i

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Section C Plant and Rad Monitonno Systems eage it QUESTION (C.7) [1.0]

The rotary specimen rack contains 40 tubular aluminum containers. Of these 40,1 tube has a hole in the bottom. Which one of the following describes the reason for this hole.

a. To equalize pressure between the rack and tubes.

b. To detect moisture in the bottom of the rack.

c. To allow moisture buildup in the tubes to drain away.

d. To allow dry air flow to flow through the rack bottom.

QUESTION (C.8) [1.0]

Air contamination greater than the setpoint has been detected in the Reactor Room.

Which 'one of the following is the correct response by the ventilation system?

)

a. The supply system will automatically stop, dampers will direct air through filters purging the room at 150 cfm.

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b. The supply system will shift to high speed, dampers will direct the exhaust to the ventilation stack at i 150 cfm.  !

c. The exhaust system will shift to high speed, dampers will direct air through filters purging the room at 150 cfm.

d. The exhaust system will autometically stop, dampers will direct air through filters purging the room at 150 cfm.

QUESTION (C.9) [1.0)

Which ONE of the following interlocks will stop withdrawal of control rods?

c. Automatic control selected following two watts on the log-n channel.

b. Less than two counts per second on the startup channel.

c. A period less than 2 seconds.

d. Loss of one out of three signals to automatic reactor control.

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1 Section C Plant and Rad Monitorina Systems Pcgn 18 i

QUESTION (C.10) . [1.0]

Which one of the following occurs when the CAM reaches the " failsafe" setpoint?

c. Amber light on.  ;

b. Amber light off.

c. Amber light on and bell sounds.

d Amber light off and bell sounds.

QUESTION ~(C.11) [1.0) .

Each fuel-moderator element has a colored spacer at the top. Which one of the following describes the fuel folding of a particular element when the spacer is RED?

a. - Fully loaded.

b. 3/4 of fullload.

c.  % of fullload.

d. Graphite Dummy.

i l QUESTION (C.12) [2.0] ,

6 l Mitch the facility radiation detector in column A with the type of radiological problem it detects in column B.

- Column A Column B l c. RAM 1. Gases and Particulates l

l b. CAM 2. Particulates Only ,

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c. APM' 3. Radiation Level I

l d. GSM 4. Gases Only l

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dection U' mant ana Mac Monitonno systems Paga19 QUESTION (C.13) [1.0]

A reactor shutdown is being performed with the control servo in the Automatic Mode.

Which one of the following describes the method by which the control rods will be positioned to continue the shutdown when the regulating rod approaches 20% of its length?

a. The operator must shift the servo to manual, insert the regulating rod, and then insert the shim and safety rods.

b. The operator must shift the servo to manual, insert the shim and safety rods, and then retum the servo to automatic.

c. Both the shim and the safety rods should automatically drive in to assist in the power reduction. .

d. The operator should manually insert the shim or the safety rod to assist in power control with the servo in automatic.

QUESTION (C.14) [2.0]

Match the control rod drive mechanism part in column "A." with its function from column "B". (2 pts.) 1 Column A Column B

a. Pull rod 1. Provides rod bottom indication

b. Push rod 2. Provides rod position indication when the electromagnet engages the armature

c. Potentiometer

3. Provides rod full withdrawn indication

d. Piston

4. Works with dashpot to slow down rod travel near the bottom of its travel l

i QUESTION (C.15) [1.0)

Which one of the following would result from the continued' operation of the reactor systems with reactor tank water level 8 inches BELOW normal?  ;

e. Increase in depletion rate of demineralizers

b. Increase in control rod temperatures  !

c. Large increase in control rod drive speeds

d. Large increase in reactor water' bulk temperature  !

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dection G mant ano Mao Monitonno dvstems Pags 20 QUESTION (C.16) [1.0]

The return water from the primary coolant / purification system is ejected from an angled nozzle, which causes a swirling motion in the pool. Which ors of the following is the primary purpose for this design . .

