ML20247N096

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NRC Operator Licensing Exam Rept 50-288/OL-98-01 (Including Completed & Graded Tests) for Tests Administered on 980505-07
ML20247N096
Person / Time
Site: Reed College
Issue date: 05/18/1998
From: Isaac P
NRC (Affiliation Not Assigned)
To:
Shared Package
ML20247N077 List:
References
50-288-OL-98-01, 50-288-OL-98-1, NUDOCS 9805270048
Download: ML20247N096 (21)
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Text

r__-.-___________._ ________

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! Reed College Docket No. 50-288 l

cc: .

l Mayor of City of Portland I 1220 Southwest 5th Avenue l Portland, Oregon 97204 David Stewart-Smith, Administrator I l Oregon Office of Energy Energy Resources Division 625 Marion Street, NE  !

l Salem, Oregon 97310 l

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9805270048 980518 k l

PDR ADOCK 05000288 i '

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U. S. NUCLEAR REGULATORY COMMISSION OPERATOR LICENSING INITIAL EXAMINATION REPORT REPORT NO.: 50-288/OL-98-01 FACILITY DOCKET NO.: 50-288 FACILITY LICENSE NO.: R-112 FACILITY: Reed College EXAMINATION DATES: May 5 - 7,1998 EXAMINER: Patrick c, Chief Examiner SUBMITTED BY: d Se o- 88 6 P issac ' e ' Examiner / D' ate

SUMMARY

During the week of May 4,1998, NRC administered Operator Licensing Examinations to seven Reactor Operator (RO) and two Senior Reactor Operator Upgrade (SROU) candidates.

All candidates passed their respective examinations.

ENCLOSURE 1

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1 2-l BEPORT DETAILS

1. Examiners:

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. Patrick Isaac, Chief Examiner

!' Paul V. Doyle i

l 2. Results: -

I RO PASS / Fall SRO PASS / Fall TOTAL PASS / Fall Written 7/0 0/0 7/0 Operating Test 7/0 2/0 9/0 Overall 7/0 2/0 9/0

3. Exit Meeting:

Personnel attending:

Mr. Christopher S. Melhus, Assistant Director, Reed College Reactor Patrick J. Isaac, Chief Examiner Paul V. Doyle, NRC Examiner The facility examination comments were discussed as noted in Enclosure 2.

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NRC RESOLUTIONS -WRITTEN EXAMINATION QUESTION (A.18)

In a just critical reactor, removing one do!!ar w'xth of reactivity will cause:

l a. The resultant period to be a function of the prompt neutron lifetime.

b. The prompt neutron term to become unimportant
c. The reactor period to be equal to 10-n1 Ap
d. A sudden drop in neutron flux.

ANSWER: a Facility Comment.

The answer key (answer a) assumes the positive reactivity has been added, bringing the reactor prompt critical. The wording of the question " removing one dollar worth of reactivity" is likely to be interpreted as removing positive reactivity, i.e., adding negative reactivity. In that case answer d or possibly b would be the best answer.

We recommend that the question be deleted from the exam and clarified in future exams.

NRC Resolution:

Comment Accepted. Question A.18 will be deleted from the examination.

QUESTION (C.2)

Whith the power control servo is in the Automatic Mcde, which one of the choices below completes the following statement?

The control servo will increase reactor power at a constant period of based on the reactor power detected by the

a. +30 seconds; log-n channel
b. +30 seconds; linear micromicroammeter channel
c. +10 seconds; log-n channel
d. +10 seconds; linear micromicroammeter channel ANSWER: b ENCLOSURE 2

Facility Comment:

Three items of interest on this question. First, although the SAR states that approximately a 30 second period is maintained, our servo maintains a 10-30 second period.

Second, although it is the intent of the question to ask what instrument provides the power level to be maintained, it is possible to read the question as asking what instrument detects the power used for the period. One of our candidates thought the question was asking "What period is maintained and what instrument is used for the period."

Third, note the typo "With" and the extra word "is' in the first sentence.

Due to the first two items, any of the four answers could be selected.

We recommend that the question be deleted from the exam and clarified in future exams.

NRC Resolution:

Comment Accepted. Question C.2 will be deleted from the examination.

QUESTION (C.16) >

Which ONE of the following could cause damage to the CAM detection device?

a. - Water level too high in the reactor pool.
b. Leaving the CAM toggle switch in " test" too long.
c. Detector high voltage set too low.
d. Loss of low voltage power supply with high voltage still applied to the detector.

ANSWER: a Facility Comment:

, We changed to a new CAM at the facility in January and thought that we had corrected all references to the old CAM in the procedures. This question came from a procedure on pool water level that we did not revise (since it wasn't apparent from the subject that it referred to the CAM). The new CAM draws air from several feet above floor level, not under the grid j

. plates, therefore high water level would not affect it.

l None of the attematives for this question are correct.

We recommend that the question be deleted from the exam and future exams.

NRC Resolution:

Comment Accepted. Question C.16 will be deleted from the examination.

