ML20239A204

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NRC Operator Licensing Exam Rept 50-170/OL-98-01 (Including Completed & Graded Tests) for Tests Administered on 980810- 11.All Candidates Passed Exams
ML20239A204
Person / Time
Site: Armed Forces Radiobiology Research Institute
Issue date: 08/24/1998
From: Isaac P
NRC (Affiliation Not Assigned)
To:
Shared Package
ML20239A199 List:
References
50-170-OL-98-01, 50-170-OL-98-1, NUDOCS 9809080314
Download: ML20239A204 (40)
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. U. S. NUCLEAR REGULATORY COMMISSION OPERATOR LICENSING INITIAL EXAMINATION REPORT REPORT NO.: 50-170/OL 98-01 FACILITY DOCKET NO.: 50-170 FACILITY LICENSE NO.: R-84 FACILITY: Armed Forces Radiobiological Research Institute EXAMINATION DATES: August 10 - 11, 1998 EXAMINER: Patr' asc, Chief Examiner SUBMITTED BY: v o- 8V 8 kIsad of Examiner ' Date

SUMMARY

During the week of A9 gust 10,1998, NRC administered Operator Licensing Examinations to four Senior Reactor Oporator instant (SROI) candidates. All candidates passed the examinations.

9909090314 990903

  • ENCLOSURE 1 PDR ADOCK 05000170 V PDR

l

. l REPORT DETAILS

1. Examiners:

Patrick Isaac, Chief Examiner

2. Results:

RO PASS / Fall SRO PASS / FAIL TOTAL PASS / Fall Written N/A 4/0 4/0 Operating Tests N/A 4/0 4/0 Overall N/A 4/0 4/0

3. Exit Meeting:

Personnel attending:

Stephen Miller, AFRRl, Reactor Facility Director George Robert, AFRRI, Senior Staff Engineer Patrick Isaac, NRC, Chief Examiner The NRC examinations were discussed. There were no generic concerns raised by ,

the Chief Examiner.

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t ________________~

U. S. NUCLEAR REGULATORY COMMISSION NON-POWER INITIAL REACTOR LICENSE EXAMINATION FACILITY: AFRRI l

REACTOR TYPE: TRIGA DATE ADMINISTERED: 08/10/98 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 wiii be picked up three (3) hours after the examination starts.

% OF CATEGORY % OF CANDIDATE'S CATEGORY VALUE- TOTAL SCORE VALUE CATEGORY 20.00 .33 2. 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. 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.

l Csndidate's Signature I

ENCIDSURE 2 l

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A. - RX THEORY. THERMO & FAC OP CHARS ANSWER SHEET .

Multiple Choice (Circle or X your choice)

~ if you change your answer, write your selection in the blank.

MULTIPLE CHOICE 001 a b c. d-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 020 a b c d

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

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

If ycu 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 006 a b c d 007 1- 2 3 4 008 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 015 a . b c d 016 a b c d 017- a b c d

.018 a b c d l'

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

F L_- _ _ _ _ _ _ _________________o

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-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 001 a b^c d

. 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 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 is h

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

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

1. Cheating on the examination means an automatic denial of your application and could result in more 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 9nly to facilitate legible reproductions.
5. Print your name in the blank provided in the upper right-hand corner of the examination cover sheet and each answer sheet.
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.
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 tunJng in your examination, assemble the completed examination with examination questions, examination aids and answer sheets. In addition turn in all scrap paper.

iO. Ensure all information 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 tumed 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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L EQUATION SHEET i

= th e b T = th bH = UA b T {p-p)2 2a(k)f f* = 5 x 10 seconds g g SCR - -

-p 1 -K,,,

h,,, = 0 .1 s e c o n ds *

  • CR, ( 1 -K,,,, ) CR, ( 1 -K,,, )

5 = 0.007 1 I'P ) = CR, ( -p, )

2 i

1-K SUR = 2 6. 0 6 en M=

6-p 1-Kerr, j l

4 M=

A

= 1 P = P, 10'"* W 1 - K,,, CR,

( 1 -K,,,) 2

'SDM = p=9 e T 9

ett f* S (1 -p)

P=

T= P*  !

p-f 0-p '

