ML20024H141
| ML20024H141 | |
| Person / Time | |
|---|---|
| Site: | Armed Forces Radiobiology Research Institute |
| Issue date: | 02/20/1991 |
| From: | Maria Moore DEFENSE, DEPT. OF, DEFENSE NUCLEAR AGENCY |
| To: | Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20024H136 | List: |
| References | |
| NUDOCS 9105220304 | |
| Download: ML20024H141 (55) | |
Text
. _ _ . _ - - _ _ _ _ _ _ _ _ _ . _ _ _ _ . _ _ _ _ _ _ _ _ _ . _ . _ . _ _ _ .
1 e
g, , DEFENSE NUCLEAR AGENCY ARMED FOACES RADIOBIOLOGY RESE ARCH INSTITUTE BETHISDA, M ARYLAND 20814 5145 RSD 20 HB 1991 Director, Operator Licensing Branch Division Of Licensee Performance and Quality Evaluation US Nuclear Regulatory Cc m ission Washington, DC 20555 l
Dear Sir:
As requested in your letter of January 30, 1991, enclosed are two copies each of the following reference materials:
- 1. Safety Analysis Report - The submitted version describes the current reactor system except that it includes fuel folloner control rods which may not be installed before the examinations.
- 2. Technical Specifications
- 3. Emergency Plan 4 Operating Procedures - Always " ilable to the operator and not :
required to be memorized.
- 5. Reference Package containing various reference equations, rod curves and technical data.
- 6. Portions of the textbook Fundamentals of Nuclear Reactor Engineering.
Note that this text was designed for a year-long intensive course for power plant operators and includes a significant amount of material ,
beyond the scope of AFRRI training. It is used at AFRRI to complement fermal lectures. Whlie the text includes material which AFRRI operators are expected to study and retain, operators are not expected to learn everything presented in the text.
- 7. A ' question bank' of questions and answers related to the AFRRI reactor.
All these items are approved final issues except as noted for the SAR.
As also requested in your letter, adequate space will be provided to conduct the examinations in accordance with your procedures and all applicants will be informed of the Rules and Guidelines.
Should you have any questions, please contact me at 301-295-1290.
Sincerely, 9 .
9105220304 910516 ADOCK 050 0
<h
-yDR ark Moore Reactor Facility Director
ENCLOSURE 3, ,
NRC Oft'icial Uso Only
- I.
'l
./ a.lf Nuclear Regulatory Commis._ :. operator Licensing Examination This document is removed from l Official Uso Only category on date of examination. NRC Official Use Only l l l l l
U. S. NUCLEAR REGULATORY COMMISSION NON-POWER REACTOR LICENSE EXAMINATION 1 FACILITY: Armed Forces Rad Ros Inst REACTOR TYPE: TRIGA-F _ DATE ADMINISTERED: 91/04/23 _ REGION: 1 CANDIDATE: LICENSE APPLIED FOR: INSTRUCTIONS TO CANDIDATE: Answers are to be written on the exam page itself, or the answer sheet provided. Write answers one side ONLY. Attach any answer shoots to the examination. Points for ehch question are indicated in parentheses for each question. A 70% in each section 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 20.00 33.33 A. REACTOR TilEORY, THERMODYNAMICS AND FACILITY OPERATING CHARACTERISTICS 20.00 33.33 B. NORMAL AND EMERGENCY OPERATING PROCEDURES AND RADIOLOGICAL CONTROLS 20.00 33.33 C. PLANT AND RADIATION MONITORING SYSTEMS 60.00 TOTALS FINAL GRADE All-work'done on thir examination is my own. I have neither given nor rocaived aid.
Candidate's Signature
,-- g -. - , - y - . - ,-+r . -, m4.,. .
.--.p
O 11RC RULES AND GUIDELIllES FOR LICE!1SE EXAMI!1ATIONS 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 cheet indicating that the work is your own and you have not received or given assistance in completing the examination. This must be done after you complete the examination.
- 3. Ecstroom 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 only to facilitate legible reproductions.
- 5. Print your name in the blank provided in the upper right-hand corner of the examination cover sheet.
- 6. Print your name in the upper right-hand corner of each answer sheet.