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i U. S. NUCLEAR REGULATORY COMMISSION NON-POWER INITIAL REACTOR LICENSE EXAMINATION FACILITY: REED College REACTOR TYPE: TRIGA DATE ADMINISTERED: 05/05/98 REGION: IV CANDIDATE:

INSTRUCTIONS TO CANDIDATE:

Answers are to be written on the answer sheet provided. Attach all answer sheets to the examination. Point values are indicated in parentheses for each question. A 70%

in each category is 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 A. REACTOR THEORY, THERMODYNAMICS 19.00 _;L;L;L AND FACILITY OPERATING CHARACTERISTICS 20.00 - 35.1 B. NORMAL AND EMERGENCY OPERATING PROCEDURES AND RADIOLOGICAL CONTROLS 18.00 _31,6 . C. FACILITY AND RADIATION MONITORING SYSTEMS 60.00-  % TOTALS FINAL GRADE All work done on this examination is my own. I have neither given nor received aid.

Candidate's Signature ENCLOSURE 3

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' A. RX THEORY. THERMO & FAC OP CHARS i ANSWER SHEET

= Multiple Choice (Circle or X your choice) .

' If you change your answer, write your selection in the blank.

f I

MULTIPLE CHOICE L

001 abcd 002 a b c d 003 a b c d 004 a b c d 005 a b c d 006 a b c d 007 a b c d 008 a b c d ]

009 a b c d 010 a b c d 011 a b c d.  ;

012 a b c d l 013 a b c d 014 a b c d 015 a b c d 016 a b c d 017 a b c d l

018 a b c d l

l 019 a b c d 020 a b c d

(**"* END OF CATEGORY A *****)

B: NORMAUEMERG PROCEDURES & RAD CON ANSWER SHEET Multiple Choice (Circle or X your choice)

If you change your answer, write your selection in the blank.

MULTIPLE CHOICE 001 abcd 002 a b c d 003 a b c d 004 a b c d 005 a b c d j

006 a b c d 007 a b c d 1

008 a b c d 009 a b c d 010 a b c d 011 a b c d 012 a b c d 013 a b c d 014 a b c d l~ 015 a b c d 016 a b c d

= 017 a b c d I

018 a b c d 019 a . b c d 020 a b c d

(*"** END OF CATEGORY B ***")

",, /.

C. PLANT AND RAD MONITORING SYSTEMS ANSWER' SHEET Multiple Choice (Circle or X your choice)

If you change your answer, write your selection in the blank.

MULTIPLE CHOICE l

001 abcd 002 a b c d 003 a b c d 004 a . b c d 005 a b c d 006 a b c d 007 a b c d 008 a b c d 009 a b c d 010 a b c d 011 abcd 012 a b c d 013 a b c d 014 a b c d 015 a b c d 016 a b c d 017 a b c d 018 a b c d 019 a b c d l

("*" END OF CATEGORY C "*")

("""**" END OF EXAMINATION """"")

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NRC RULES AND GUIDELINES FOR LICENSE EXAMINATIONS During the administration of this examination the following rules apply:

I j 1. Cheating on the examination means an automatic denial of your application and could result in more l severe penalties.

2. After the examination has been completed, you must sign the statement on the cover sheet indicating that the work is your own and you have neither received nor given assistance in completing the examination. This must be done after you complete the examination.
3. Restroom trips are to be limited and only one candidate at a time may leave. You must avoid all contacts with anyone outside the examination room to avoid even the appearance or possibility of cheating.
4. Use black ink or dark pencil QDk to facilitate legible reproductions.

l 5. Print your name in the blank provided in the upper right-hand corner of the examination cover sheet l and each answer sheet.

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l 6. Mark your answers on the answer sheet provided. USE ONLY THE PAPER PROVIDED AND DO NOT WRITE ON THE BACK SIDE OF THE PAGE.

l L 7.- The point value for each question is indicated in [ brackets) after the question.

8. If the intent of a question is unclear, ask questions of the examiner only.
9. When tuming in your examination, assemble the completed examination with examination questions, l examination aids and answer sheets. In addition tum in all scrap paper.
10. Ensure allinformation you wish to have evaluated as part of your answer is on your answer sheet.

Scrap paper will be disposed of immediately following the examination.

11. To pass the examination you must achieve a grade of 70 percent or greater in each category.
12. There is a time limit of three (3) hours for completion of the examination.
13. When you have completed and turned in you examination, leave the examination area. If you are observed in this area while the examination is still in progress, your license may be denied or revoked.

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EQUATION SHEET l = sc b T = A bH = UA b T {p g}2 2a(k)#

1 l' = 5 x 10~* seconds g g l SCR = =

l

-p 1 -K,f f l A,,f = 0.1 seconds ~2 l

CR, ( 1 -K,ff, ) = CR 2I 1 ~Kert,)

5 = 0.0075 C#1 I ~P ) = CR2 I -P2 )

1 l 1 1 1-K 1

'" M*

1 S UR = 2 6. 0 6 y_g e-p .u,  ;

I 1 CR 1 P=P 10 sun t o M_ _

- 0 1-K,g CR, t

SDM = (1-K*ff) l P=P e' eff f* p= S (1 -p) 7= p' p-J S-P K ,,,, - K ,,,, g_

gp _

k,,, x K,f, p A,,,p 0.693 ( K,,,-1 )  !

i T9 =

p=

x eff D R =DR, e ~h' DR,d,# = DR,d,#

1 6CIE(n) IP2 -0) =

(Pi -0)

DR =

y2 Peak, Peak,

! I = I,e~"

l 1 Curie = 3.7 x 10 dis /sec 1 kg = 2.21 lbm 1 BTU = 778 ft-lbf *F = 9/5 "C + 32 1 gal (H2 O) = 8 lbm *C = 5/9 (*F - 32) cp = 1.0 BTUllbml"F c, = 1 callsecIgmI*C

Page 1 Section A* a Theorv. Thermo & Fac. Ooeratina Characteristics Question (A.1) [1.0]

' Which ONE of the following combinations of characteristics make a good reflector?