K,,,,- K,,, T = p. g_

Ap = +

k,,,, x K,,, p A,,, p l

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T9 _

0.693 (K,,,-1) x p= i Katt '

DR =DR. e ~ht DR, d, * = DR, d,*

6CIE(n) IP2 -0) =

IP -0) i DR =

g2 Peak, Peak, I = I,e ~"

1 1 Curie = 3.7 x 10 dis /sec 1 kg = 2.21 lbm i BTU = 778 ft-lbf *F = 9/5 C + 32 i

1 gal (H2 O) = 8 lbm *C = 5/9 (*F - 32)

.c,=1.0 BTUllbml*F c, = 1 callsec/gml*C j i

L_____.____

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Section A: R Theory. Thermo & Fac. Ooeratina Characteristics Page 1 Question (A 1) [1.0)

A reactor scram has resulted in the instantaneous insertion of .003AK/K of negative reactivity.

Which one of the following is the stable negative reactor period resulting from the scram?

a. 45 seconds
b. 56 seconds
c. 80 seconds l

l d. 112 seconds Question (A.2) [1.0]

l 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?

l

a. Ap = - 0.42
b. Ap = + 0.42 l

! c. Ap = - 0.21

d. Ap = + 0.21 l

l Question (A.3) [1.0)

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

. the reactor is operating at 100% power prior to the scram, approximately how high will reactor power get with a positive 20 second pc-iod?

a. 113 %
b. 116 %
c. 124 %
d. 225 %

-E .

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Star *% A R Theorv. Thermo & Fac. Ooeratina CharMarisfa Page 2 Question ~ (A.4) [1.0)

Which one of the following is the dominant factor in determining differential rod worth?

a. ' Axial and Radial Flux.
b. Total Reactor _ Power _

. c. Rod speed

d. - De!ayed neutron fraction Question (A.5) [1.0) o Which one of the following is the MAJOR source of energy recovered 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

Question (A.6) [1.0]

Which statement illustrates a characteristic of Subcritical Multiplication?

I

a. As Keff approaches unity (1), for the same increase in Keff, a greater increase in I 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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Section A: R Theory. Thermo & Fac. Ooeratino Characteristics Page 3 Question (A.7) [1.0]

Assume that the core can be made critical with an excess reactivity of $.40 with 68 fuel elements in the core. Which one of the following is the maximum number of fuel rods that can again be inserted without exceeding Technical Specification excess delta K limits.

a. 3
b. 9
c. 12 1
d. 19 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 suberitical.)

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

Question (A.9) [1.0]

i Most nuclear text books list U-235 delayed neutron fraction (p,) as being 0.0065Ap. Most research reactors however have an effective delayed neutron fraction (pm) 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 peutrons are born at lower energies than prompt neutrons resulting in a greater worth for the neutrons.

l c. The fuel includes U228 which has a relatively large p for fast fission.

rse f d. The fuelincludes U23 which via neutron absorption becomes Pu which has a larger p for fission.

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Section A: R Theory Thermo & Fac. Ooeratina Characteristics Page 4 Question . (A.10) [1.0)

A CET is installed in the normal position with an experiment worth +$0.40 (calculated). The reactor is brought to criticality at 5 watts at position 500 with the following rod positions; Safe: 100% (full up)

Shim: 100 %

Trans: 0%

Reg: 700 units l

Which one of the following is the amount of reactivity by which the reactor is shutdown?

]

[ a. $2.6

b. $4.6
c. $7.0
d. $9.7 Question (A.11) [1.0]

Which one of the following is the reason for an installed neutron source within the reactor? A l startup without a neutron source ..

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a. is impossible as there would be no neutrons available to start the fission process.  !

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' b. would be very slow due to the long time to build up neutron population from so low a j level.

c. could result in a very short period due to the reactor going critical before neutron 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.

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b- _- _ _ .

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  • Section A: R Theory. Thermo & Fac. Ooeratina Characteristics Page 5 Question (A.12) [1.0]

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

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

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

Question (A.14) [1.0)

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

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.