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c. Increase the heat transfer rate due to increase convective flow.

b. Decrease the activation rate of O'8 to N'8 due to decrease time in the core.

c. Increase the transport time for N'8 to reach the surface of the pool.

d. Break up O'8 bubbles in the pool thereby decreasing the formation of N'8 QUESTION (C.17) [1.0]

When inserting a SCRAM signal to shutdown the reactor the operator forgets and leaves the rod control system in automatic mode. What will be the conditior, of the rods after three minutes?

a. All 3 rods will be on the bottom. The rod drive for the Shim rod will be fully out.

b. All 3 rods will be on the bottom. The rod drive for the Regulating rod will be all the way out.

c. The Safety and Regulating rods will be on the bottom. The Shim rod will be all the way out.

d. The Shim and Safety rods will be on the bottom. The Regulating rod will be all the way out.

QUESTION (C.18) [1.0]

According to SOP-03, what is the minimum power at which the linear po'wer range should be switched?

c. 80%

b. 70%

c. 60%

d. 50%

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! (*" End of Section C "*)

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ANSWER (A.1) a REFERENCE Reed RO Requalification Exam ANSWER (A.2) b REFERENCE Reed Training Manual (pg 5-15)

ANSWER (A.3) b, c REFERENCE REED Reactor Training Manual Sect.10.5.2 ANSWER (A.4) c REFERENCE Reed Training Manual (pg 12-5-5)

ANSWER (A.5) d REFERENCE Reed Training Manual, Ch. 9.5 ANSWER (A.6) b l REFERENCE REED Requalification Exa.7,88-89 ANSWER (A.7) I d

REFERENCE Reed Training Manual (pg 12-6/12-7) 1 ANSWER (A.8) c REFERENCE RRF Training Manual (pg 12-7-25)

~

ANSWER (A.9) c 1

REFERENCE 1987,1993 Reed Examination l

l

[.

{

rage et

-occuusin = iieu,v. i i i= o i iv = i =viiiiv vuoi =.. .y vi .=i =vi="mive ANSWER (A.10) c-REFERENCE.

Reed Training Manual, page 1-1.1 .

Reed Exam 1/93 ANSWER (A.11) d

. REFERENCE RRF Training Manual, page 10-1.

ANSWER (A.12)

._ b ,

REFERENCE Reed Reactor Facility Training Manual, Section 9.4, pg 9-5 P= Poe '".. '

2 = 1 e"'"

t = In 2 x 80 sec = 55.5 see ANSWER (A.13) d REFERENCE RRF Training Manual, page 10-6 and 10-7.

ANSWER (A.14) .

a -

REFERENCE RRF Training Manual, page 9-13 ,

t

ANSWER (A.15)  ;

I' b l l REFERENCE RRF Tech. Specs F.4

' $2.00 x 0.0075 = 0.015 AK/K -

. 0.015 AK/K / 0.0012 AK/K/sec = 12.5 seconds

' ANSWER (A.16) I

.c

. REFERENCE CR1/CR2= (1-Keff2)/(1-Keff1) l 15/45= (1-Keff2/(1-0.95) i L (0.05)(0.3333)= 1-Keff2.

K;ff2= 1- 0.016665= 0.983 l ,

e i

~

( section M w ineorv. inermo a t-acmtv uoeraunu urimiacterisuc= r ,go u ANSWER (A.17) -

.c.

REFERENCE SAR Section 2.1, pg 2-1 and Section 7.3, pg 7-5 ANSWER, (A.18)

. o.

REFERENCE

- Reed Reactor Facility Training Manual, Section 10.3, pg 10-6 and 10-7 ANSWER -- l(A.19)

~d REFERENCE ANSWER ' (A.20)

a. i REFERENCE  ?

i I

6

F Section B Normal /Emeraency Procedures & Rad Con Pag 3 24 ANSWER . (8.1)-

b ,

REFERENCE RRF Training Manual ch. 2

' ANSWER (8.2)

.d

-REFERENCE T.S. E.2 '

ANSWER (B.3) ,

c REFERENCE RRF 1990 RO Requalification Exam

.- ANSWER (B.4) a,2; b,2; c, 3 d, 3 REFERENCE 10 CFR 20.1003, Definitions ANSWER (B.5) d

REFERENCE:

Tech Specs, Table'l, page 9.