Scattering Cross Section Absorption Cross Section

a. High High
b. Low High
c. High Low
d. Low Low Question (A.2) [1.0]

The count rate is 50 cps. An experimenter inserts an experiment into the core, and the count rate decreases to 25 cps. Given the initial K, of the reactor was 0.8, what is the worth of the experiment?

a. negative 0.42
b. positive 0.42
c. negative 0.21
d. positive 0.21 Question (A.3) [1.0]

Given the lowest of the high power scrams is 110%, and the scram delay time is 0.5 sec.

Approximately how high will reactor power get during a 20 second power excursion?

fWS

b. 116 %
c. 124 %
d. 225%

, .l, Section A: R Theorv. Thermo & Fac. Ooeratina Characteristics Page 2 l Question (A.4) [1.0]

1 l Which ONE of the following is the dominant factor in determining differential rod worth?

a. Axial and Radial Flux.

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b. Total Reactor Power l
c. Rod speed
d. Delayed neutron fraction 1

Question (A.5) [1.0)

Which ONE of the following is the MAJOR source of energy re:: overed from the fission process?

a. Kinetic energy of the fission neutrons
b. Kinetic energy of the fission fragments
c. Decay of the fission fragments
d. Prompt gamma rays l

l Question (A.6) [1.0]

Which statement illustrates a characteristic of Subcritical Multiplication?

a. As Keff approaches unity (1), for the same increase in Keff, a greater increase in neutron population occurs.
b. The number of neutrons gained per generation gets larger for each succeeding generation.
c. The number of fission neutrons remain constant for each generation.
d. The number of source neutrons decreases for each generation.

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Page 3 Section A: R Theorv. Thermo & Fac. Ooeratina Characteristics Question (A.7) [1.0]

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

' excess is $2.5 . Calculate the Shutdown Reactivity with the Shim rod stuck all the way out.

a. $3.0
6. $3.5
c. $6.0 l
d. $7.25 Question (A.8) [1.0]

Which ONE of the following statements describes Count Rate characteristics after a control rod withdrawal with the reactor suberitical? (Assume the Rx remains subcritical.)

a. Count Rate will rapidly increase (prompt jurrp) then gradually increase to a stable value.
b. Count Rate will rap:dly increase (prompt jump) then gradually decrease to the previous value,
c. Count Rate will rapidly increase (prompt jump) to a stable value, i
d. There will be no change in Count Rate until criticality is achieved.

Question (A.9) [1.0) l Most nuclear text books list the delayed neutron fraction (p) as being 0.0065Ap. Most research l reactors however have an effective delayed neutron fraction (p ) of 0.0070 Ap. Which ONE  !

of the following is the reason for this difference?

a. Delayed neutrons are born at higher energies than prompt neutrons resulting in a greater worth for the neutrons.
b. Delayed neutrons are born at lower energies than prompt neutrons resulting in a greater worth for the neutrons.
c. The fue! includes Uzu which has a relatively large p for fast fission.
d. The fuel includes U " which via neutron absorption becomes Pu2 " which has a larger p for fission.

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l Section A: R Theory. Thermo & Fac. Ooeratina Characteristics Page 4 Question (A.10) [1.0) l JF;L&SJ1C_SCAIZEBlNQ is the process by which a neut.on collides with a nucleus and ...

a. recoils with the same kinetic energy thar. it had prior to the collision
b. recoils with the a lower kinetic energy thar it had prior to the collision
c. is absorbed, with the nucleus emitting a gamma ray.

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d. recoils with a higher kinetic energy than it had prior to the collision, with the nucleus emitting a gamma ray.

Question (A.11) [1.0]

l Which ONE of the following is the reason for an installed neutro' source within the reactor? A '

startup without a neutron source ... j

a. is impossible as there would be no neutrons available to start the fission process,
b. would be very slow due to the long time to build up neutron population from so low a level.
c. could result in a very short period due to the reactor going critical before neutron l population can build up high enough to be read on nuclear instrumentation. '
d. can be compensated for by adjusting the compensating voltage on the source range detector.

l Question (A.12) [1.0]

An element decays at a rate of 20% per day. Determine its half-life.

a. 3 hr.
b. 75hr.
c. 108 hr. l l
d. 158 hr.

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L _ __ - _ _ - _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ -_- __._____- _ _ - _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

h-r , A R Theorv. Thenno & Fac. Ooeratina Characteristics Page 5 Question (A.13)- [1.0]

The reactor is operating at 150 KW The reactor operator withdraws the Regulating Rod adding

$0.50 of reactivity and 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. the same period due to equal amounts of reactivity being added.

b.' a shorter period due long lived delayed neutron precursors.