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l Section A: R Theory. Thermo & Fac. Ooeratina Characteristics Page 6 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.
b. Doppler resonance effects to decrease.
c. The hydrogen atoms in the ZrH to slow down more neutrons.
d. More thermal neutron absorption by the moderator. '

Question (A.16) [1.0)

During a fuel loading, if the fuel elements are loaded to the core one by one starting near the source and proceeding toward the detector, which one of the following statements describes the effect of this loading sequence on the 1/M plot?

a. The sequence has no effect on the 1/M plot.
b. The 1/M plot will have a less angular slope, predicting criticality for a larger number of elements.
c. The 1/M plot will have a steeper slope, initially predicting criticality for a fewer number of elements.
d. The 1/M plot will approach infinity. Predicting criticality would be difficult.

l Question (A.17) [1.0] l An experiment is loaded into the B-ring of the core when the reactor is operating at 1 MW in the manual mode. After loading the experiment, the reactor power level decreases to 600 KW.

How much reactivity was added by the experiment?

a. $0.46
b. $0.76
c. $1.80
d. $2.63 j

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Section A: R Theory. Thermo & Fac. Ooeratina Characteristics Page 7 l

Question (A.18) [1.0)

Which of the following is not an assumption of the Fuch's model for pu! sing reactors?

a. All materials have a constant heat capacity.
b. Delayed neutrons have a mean lifetime of 55 sec.

! c. The reactor is assumed to occupy a single point in space.

d. No heat transfer takes place .

l Question (A.19) [1.0]

Given the reactor is critical at 5 watts at position 500 with the following rod positions:

Safe: 100 %

! Shim: 100 %

Trans: 0%

Reg: 80%

Which one of the following is the K-excess for the core?

a. 2.8
b. 3.5
c. 4.9
d. 5.2 i

Question (A.20) [1.0j 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. Procedures & Rad Con Page 8 Question (B.1) [1.0)

A small radioactive source is to be stored in the reactor building. The source is a 0.5 curie and emits a 1.33 Mev gamma.

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

a. 28 feet
b. 22 feet
c. 17 feet
d. 2 feet QUESTION (B.2) [1.0)

A room contains a source which, when exposed, results in a general area does 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.
c. Equip the room with a motion detector that will alarm in the control room.
d. Lock the room to prevent inadvertent entry into the room.

Question (B.3) [1.0)

Which one of the following does NOT need to be submitted to the NRC when modified?

a. License
b. Requalification plan
c. Emergency implementation Procedures
d. Emergency Plan f

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Section B: Normal /Emero. Procedures & Rad Con Page 9 Question (B.4) [1.0]

Consider two point sources, each having the same curie strength. Source A's gammas have an j 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 (8.5) [1.0)

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

a. 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.

7 Section B: Normal /Emero. Procedures & Rad Con Page 10 Question (B.7) [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

1. Renewal of license a. 1 year
2. Medical Examination b. 2 years
3. Requalification Written examination c. 4 years
4. Requalification Operating Test d. 6 years Question (B.8) [1.0)

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

a. Each fueled experiment shall be controlled such that the total inventory of lodine isotopes 131 thru 135 in the eroeriment is no greater than 5 millicuries.
b. The reactivity worth of all experiments shall not exceed $3.00.
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 of the following radiation detectors are used to meet the Technical Specification requirements for core measuring channels?

a. 1 fission chamber, and three uncompensated gamma-ion chambers.
b. 1 fission chamber, three compensated gamma-ion chambers, and a Cerenkov detector.
c. 1 fission chamber, two boron-lined uncompensated ion chambers, and either an uncompensated gamma-ion chamber or a Cerenkov detector.
d. 1 fission chamber, two compensated gamma-ion chambers,1 uncompensated gamma-ion chamber, and a Cerenkov detector.

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Section B: Normal /Emera. Procedures & Rad Con Page 11 l 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 mrinr
c. 6.25 mr/hr
d. 17.5 mr/hr Question (B.11) [1.0]

Personnel may enter the exposure rooms (ER) without a SHD monitor present provided which of the following sets of conditions to met?