- 7. Partial credit may be given. Thercfore, A!1SWER ALL PARTS OF THE QUESTION AND DO NOT LEAVE ANY ANSWER BLA!1K. NOTE: partial credit will NOT be given on multiple choice questions.
B. Proportional grading will NOT be given on multiple choice questions.
- 9. If the intent of a question is unclear, ask questions of the examiner only.
- 10. When turning in your examination, assemble the completed examination with examination questions, examination aids and answer sheets. In addition, turn in all scrap paper.
- 11. To pass the examination, you must achieve at least 70% in each category.
- 12. There is a time limit of (3) hours for completion of the examination.
- 13. When you are done and have turned in your examination, leave the examination area as defined by the examiner. If you are found in this area while the examination is still in progress, your license may be denied or revoked.
i
A. Page RX THEORY. TilERMO & FAC OP CilhEE 2 A 11 S W E R S !! E E T Multiple Choice (Circle or X your choice) If you change your answer, write y'aur selection in the blank. MULTIPLE CHOICE 001 a b c d 011 a b c d 002 a b c d 012 a b c d 003 a b c d 013 a b c d 004 a b c d 014 a b c d 005 a b c d 015 a b c d 006 a b c d 016 a 5 c d 007 a b c d 017 a i c d 008 a b c d 018 a b c d 009 a b c d 019 a b c d 010 a t c d 020 a b c d (***** Et4D OF CATEGORY A *****)
a B. NORMAL /EMERG PROCEDURES & RAD CON Page 3 ANSWER SHEET Multiple Choice (circio or X your choice) If you change your answer, writo your selection in the blank. 001 a b c d 011 a b c d 002 a b c d 012 a b c d 003 a b c d 013 a b c d 004 a b c d 014 a b c d 005 a b c d 015 a b c d 006 a b c d 016 a b c d 007 a b c d 017 a b c d 008 a b c d 018 a b c d 009 a b c d 019 a b c d 010 a b c d 020 a b c d (***** END OF CATEGORY B *****)
C. PIA!!T AllD RAD MO!!IT.CRUlQ_SXEIDiS Page 4 A 11 S W E R S ll E E T Multiple choice (circle or X your choice) If you change your answer, writo your selection in the blank. 001 a b c d 011 a b c d 002 a b c d 012 a b c d 003 a b c d _ _ _ 013 a b c d 004 a b c d 014 a b c d 005 a b c d ___ 015 a b c d 006 a b c d 016 a b c d 007 a b c d 017 a b c d 008 a b c d 018 a b c 4 009 a b c d 019 a b c d 010 a b : d 020 a b c d (***** E!1D OF CATEGORY C *****) (********** E!1D OF EXAMIllATIOli **********)
- g. t I
PAGE 6 ; i F t k [ PAGE INTENTIONALLY LEFT BUdm i I l. i 1. 5 i l L 1 l l ' i 7-"+r'*WN-&-4Nru -7 y e .w 9 7_ 9 ,
. i f
PAGE 7 I
+
I i t PAGE IllTEllTIollALLY LETT BLA11K , r L e k J b F
=
1 I k l i
?
I l l. I i- { l t
PAGE B PAGE Il1TEllTIOllALLY LETT D11s!1K
.1 1 4
- ) !
j PAGE 9 ! ' i i j 3 1 = , I 1 [; I f I n , 1 9 PAGE IllTEllTIOP _;'Y LEPT DLANK I i- , t i t I i I i f i
)s 1
i > I I r i ! I i i h
+
f t I I t )
)
. d.
h e 3 l k
?
r
)
r
<e er JW 'r PT e Wem_ w,s.e.yg.W _g g y w w mq im sa g ,.g ep-, _ , yqq 99,g g qwyqq qm.weg_ . _ _ . , , ,, 9,, _ .