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c. the same period due to equal reactivity rates from the rod.
d. a longer period due to long lived delayed neutron precursors.

l Question (A.14) [1.0]

Which statement best describes Xe-135 behavior following a Rx Scram?

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a. ' Xenon concentration decreases due to production rate from fission stops
b. Xenon concentration decreases due to production rate from l-135 decay increasing.  ;
c. Xenon concentration increases due to production rate from Pm-149 increasing.
d. Xenon concentration increases due to 1-135 decay exceeding Xe-135 decay.

Question (A.15) [1.0]

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

a. 238U to absorb neutrons over a wider range, thus decreasing the number of neutrons -

available for fission with 235U.

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b. Doppler resonance effects to decrease.
c. The hydrogen atoms in the ZrH2 to slow down more neutrons.

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d. More thermal neutron absorption by the moderator.

Section A: R Theorv. Thermo & Fac. Ooeratina Characteristics Page 6 Question (A.16) [1.0]

The reactor has been stable at 20 Watt for about an hour. Removing the source from the core causes reactor power to:

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a. Decrease since the reactor is undermoderated
b. Increase due to an increase in the amount of moderator, j
c. Stay the same due to Keff being constant.
d. Decrease due to fast neutron non-laakage probability increases.

Question (A.17) [1.0) l Why does the effect on reactivity by the Fuel Temperature Coefficient (FTC) decrease as fuel temperature increases?

a. The water density decreases, causing the neutron resonance escape probability (p) to decrease.

l b. The neutron thermal utilization factor (f) predominates in its effect on the neutron life i cycle. i

c. The neutron energy resonance absorption peaks broaden less for the same degree of fuel temperature change.
d. More neutrons leak out of the core.

l Question (A.18) [1.0) Deleted in t just critical reactor, removing one dollar worth of reactivity will cause:

a. The resultant period to be a function of the prompt neutron lifetime.
b. The prompt neutron term to become unimportant
c. The reactor period to be equal to {S-p1 AP
d. A sudden drop in neutron flux.

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Rardian A: R Theorv. Thermo & Fac. Ooeratina Characteristics Page 7 )

Question (A.19) [1.0)

Which statement best describes the heat transfer mechanism at the Reed College Reactor?

a. From the fuel center line, heat is transferred to the surface of the fuel rod by convection- l and is carried into the coolant by conduction. l
b. Heat is transmitted to the fuel rod surface by thermal radiation and carried to the coolant 3 by conduction. {
c. Heat conducted to the surface of a fuel rod is carried into the coolant and out of the system by convection.
d. The temperature distribution from the fuel center line to the coolant is linear.

- Question (A.20) [1.0]

A mixed beta-gamma point source measures 200 mrem /hr at one foot and 0.1 mrem /hr at 20 feet. The beta emission has an energy of 1.0 MeV. What is the fraction of betas in the source?

a. 10%
b. 20 %
c. 80 %
d. 90 %

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Section B: Normal /Emera. PrWwas & Rad Con- Page 8 Question (B.1) [1.0).

- A small radioactive source is to be stored in the reactor building. The source is estimated to contain % curies isnd emit a 1.33 Mov gamma.

Assuming no shielding was to be used, a Radiation Area barrier would have to be erected from j the source at a distance of approximately;

- a. - 28 feet i

b. 22 feet I
c. . 17 feet L d. 2 feet QUESTION (B.2) [1.0)

A room contains a source which, when exposed, results in a general area dose rate of 175 millirem per hour. This source is scheduled to be exposed continuously for 35 days. Select an acceptable method for controlling radiation exposure from the source within this room,

a. Post the area with the words " Danger-Radiation Area".
b. Equip the room with a device to visually display the current dose rate within the room.

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Equip the room with a motion detector that will alarm in the control room.

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d. Lock the room to prevent inadvertent entry into the room.

l- Question (B.3) [1.0)

Which of the following does NOT require NRC approval for changes?

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a. License l

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b. Requalification plan
c. Emergency implementation Procedures
d. Emergency Plan i

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Page 9 h+ian B: Normal /Emera. Procedures & Rad Con Question (B.4); [1.0]

Consider two point sources, each having the same curie strength. Source A's gammas have an energy of 1 MEV whereas Source B's gamma have an energy of 2 MEV. You obtain a reading from the same Geiger counter 10 feet from each source. Concerning the two readings, which one of the following statements is correct?

a. . The reading from Source B is four times that of Source A.
b. The reading from Source B is twice that of Source A.
c. Both readings are the same,
d. The reading from Source B is half that of Source A.

QUESTION (B.5) (1.0]

Which one of the following is the definition for " Annual Limit on intake" (ALI)?

a. 4 The concentration of a radionuclides in air which, if inhaled by an adult worker for a year, results in a total effective dose equivalent of 100 millirem.
b. 10 CFR 20 derived limit, based on a Committed Effective Dose Equivalent of 5 rems whole body or 50 rems to any individual organ, for the amount of radioactive material inhaled or ingested in a year by an adult worker.

. c. The effluent concentration of a radionuclides in air which, if inhaled continuously over a year, would result in a total effective dose equivalent of 50 millirem for noble gases.

d. Projected dose commitment values to individuals, that warrant protective action following a release of radioactive material.