1. ER CAM reading is less than 200 cpm above background.
2. Survey meter readings at the door are less than 1 mr/hr.
3. At least two days have passed since the last power run.
4. The reactor has not been to power in that ER since the last survey.
a. 1&3
b. 1,2 & 3
c. 2&3
d. 1,2 & 4

Section B: Normat/Emera. Procedures & Rad Con Page 12 Question (B.12) [1.0)

Which one of the following defines the basis for the Safety Limit applicable to fuel temperature?

a. Excessive gas pressure may result in loss of fuel cladding integrity
b. High fuel temperature combined with lack of adequate cooling could result in fuel melt
c. Excessive hydrogen produced as a result of the zirconium-water reaction is potentially explosive
d. High fuel temperature could reeult in clad melt Question (B.13) [1.0]

Which one of the following describes the basis for limiting the sum of reactivity worths of experiments in the core?

a. To prevent exceeding the core temperature safety limit due to the power excursion resulting from the experiments removal from a cold critical reactor.
b. To insure that the limits of 10CFR20, Appendix B, are not exceeded if an experiment malfunctions.
c. To assure that the required shutdown margin is available.
d. To ensure that the total inventory of iodine isotopes 131 through 135, in the event of experiments malfunction, will present a minimal hazard to the environment should a release occur.

Question (B.14) [1.0]

A system or component is defined as " operable" by Technical Specifications if:

a. a channel check has been performed.
b. it is capable of performing its intended function.
c. it has no outstanding testing requirements.
d. a functional test has been performed.

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Section B: Normal /Emera Procedures & Rad Con Page 13 Question (B.15) [1.0]

Per the Safety Evaluation Report, which one of these hypothetically conceived accidents is the Design Basis Accident (DBA) for the AFRRI reactor?

a. Loss of Shielding and Cooling Water
b. Fuel Drop Accident
c. Improper Fuel Loading (Rapid insertion of reactivity)
d. Metal-water reactions Question (B.16) [1.0)

Based on the Requalification Plan for operators at AFRRI, each licensed operator must complete a minimum of Daily Startup Checklist during each requalification cycle.

a. 4
b. 6
c. 8
d. 10 Question (B.17) [1.0) q The governor requests radiatior workers to clean up an accident at Calvert Cliffs. While helping out you receive a dose of 6 Rem.10 CFR 20 requires that this dose be tracked as a Planned Special Exposure. Who is responsible for maintaining a permanent record of this dose?
a. Federal Emergency Management Agency (FEMA).
b. AFRRI reactor facility
c. Nuclear Regulatory Commission.
d. State of Maryland, (an agreement state).

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_ _ _ _ _ = _ - _ _ - - _ - - - - - - - - - - _ - - - - - - - - - - - - - - - - _ - - - - - - - - - - - - - - - - - - . - - - - - - - - - - - - - - - - - - - - _ - - - - ------ - -

- _ - - --_ j

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Section B: Normal /Emera. Procedures & Rad Con Page 14 Question (8.18) [2.0]

Identify each of the actions listed below as either a Channel Check, Channel Test, or Channel Calibration,

a. Verifying overlap between Nuclear Instrumentation meters,
b. Replacing an RTD with a precision resistance decade box, to verify proper channel output for a given resistance.
c. Performing a calorimetric (heat balance) calculation on the primary system, then adjusting Nuclear Instrumentation to agree.
d. - During shutdown you verify that the period meter reads -80 seconds.

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m Sedian C: Plant and Rad Monitorina Systems Page 15 Question (C.1) [1.0)

Which ONE of the following describes the location (s) in the primary water purification system where conductivity is measured?

a. Water monitor box only.

_]

b. Inlet to purification pump only,
c. Water monitor box and outlet of each demineralized.
d. . inlet to purification pump and outlet of the domineralizers.

Question- (C.2) .[1.0)

Which one of the following design features prevents water from being siphoned out of the reactor pool and uncovering the core in the event of a primary coolant pipe rupture?

a. The capacity of the primary water makeup system. j
b. All primary coolant pipes and components are located above core height.

, c. The suction and discharge lines penetrate the reactor tank approximately 8 feet below pool surface.

d. The small holes that are drilled in the suction and retum lines approximately 4 inches below pool surface.

Question (C.3) [1.0]

Which ONE of the following describes the reason why the lower grid plate is gold-anodized?

a. To reduce grid plate wear.
b. To minimize corrosion of the grid plate.
c. To reduce the activation of the grid plate.

- d. To differentiate between the upper and lower grid plates.