..ppp wwh
Ao R$ TilEORY, TilERMO & TAC OP CilARS Page 10 QUESTIOlit 001 (1.00) Which ONE of the following vill be the resulting reactor period uhen a $0.50 reactivity insertion is made into a just critical reactor core? A. 46 seconds , B. 22 seconds C. 11 seconds D. 5 seconds QUESTION: 002 (1.00) Which ONE of the following is classified as a FISSILE nuclide? A. N-2 41 B. U-238 C. Th-232 D. Fu-239 (***** CATEGORY A CONTINUED ON NEXT PAGE *****)
A. RX THEORY, THERMO & FAC OP CHARS Pago 11 QUESTION: 003 (1.00) Which ONE of the following.is the estimated shutdown margin of a fully loaded core given the indicated rod worths? (Assume the maximum K excess of the AFRRI core as defined by the Technical Specifications). Rod worth Data Transient Rod $3.63 Safety Rod $1.88 Shim Rod $1.90 Regulating Rod $1.87 A. $9.28 B. $5.00 C. $4.28 D. $5.65 QUESTION: 004 (1.00) Which ONE of the following is the principle reason for operating with thermal neutrons rather than fast neutrons? A. Neutron efficiency is increased since thermal neutrons are less likely to leak out of the core. B. Reactors operating primarily on fast neutrons are inherently unstable and cannot be safely controlled. C. The fission cross section of the fuel is much higher for thermal neutrons. D. The. fuel temperature and moderator temperature coefficients become positive as neutron energy increases. (***** CATEGORY A CONTINUED ON MEXT PAGE *****) _ . _ _ ,, ._.__ _ --._ _ _ _ _ . _ _ . _ . _ _ _ - _ ~, . - -
A. RX THEORY, THERMO & FAC OF CHARS Page 12 QUESTION: 005 (1.00) Which ONE of the following defines the term "Lf" in the formula Keff = K(infinite) Lt Lf? , A. Fast fission factor D. Thermal utilization factor C. Thermal non-leakage probability D. Fast non-leakage probability QUESTION: 006 (1.00) Which ONE of the following characterizies how heat is removed from the AFRRI TRIGA reactor coro? A. Forced convection
'B. Free conduction C. Natural convection D. Thermal radiation QUESTION: 007 (1.00)
The number of neutrons passing through a one square centimeter of target material per second is the definition of which ONE of the following? A. Neutron Population B. Neutron Impact Potential C. Neutron Flux D. Neutron Density (***** CATEGORY A CONTINUED ON NEXT PAGE *****) .
.. _ _ . . . _ _ . . ~ . _
A. RX THEORY, THERMO & FAC OP CHARS Page 13 QUESTION: 000 (1.00) Which ONE of the following represents the nominal worth of a standard control rod? A. 0.0105 delta K/K B. 0.0133 delta K/K C. 0.0161 delta K/K D. 0.0210 delta K/K QUESTION: 009 (1.00) Which ONE of the following is the power defect between the reactor at 10 KW and 1 MW? A. $1.55 B. $2.60 C. $3.05 D. $3.90 QUESTION: 010 (1.00) Which ONE of the following is the major source of Xenon in the roactor? A. Direct production by fission B. Decay of Promethium-149 C. D, ay of Cesium-135 D. Decay of Iodine-135 (***** CATEGORY A CONTIlfUED ON NEXT PAGE *****)
_m_ -- . _ _ _ . _ _ _ . _ _ . . . _ _ _ _ _ _ _ _ . . _ . . . . l A. RX THEORY, THERMO & FAC OP CHARS Pa90 14 QUESTION: 011 (1.00) Which ONE of the following moderator conditions describes the most efficient thermalization of neutrons? A. Moderators with LOW atomic mass number and HIGil scattering cross-section. i B. Moderators with HIGH atomic mass number and HIGH , scattering cross-section. C. Moderators with LOW neutron absorption cross-section and LOW scattering cross-section. I 1 D. Moderators with LOW neutron absorption cross-section and HIGH scattering cross-section. QUESTION: 012 (1.00) Which ONE of the following fuel element rings has the highest individual element worth during non-pulse operations? A. B - element ring B. C - element ring C. E - element ring D. F - element ring (***** CATEGORY A CONTINUED ON NEXT PAGE *****)
A. RX THEORY, THERMO & EAC OP CHARS Page 15 f l QUESTION: 013 (1.00) Which ONE of the following statements describes the suberitical reactor response as Keff approaches unity? A. A LARGER change in neutron level results from a given change in Keff and SHORTER period of time is required to reach the equilibrium neutron level for a given change in Keff. B. A LARGER change in neutron level results f rom a given change in Koff and LONGER period of time is required to reach the equilibrium neutron icvel for a given change in Koff. C. A SMALLER change in neutron level results from a givan change in Keff and SHORTER period of time is required to reach the equilibrium neutron level for a given change in Koff. D. A SMALLER change in neutron icvel results from a given change in Keff and LONGER period of time is required to reach the equilibrium neutron level for a given change in Keff. QUESTION: 014 (1.00) Which ONE of the following explains why the transient rod is worth approximately twice as much as the regulating rod. A. The neutron absorbing material in the transient rod is hafnium, where as the regulating rod is boron, i B. The active (absorber filled) section of the transient rod is longer than the regulating rod. C. The lower section of the transient rod contains a U-Rh j fuel mixture where as the regulating rod contains air. D. The transient rod is located in a region of higher flux as compared to the regulating rod. l l (* * * - CATEGORY A CONTINUED ON NEXT PAGE *****) 1
. . - ----- - - . - . . - - - - - - - - - - - - - - - - - - - - - . - - ~ - .