QUESTION (B.6) [1,0]

_' In order to ensure the health and safety of the public,10CFR50 allows the operator to deviate from Technical Specifications. What is the minimum level of authorization needed to deviate -

from Tech. Specs?

a. USNRC
b. Reactor Supervisor
c. Licensed Senior Reactor Operator.
d. ' Licensed Reactor Operator.

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l-Section B: ' Normal /Emera. Procedures & Rad Con Page 10 Question (B.7) [1.0) l In the event of a ' pool level alarm and visual indication of abnormal loss of pool water, which l ONE of the following actions is the reactor operator NOT allowed to perform if he is the L

Emergency Coordinator.

a. Shutdown the reactor l
b. Isolate the Pool
c. Notify a member of the ENCL l
d. Terminate the emergency I

Question (B.8) [1.0]

In accordance with Technical Specifications, which ONE of the following statements is TRUE7

a. Each fuel experiment shall be controlled such that the total inventory of lodine isotopes i 131 thru 135 in the experiment is no greater than 1.5 curies.

l b. The reactivity worth of any individual in-core experiment shall not exceed $2.00. 1

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c. Experiments containing materials corrosive to Rx components shall not be irradiated in the Rx.
d. Explosive experiments shall be doubly encapsulated Question (B.9) [1.0]

Which ONE of the following conditions is a violation of Technical Specifications, Rx Pool?

a. Conductivity of the pool water is 2 mhos per centimeter averaged over one month.
b. Radioactivity in the pool water is 0.2 micro Ci/ml.
c. Pool water ph is 5.7 i 1
d. Bulk temperature of the coolant is 45 degrees C during reactor operation.

l L_____________________________________________._____________-.______ - - _ _ _ . _ _ - - - _ _ - - - _ - _ - - - - - - - - - - - - - - - - - - - - --

4 Page 11 Sae+ inn 8: Normal /Emera. Preariures & Rad Con Question (B.10) [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) 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 Question (8.11) [1.0]

You are the RO on duty during an experiment. You discover that the Core Excess Reactivity Worth is 2.30% delta-K/K.

What actions should be taken?

a. 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.

Question (B.12) ['1.0]

Per Reed's Emergency implementation 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

L-Section B: Normal /Emera. Procedures & Rad Con Page 12 i Question (B.13) [1.0)

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

a. Linear channel
b.  % power channel
1 i

! c. Manual '

d. Log channel l

Question (B.14) [1.0)

While performing SOP 01, The Start-up Checklist, the operator places the Count Rate Channel switch to one of the calibrate positions and attempts to raise a control rod. The Source light illuminates and you note rod motion. Which one of the following describes what was just observed?

The operator checked the:

a. Source Interlock is inoperable,
b. Source Interlock is operable.
c. Rod Raising Interlock is inoperable.
d. Rod Raising interlock is operable.

Question (B.15) [1.0]

For training purposes, reactor power was increased from 400 watts to an equilibrium power

! 98% of the license limit in accordance with SOP 03, Reactor Operations. Which one of the following describes this power increase? l

a. The power increase is within all prescribed procedures and Tech. Specs.
b. The power increase is within all prescribed procedures and Tech. Specs. but violates l good practice. i
c. It violates SOP 03, but not Tech. Specs.

- d. It violates SOP 03 and Tech. Specs.

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Page 13 Section B: Normal /Emera. Procedures & Rad Con Question (8.16) [1.0)

The REED TRIGA reactor has been shutdown due to a fuel element leak. Which one of the following radioactive gases poses the most significant hazard during the search for the leaking fuel element?

a. Nitrogen 16
b. Tritium
c. Xenon 135
d. Argon 41 Question (B.17) [1.0]

In accordance with the Reed Emergency implementation procedures, which one of the following is the minimum number and type of portable survey meters required for reactor operation?

a. 1 GM and 1 Scintillation.
b. 1 GM and i lon chamber.
c. 2 GM and 1 Scintillation.
d. 2 GM and 1 lon chamber.

Question (B.18) [1.0]

The following paragraph is a Reed Facility Emergency Plan definition:

...that boundary, not necessarily having restrictive barriers, including the adjoining Chemistry Building and extending 250 feet in every direction from the operations boundary.

Which one of the following terms matches the above definition?

a. Restricted Arec.
b. Site Boundary.
c. Emergency Planning Zone (EPZ).
d. Offsite Geographical Area.

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Section B: Normal /Emera. Procedures & Rad Con Page 14 Question (B.19) [1.0)

A change to SOP 40, Fuel Element inspection, is required at Step 40.7.1, Procedure for Moving l-Fuel from the Core to the Viewing Periscope. Which one of the following is required for the l

procedure change to be implemented? -

d l .

a. Implement immediately with Reactor Supervisor concurrence.
b. . Implement immediately with Director's concurrence.
c. Implement after Director's approval with Reactor Safety Committee approval within 14 days.

L d. Implement only after Reactor Safety Committee and/or the Radiation Safety Committee j approval.

l l Question (B.20) [1.0]

l-Reed's Technical Specifice' ions and operating procedures require the reactor to be shutdown if

' the reactor pool temperature exceeds a specified limit.