L - - _ _ _ -._ . _ _ _ - - _ - - - _ _ _ _ - - - _ - _ _ _

4 Section C: Plant and Rad Monitorina Systems Page 16 I Question (C.4) [1.0)

Which one of the following describes the purpose for the compressed air connection to the hot  ;

liquid radioactive waste tank? '

a. To stir the tank prior to sampling.

' b. Pressurization of the tank to provide the driving force for discharge.

c. Ensure that an explosive atmosphere condition inside the tank is prevented.
d. Provide positive venting to reduce the buildup concentration of radionuclides above l allowable limits. l Question (C.5) [1.0)

The reactor is operating at 50% power steady state with normal primary and secondary water system lineup when a primary water system heat exchanger tube leak occurs. i Which one of the following would be an initialindication of this event assuming no operator. l action is taken?

a. Reactor power increases. I
b. Reactor power decreases.
c. Reactor poollevelincreases.

1

d. Reactor poollevel decreases.  !

l Question (C.6) [1.0) l Due to an interlock failure the core is driven into region 2 with the lead shield doors closed.

What will prevent damage to the core or the doors.

a. The clutch on the lead shield door motor.
b. The reverse contact switch on the core shroud.
c. The clutch on the core drive motor. l

[

d .- The thickness of the core shroud.

- _ _ _ _ _ _ _ _ - - _ _ - _ _ _ _ _ _ _ _ _ - _ _ - _ - ~

Section C: Plant and Rad Monitorina Systems Page 17 Question (C.7) [2.0)

Match the control rod drive mechanism part in column "A" with its function from column "B".

Column A Column B

a. Pull rod 1. Provides rod bottom indication l ' 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

. Question _ (C.8) [2.0)

Match the conditions given in Column A with the correct safety signal provided by that condition as listed in column B. (2 points,0.5 each)

COLUMN A COLUMNB

a. Pool Water Temperature high 1. Rod withdrawal prevent

- b. Source level Low 2. Reactor SCRAM

c. Console Key Hemoved
d. Loss of NM 1000 High Voltage l

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Section C: Plant and Rart Monitorina Systems Page 18 Question (C.9) [1.0)

Which one of the following describes the action of the rod cor. trol 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.

Question (C.10) [1.0)

Which one of the following scrams IS REQUIRED by Reactor Technical Specifications?

a. Percent Power, High Flux in the Pulse Mode
b. Steady State Timer
c. Manual Scram Bar
d. Loss of AC Voltage Question (C.11) [1.0)

Which of the rings include the chromel-alumel thermocouple?

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a. A and B
b. A and C
c. B and C

.d. B and D

Saggion C Plant and Rad Monitorina Systems Page 19 Question (C.12) _ [2.0]

For a power failure, describe the status of each of the following items in column A with the correct choice from column B. (2 points,0.4 each)

Column A Column B

a. Shim, Safety and Regulating Blades 1. Open j
u. Control Room Dampers, D-27 & D-28 2. Closed
c. ' Main isolation Dampers 3. Inserted
d.  : Transient Rod 4. No change

- e. Reactor Room Dampers, D-29 and D-30 )

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Question . (C.13) [1.0]

Which one of the following completes the following statement?

The fuelin the AFRRI TRIGA is a homogeneous mixture of uranium- hydride alloy containing  % by weight of uranium enriched to <  %

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

Which one of the' conditions will NOT prevent rod withdrawal?

a. , While conducting a reactor startup, the reactor operator notices a loss of high voltage to the high flux safety channel one.
b. The reactor operator selects pulse mode and attempts to withdraw the shim rod.

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c. Rods are being pulled for a reactor startup. Source count i is 0.1 cps,
d. The demin inlet temperature is 40*C.

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4 Section CF Plant and Rad Monitorina Systems Page 20 Question (C.15) [1.0]--

Which one of the following sets of devices is tested when the TRIGA control system is in the PRESTART mode?

! - a. - Fuel temperature scram circuits

- NM1000 scram circuits

- Interlock preventing control rod withdrawal with low neutron level

b. - DAC Watchdog timer

- NPP High Voltage Scram

- NM1000 power level calibration

c. - Interlock preventing simultaneous withdrawal of two control rods .