ANSWER (B.6) c ,

REFERENCE 10 CFR 20.1201

• ANSWER (B.7) d

REFERENCE:

Rr::d SOP-01, page 1.

ANSWER (B.8) a PEFERENCE '

Reed, SOP 21, Section 21.3.

j' -

ANSWER- _

(B.9)

a. 4; b. 2; c. 2; d.1 l ' REFERENCE

. 10CFR55.55; 10CFR55.57

_ -. .~ - . .

secnon is Normautmeroency Fromoures a Maa con .

Pags 25 4 h

' ANSWER- (B.10) :

'd  !

REFERENCE Reed, Administrative Procedures,Section IV.4.2 and 4.3, page 13.

t ANSWER > (B.11)

.c-REFERENCE '

Red Emergency Plan, Section 2.0, page 7.

'~ ANSWER ~ (B.12) .}

a- .

' t, REFERENCE..

' ANSWER (9.13) '

d~

' REFERENCE 10CFR20 /

ANSWER' (B.14) b 3

REFERENCE

~ SOP-23 Health Physics Wipe Tests ANSWER - (B.15) b REFERENCE

. SOP 70, Weekly Checks. l ANSWER- . (B.16) -  !

, c REFERENCE Emergency Plan '  !

ANSWER ~ (B.17)

-b REFE'ENCER Reed Reactor Facility Training Manual, Section 5.4, pg 5-18; SAR Section 7.6, pg 7-8 CALCULATION: j R=6CEn 1 R = 6 (2000 ci) (1,10 + 1.29 Mev) (1 disintegration)

R = 28,680 R/hr 1

-l ANSWER. (B.18) l c  ;

,; REFERENCE-SOP-28, Radiation Work Permits,28.2

7 ;-----

Pag 3 20 cectioli o riatti attu tsau tyturittutistu ovdtetish ANSWER (C.1) d REFERENCE GA TRIGA Maintenance and Operating Manual ANSWER (C.2) c REFERENCE SOP 44, Power Calibration.

ANSWER (C.3) b REFERENCE GA TRIGA Mechanical Maintenance and Operating Manual ANSWER (C.4) c REFERENCE RRF Introduction to Radioactivity (pg 12-1-25 & 2-31)

ANSWER (C.5) d s REFERENCE RRF Description and SAR (pg 5-7)

ANSWER (C.6) c, d REFERENCE RRF Emergency Plan ANSWER (C.7) b REFERENCE R:ed, Maintenance and Operating Manual, page 30.

ANSWER /1 (9 a

REFERENCE Reed SAR, page 4-5 ANSWER (C.9) b REFERENCE RI:ed Technical Specification, Table 11, page 9 i

UCVitut t u e eat et op lu f %cu tyIVI titUf fi tu OYelet t td rage it d

ANSWER (C.10) b REFERENCE Reed SOP-70, Section 70.7.3.2 ANSWER (C.11) c REFERENCE Reed, Mechanical Maintenance and Operating Manual, Page 11.

ANSWER (C.12) a,3; b,1; c,2; d,4 REFERENCE SOP-30, Cal. of RAM; SOP-31, Cal. of CAM; SOP-32, Cal of APM; SOP-33, Cal. of GSM ANSWER (C.13) d REFERENCE SAR Section 5.3.2, pg 5-14 SOP 03, Section 3.7.2.3 and 3.7.4.3, pg 3 and 4 ANSWER (C.14) a,1; b,3; c,2; d,4 ANSWER (C.15) a REFERENCE TRIGA Mark l Reactor Mechanical Maintenance and Operating Manual, Section 5.11.3, pg 81 ANSWER (C.16) c REFERENCE Examiner Notes from previous examinations ANSWER (C.17) b REFERENCE Facility comment from NRC examination administered Jar uary,1995.

ANSWER (C.18) d REFERENCE SOP-03 Reactor Operations, Step 3.7.1.8

_ _.