Which one of the following is the LOWEST temperature that EXCEEDS the Tech. Spec. limit?

a. 50 degrees F
b. 45 degrees C l
c. 50 degrees C
d. 120 degrees F l

Page 16

'hreinn C Plant and Rad Monitorina Svstems Question (C.1)' [1.0]

Which one of the following nuclear channels provides the operator with a continuous record of neutron flux from approximately one watt to full power?

a. Period channel b.- Count rate channel
c. - Linear power channel
d. Log power channel Question' (C.2) [1.0) - Deleted Whita the power control servo is in the Automatic Mode, which one of the choices below completes the following statement?

based The control servo will increase reactor power at a constant period of on the reactor power detected by the .

a. +30 seconds; log-n channel
b. +30 seconds; linear micromicroammeter channel
c. +10 seconds, log-n channel

^d. +10 seconds; linear micromicroammeter channel

. Question (C.3) [1.0]

The pool water level must be maintained at a specified level for proper skimmer operation. Why is this pool level necessary?

a. Above this pool level, the reactor water system pumps will lose suction and fail.
b. Below this level, air entry could interfere with proper operation of the rabbit tube.

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c. Above this level, the water pressure could damage the purification system filters.
d. Below this level, air entry could damage the purification system demineralizers.

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Section C: Plant and Rad Monitorina Systems Page 16 Ques' ion (C.4) [1.0)

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

l l a. Automatic control selected following two watts on the log-n channel,

b. Less than two counts per second ori the startup channel.
c. A period less than 2 seconds,
d. Loss of one out of three signals to automatic reactor control.

Question (C.5) - [1.0]

Which ONE of the following statements correctly describes the pneumatic transfer system path

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

l l . b. The pneumatic transfer system exhausts to the building exhaust and maintains the transfer systern at a positive pressure.

c. The pneumatic transfer system exhausts to the reactor room and maintains the transfer system at a negative pressure,
d. The pneumatic transfer system exhausts to the building exhaust and maintains the

!; transfer system at a negative pressure.

Quastion (C.6) [1.0)

When a compensated ion chamber is used for neutron detection, how is the gamma flux accounted for?

a. Pulse height discrimination is used to cancel the gamma flux.
b. The gamma flux is proportional to neutron flux and is counted with the neutrons.
c. The gamma flux is cancelled by creating an equal and opposite gamma current.

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d. The gamma flux passes through the detector with no interaction because of detector design.

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Page 17 Section C: Plant and Rad Monitorina Systema j Question (C.7) [1.0]

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' Which one of the following describes the radiation to which the lon Chamber, Model RO-2 is sensitive?

a. Beta only.
b. Beta and Gamma only.
c. Beta and Alpha only.
d. Beta, Gamma, X-ray and Alpha only.

Question (C.8) [1.0]

When calibrating the Gaseous Stack Monitor, the supervisor can authorize a change to the alarm setpoint values. Which one of the following describes the rules that govern the changing of the setpoint values?

The setpoint values may be changed providing:

a. the Failsafe setpoint is less than the Alarm setpoint AND the Alarm setpoint is less than 1000 cpm.
b. the Failsafe setpoint is less than the Alarm setpoint OR the Alarm setpoint is less than 1000 cpm.
c. the Failsafe setpoint is greater than the Alarm setpoint AND the Alarm setpoint is less than 1000 cpm.
d. the Failsafe setpoint is greater than the Alarm setpoint OR the Alarm setpoint is less than 1000 cpm.

Question (C.9) [1.0]

Which ONE of the following describes the action of the rod control system to drive the magnet draw tube down after a dropped rod?

a. Deenergizing the rod magnet initiates the rod down motion of the draw tube.
b. Actuation of the MAGNET DOWN limit switch initiates the rod down motion of the draw tube.
c. Actuation of the ROD DOWN limit switch initiates the rod down motion if the rod drive is withdrawn.
d. Resetting the scram signal initiates the rod down motion of the draw tube.

L Section' C: Plant and Rad Monitorina Svatoms Page 18 Question (C.10) [1.0)

Which ONE of the following statements describes the drive speeds of the shim ' rod, Regulating rod and Safety rod? -

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a. ' The Shim rod drives at 24 inches per minute, the Regulating and Safety rods drive at 19 L inches per minute.
b. The Shim and Regulating rods drive at 24 inches per minute,' the Safety rod drives at 19

! inches per minute.

j- - c. . The Safety rod drives at 24 inches per minute, the Regulating and Shim rods drive at 19 inches per minute.

. d. The Regulating rod drives at 24 inches per minute, the Safety and Shim rods drive at 19 inches per minute. i i

Question (C.11)- [1.0) )

I Which ONE of the following statements correctly describes the purpose of the potentiometer in the control rod drive assembly.

L . a. Provides rod position indication when the electromagnet engages the connecting rod j armature.

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b. Provides a variable voltage to the rod drive motor for regulating control rod speed. '

[ c. Provides potential voltage as required for resetting the electromagnet current. j l

d. Provides the potential voltage to relatch the connecting rod.

L Question (C.12). [1.0] j i

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

L 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.

l The supply system will shift to high speed, dampers will direct the exhaust to the ll b.

l ventilation stack at 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 automatically stop, dampers will direct air through filters purging

- the room at 150 cfm.