- Fuel temperature scram circuits

- NPP1000 High % power scram

d. ' - NM1000 scram circuits

- Key Switch in the OFF position

- DAC Watchdog timer Question (C.16) [1.0)

, ~ A minimum loss of ___ inches of water from the reactor pool will activate the lobby audio alarm.

' a. 2

b. 4
c. 6
d. 19.5 mm____________m_ _ _ . _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ .m__._. _

Section C: Plant and Rad Monitorina Systems Page 21 Question (C.17) [1.0)

Which one of the following changes will have an effect on nuclear power indications when operating in the steady state mode?

a. The NVT circuit failed and is indicating 50 MWS on the bargraph.
b. The campbelling portion of the fission chamber signal processing circuitry provides no signal at 200 KW.
c. The Primary flow rate increases from 250 gpm to 350 gpm.
d. Loss of power to the Cerenkov detector, 9

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

  • ANSWER (A.1) c
  • REFERENCE Burn, R., Introduction to Nuclear Reactor Operations, @ 1982, S 4.6, p. 4-16.
  • 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 was increased by 2. therefore added 0.25 negative CR, (1-K,f,) 50 (I ~ K,g,)

CR, (1-K,y,) 25 (1 -0.8) 1 -K,, =2 x .02 = 0.4 Therefore K,, = 0.6 which implies K,,, - K,y, 0.6 - 0.8 _ 0.2 = -0.41667 K,g,K,g, 0.8 0.6 0.48 ANSWER (A.3) a

  • REFERENCE P = Poe" P = 110% T = 20 sec. t = 0.5 P = 110 e sta = 112.78%
  • ANSWER (A.4) a
  • REFERENCE.

)

J Standard NRC Theory Question

  • ANSWER (A.5) b
  • REFERENCE Standard NRC Reactor Theory Question
  • ANSWER (A.6) a
  • REFERENCE Standard NRC Reactor Theory Question

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l-Section A R Theorv. Thermo & Fac. Ooeratina Characteristics Page 23 j

  • ANSWER (A.7) c
  • REFERENCE Operations Manual ch. 2, A. General Design. - Reference Package for the AFRRI TRIGA.

AFRRI Technical Specifications 3.1.3 Max excess = $5.00 Fuel rod worth in the F ring is $.37/ rod Therefore: ($5.00 - $.40)/ $.37/ rod = 12.4 rods may be added

  • ANSWER -(A.8) a
  • REFERENCE Burn, R., introduction to Nuclear Reactor Operations,
  • 1982, f 5.7, pp. 5 5-38
  • ANSWER (A.9) b
  • REFERENCE Standard NRC Reactor Theory Question
  • ANSWER (A.10)
  • REFERENCE Excess 5 = Trans + Reg - 0.40 = 2.526 + (2.486 - 1.895) - 0.40 = 2.717 SDM = RW. - K,. = 2.526 + 2.205 + 2.499 + 2.486 - 2.717 = 7.00
  • ANSWER (A.11) c
  • REFERENCE

- Standard NRC Reactor Theory Question

  • ANSWER (A.12) b REFERENCE A = A, e* . A = .693/T2 In(A/A ) = .693t/T2 -

. T2 = .693 24hr/in 0.8 = 75 hr i

  • ANSWER (A.13) d j i
  • REFERENCE I Burn, R., Introduction to Nuclear Reactor Operations, @ 1988, 99 4.5.

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

  • ANSWER . (A.14) .

d

_

  • REFERENCE Burn, R., introduction to Nuclear Reactor Operations,
  • 1988, gg 8.2 - 8.4, pp. 8 8-14.
  • ANSWER (A.15) a
  • REFERENCE FSAR Section 4.16.3
  • ANSWER - (A.16) b
  • REFERENCE Burn, R., Introduction to Nuclear Reactor Operations, C 1982, G 5.5, pp. 5 5-25.
  • ANSWER (A.17)

L b

  • REFERENCE Power Coefficient of Reactivity curve
  • ANSWER (A.18) b

REFERENCE:

AFRRI supplied question ANSWER (A.19) a

  • REFERENCE Supplied Rod Worth curves-
  • ANSWER (A.20) c REFERENCE At 20 feet, all measured radiation is from gammas.

u- D, r,8 = Da rw8 D, (1)8 = 0.1 mr (20)2 D, = 40 mrem /hr gamma Ratio of beta to total = 1 -(40/200) = 80%

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

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

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

  • ANSWER (B.3) c
  • REFERENCE 10CFR50.54; ANSWER (B.4) c REFERENCE GM is not sensitive to energy.