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Section C: Plant and Rad Monitorina Systems Page 19 Question' (C.13) [1.0]

Which ONE of the following completes the following statement?

. The fuelin the Reed reactor is a mixture of uranium-

% by weight of uranium enriched to  %.

hydride alloy containing

a. heterogeneous, graphite,20,8.5
b. heterogeneous, zirconium, 8.5,20
c. homogeneous, graphite,20, 8.5
d. homogeneous, zirconium,8.5,20 Question (C.14) [1.0]

Limit switches mounted on each drive assembly provide switching for cor. sole lights.

Which one of the statements is FALSE 7

a. The DOWN light indicates that the centrol rod and rod drive are at their lower limits.
b. The UP light indicates that the control rod and rod drive are at their upper limits.
c. When the CONT /ON pushbuttons are depressed, the ON lights are extinguished.
d. The CONT side light of the CONT /ON switch goes off less than one second after a scram occurs.

Question (C.15) [2.0]

Match the facility radiation detector in column A with the type of radiological problem it detects ,

in column B.

\

l Column A Column B

a. RAM 1. Gases and Particulate l
b. CAM 2. Particulate Only
c. APM 3. Radiation Level ,
d. GSM 4. Gases Only l l

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!* ... . ; j Sechon C: Plant and Rao Monitorng Systems Page 20

Question (C.16) -[1.0] Deleted

!- - Which ONE of the following could cause damage to the CAM detection device?

a. _ Water level too high in the reactor pool,
b. Leaving the CAM toggle switch in " test" too long.
c. Detector high voltage set too low.

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d. Loss of low voltage power supply with high voltage still applied to the detector.

Question (C.17) [1.0)

The upper end fixture of each fuel element consists of a .

l a. knob for attaching the fuel handling tool and a rectangular spacer to prevent the fuel L handling tool from damaging the fuel cladding

b. - knob for attaching the fuel handling tool and a triangular spacer to allow cooling water to flow through the upper grid plate
c. a rectangular spacer to allow the top grid to provide lateral supwrt and a triangular l opening to allow sampling for fuel element failure

! d. a triangular spacer to allow the top grid to provide lateral support and a rectangular opening to allow sampling for fuel element failure Question (C.18) [1.0) l' 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 insett j

the shim and safety rods.

l.

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

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l' Rardian C: Plant and Rad Monitorina Systems Page 21 Question (C.19) [1.0) i Which'one of the following describes the expected response of the Reed Reactor Facility 24-hour telephone communications if 110 VAC power to the Reed College switchboard is lost?

s. The direct dial-in line and the special phone line will fail.
b. The direct dial-in line will tail, but the special phone line will be unaffected.
c. The direct dial-in line will shift to the special phone line.
d. The direct dial-in line will be re-powered by a backup generator and the special line will be unaffected.

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f Section A: R Theory. Thermo & Fac. Ooeratina Characteristics Page 22

  • ANSWER (A.1)
  • REFERENCE l Standard NRC Reactor Theory Question

'I;

  • ANSWER (A.2).

a

  • REFERENCE <

SDM = (1 - K,)/K, = (1.0 - 0.8)/0.8 = 0.25 If counts decreased by 2, then distance to criticality l was increased by 2. therefore added 0.25 negative CR, _ (1 -K,f,) 50 _ (I-#<#,)

CR 2 (I -X,#,) 25 (1 -0.8) 1 -K,g, =2 x .02 = 0.4 Therefore K,g, = 0.6 which implies K,g, - K,#, _ 0.6 - 0.8 , _ 0.2

= -0.41667 K,g,K,f, 0.8 0.6 0.48 l

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  • ANSWER (A.3) a i
  • REFERENCE P=Po e" P = 110% T = 20 sec. t = 0.5 P = 110 e'" = 112.78%

!

  • ANSWER (A.4) a '
  • REFERENCE Standard NRC Theory Question  !
  • ANSWER (A.5) b
  • REFERENCE Standard NRC Reactor Theory Question l

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  • ANSWER (A.6) l a l
  • REFERENCE I

Standard NRC Reactor Theory Question

Section A: R Theory. Thermo & Fac. Ooeratina Characteristics Page 23

  • ANSWER (A.7) b
  • REFERENCE Reed Requal Exam 88-89
  • ANSWER (A.8) a
  • REFERENCE RRF Training Manual
  • ANSWER (A.9) b

' REFERENCE Standard NRC Reactor Theory Question

  • ANSWER (A.10) b
  • REFERENCE Standard NRC Reactor Theory Question
  • ANSWER (A.11) c
  • REFERENCE Standard NRC Reactor Theory Question
  • ANSWER (A.12) b REFERENCE A = A, e* A = .693/T2 In(A/Ao ) = .693t/T2 3 T2 = .693 24hr/In 0.8 = 75 hr
  • ANSWER (A.13) l d
  • REFERENCE Burn, R., Introduction to Nuclear Reactor Operations, @ 1988, 9g 4.5.
  • ANSWER (A.14) d
  • REFERENCE l RRF Training Manual (pg 12-7-23 /12-7-24) l I

mw -..-- . ...- - - .. . .

Section A: R Theorv. Thermo & Fac. Ooeratina Characteristics Page 24

  • ANSWER (A.15) a ,
  • REFERENCE Reed RO Requal Exam
  • ANSWER (A.16) b
  • REFERENCE Reed RO Requal Exam
  • ANSWER (A.17) c
  • REFERENCE

' Standard NRC Reactoi Theory Question

  • ANSWER (A.18) Deleted a
  • REFERENCE RRF RO Requal Exam.1990
  • ANSWER (A.19) c
  • REFERENCE RRF Requal Exam.1990 l
  • ANSWER (A.20)
e REFERENCE At 20 feet, all measured radiation is from gammas.

! D, r,2 = D o 202r' D, (1): = 0.1 mr (20):

Di = 40 mrem /hr gamma -

l Ratio of beta to total = 1 -(40/200) = 80%

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Page 25 Section B: Normal /Emera. Procedures & Rad Con

  • ANSWER (B.1) a REFERENCE Glasstone & Sesonske,9.41, p 525.

DR= 6CE/x2 = 0.005 = 6(1/2)(1.33)/x2, x2 = 798, x = 28.25 feet

  • ANSWER (B.3) c
  • REFERENCE RRF 1990 RO Requal Exam ANSWER (B.04) [1.0]

c REFERENCE GM is not sensitive to energy.

ANSWER (B.05) [1.0]

b REFERENCE 10CFR20.1003 ANSVER (B.06) [1.0]

c REFERENCE 10CFR50.54(y)

" ANSWER (B.7) d

  • REFERENCE Emergency implementation Procedures
  • ANSWER (B.8) a
  • REFERENCE RRF Tech Specs

!.., e..

Section B: Normal /Emera. Procedures & Rad Con Page 26

  • ANSWER ~ (B.9) a
  • REFERENCE RRF Tech Spec
  • ANSWER (B.10) b
  • REFERENCE RRF Training Manual ch. 2
  • ANSWER (B.11) a
  • REFERENCE SOP-02; 2.7.2
  • ANSWER (B.12) c
  • REFERENCE Emergency implementation Procedures, ElP-7
  • ANSWER (B.13) d
  • REFERENCE Tech Specs
  • ANSWER (B.14) a
  • REFERENCE Reed, SOP 01, Step 1.7.6.7
  • ANSWER (B.15) c

' REFERENCE Reed, SOP 03, Precaution 3.5.4, page 1.

  • ANSWER (B.16) i c
  • REFERENCE Facility Comments on Written Examination for Requal. Exam Administered in August 1992.

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Sac

  • inn B: Normal /Emera. Procedures & Rad Con ' Page 27 ,
  • ANSWER (B.17) b

' REFERENCE Reed EIPs, Attachment B

  • ANSWER (B.18) b
  • ANSWER (B.19) d
  • REFERENCE Reed, Admin Procedures, Section Vll.7.1.a and 7.2, page 16.
  • ANSWER (B.20) c
  • REFERENCE Reed, Technical Specifications, D.1.

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J l Section C: Plant and Rad Monitorina Systems Page 28 I l

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  • ANSWER (C.1) d
  • REFERENCE

{

l RRF TRIGA Mechanical Maintenance and Operating Manual, Appendix B, pp.1 15

  • ANSWER (C.2) Deleted b
  • REFERENCE SAR Section 5.3.2, pg 5-14
  • ANSWER (C.3) d
  • REFERENCE GA Triga Maintenance and Operating Manual
  • ANSWER (C.4) b
  • REFERENCE Reed Technical Specification, Table 11, page 9
  • ANSWER (C.5) d I'
  • REFERENCE RRF Description and SAR (pg 5-7) 1
  • ANSWER (C.6) l c
  • REFERENCE RF Training Manual, page 6-12.

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  • ANSWER (C.7) b'
  • REFERENCE Reed, Survey Instrument instruction Manuals, Model RO-2, page 1.
  • ANSWER (C.8) a
  • REFERENCE Reed SOP 33, page 4.

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Sar* ion C: Plant and Rad Monitorina Systems Page 29

" ANSWER (C.9) c

)

  • REFERENCE GA TRIGA Mech. Maint. & Operating Manual
  • ANSWER (C.10) d
  • REFERENCE GA TRIGA Mech. Maint. & Operating Manual
  • ANSWER (C.11) a
  • REFERENCE RRF SAR (pg 5-6 through 5-11)
  • ANSWER (C.12) a
  • REFERENCE Reed SAR, page 4-5
  • ANSWER (C.13) d
  • REFERENCE Reed SAR, page 5-3
  • ANSWER (C.14) b
  • REFERENCE GA TRIGA Electrical Maintenance Manual
  • ANSWER (C.15) 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.16) Deleted a
  • REFERENCE Reed SOP-63, Section 63.1

i Section C Plant and Rad Monitorina Systems Page 30

  • ANSWER (C.17) ,

1' b i

  • REFERENCE SAR, Section 5.2.2, pg 5-5 and Fig. 5-2, pg 5-4
  • ANSWER (C.18) d.
  • REFERENCE' SAR Section 5.3.2, pg 514 SOP 03, Section 3.7.2.3 and 3.7.4.3, pg 3 and 4
  • ANSWER (C.19) d

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