ANSWER (B.5) b REFERENCE.-

10CFR20.1003 ANSWER (B.6) c REFERENCE 10CFR50.54(y) .

ANSWER (B.7) 1 _d_ 2 _b_ 3 _b_ 4 a_

REFERENCE 1CCFR55

  • ANSWER (B.8) b

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

  • ANSWER (B.9) c REFERENCE (B.17)

AFRRl Question Bank Cat. B AFRRI Manual 82-1, Chapter 5, Sect. A

  • ANSWER (B.10) b

' REFERENCE DR,D,8 = DR 2 D,2 . . ,pg,g,2 = DR,

  • DR, " 50 mr/hr x 5 ft2 = 12.5 mr/hr D,2 10 ft2
  • ANSWER (8.11) d REFERENCE AFRRI Operational Procedure 1, Tab A, Step 4, p 4.
  • ANSWER (B.12) a
  • ANSWER (B.13) a
  • REFERENCE AFRRI T.S. 3.6 Basis
  • ANSWER (B.14) b
  • REFERENCE

. T.S. Definition 1.15

  • ANSWER (B.15) b
  • REFERENCE SAR Section 6.3.4
  • ANSWER (B.16) c
  • REFERENCE AFRRI Requalification Program; On-The-Job Training.

Section B: Normal /Emerg. Procedures & Rad Con Page 27

  • AHSWER (B.18) a, check; b, test; c, calibration; d, check REFERENCE Tech. Specs, Definitions 1.2 l

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Section B: Normal /Emera. Procedures & Rad Con Page 28

  • ANSWER (C.1) e i
  • REFERENCE AFRRl SAR, Section 3.3.3, pp 3-16 & 3-17.

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' *ANSWER '(C.2) d

  • REFERENCE AFRRI SAR, Section 3.3.1
  • ANSWER (C.3) a
  • REFERENCE AFRRI SAR, Section 4.6
  • ANSWER (C.4) a
  • REFERENCE' AFRRI SAR, Section 3.4.2, p 3-22.
  • ANSWER (C.5) c
  • REFERENCE NRC Exam 4/23/91.
  • ANSWER (C.6)

.C

  • REFERsNCE NRC Exam 2/93
  • ANSWER - (C.7) a 1 b 3 c 2

'd 4 l

  • REFERENCE FSAR Section 4.10 & Fig 4-8 l ' ANSWER (C.8)

[ a. 1 f

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Sechon B: Normal /Emera Prae =dures & Rad Con Page 29 l b. 1:

c. 2
d. 1
  • REFERENCE AFRRI Procedure 8, Tab B.

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  • ANSWER (C.9) e i
  • REFERENCE GA Maintenance Manual'
  • ANSWER . (C.10)'

c-

  • REFERENCE AFRRl supplied question qa55, also Reactor Tech. Specs.

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  • ANSWER (C.11) c
  • REFERENCE AFRRI supplied question i
  • ANSWER (C.12) ' ,
s. 3
b. 2-
c. 4
d. 3
e. 2
  • REFERENCE AFRRI Operations Manual, Chapter 4 9 D Distribution System for Electrical Power. also; AFRRI SAR, 9 4,10.2 Standard Control Rod Drives , 9 4.10.4 Iransient Control Rod Drive

'*ANSWER' (C.13)

.d

  • REFERENCE

' AFRRI SAR Section 4.16.1 L

  • ANSWER (C.14)

{ d

[

  • REFERENCE Operations Manual ch. 5 1
e ,

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l, 5 =g.-

I 'b .

l Sedion B: Normal /Emera. ProMures & Rad Con Page 30

  • ANSWER (C.15) l b
  • REFERENCE

' GA Control Console Operator's Manual pg. 2-5 i

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  • ANSWER (C.16) c

'* REFERENCE

, SAR Sect. 3.3.6

  • ANSWER (C.17)

L b

REFERENCE:

l Operations Manual ch. 5 l

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