A,. RX THEOT,Y, THERMO & FAC OP CilARS Page 16 QUESTIOll: 015 (1.00) The reactor is critical at 1 MW. Which ONE of the following would be the stable reactor period resulting from a rod drop which inserted 0.003 delta K/K negative reactivity? A. negative 45 seconds B. negative 56 seconds C. negative 80 seconds D. negative 112 seconds QUESTIOll: 016 (1.00) Which ONE of the following allows more excess reactivity to be built into the core? A. A burnable poison (samarium) is built into the fuel elements B. A burnable poison (hafnium) is built into the control rods C. Zirconium Hydride is mixed with the fuel in the fuel elements D. Cadmium is mixed with the absorbing material in the control rods ( * * * *
- CWEGORY A CONTINUED ON NEXT PAGE *****)
-_ __ _-m.. __,, - . . - - - . _ _ , - _ _ _. . . - . _ - - - . , _ _
A. RX TiltoRY, TilERMo & TAC op CHARS Page 17 W OUEST1oN: 017 (1.00) Which ONE of the following events vill cause the Wide Range log channel indication to decrease while operating at high power levelp? A. The campbelling portion of the fission chamber signal processing circuitry providing no signal. B. The primary coolant flow rate increasing from 250 gpm to 350 gpm. I C. The pool temperature increasing 10 degrees. ! I a D. The count rate portion of the fission chamber signal ' processing circuitry providing no signal. l l QtfESTION : 018 (1.00) t'hich ONE of the following processes stops the prompt crititical excursion during a pulso? A. Magnet power doonorgized B.- Xenon posioning C. Zril disadvantage factor D. Fission fragment contamination QUESTIONi 019 (1.00) Which ONE of the following compounds is used for the ATRR1 TRIGA's startup source? A. AmBe B. PuBe C. KrPu D. PoBe F (***** CATEGORY A CONTINUED ON NEXT PAGE * * * * * )
Pago 211 f A. EX'Ti!EORY, TilERMO & TAC OP CilARS QUESTION: 020 (1.00) Which ollE of the following in the MAJOR contributor to the largo nogativo tortporature coefficient of reactivity. A. Doppler broadening B. Moderator Density , C. Zril disadvantage factor D. Fuel Enrichment i (***** EllD OF CATEGORY A *****) .
I' MORMAL/EMERG PROCELURES & RAD CON Pago 29
.U1.0T1011: 001 (1.00)
Which OllE of the following personnel may authorize the entry of fire fighters into the AFRRI TRIGA facility if an omorgency occurs after normal duty hours? A. Emergercy Rosponso Team Commander D. lloalth Physics coordinetor C. Roactor Pacility Director D. Reactor Operations Supervisor l QUESTIO!!! 002 (1.00) Which OllE of the following is the number of Licensed Reactor Operators required to visually inspect the exposuro room before the plug door is closed if Exposure Room 11 umber One horn is disconnected for testing? A. O B. 1 C. 2 D. 3 QUESTIOll: 003 (1.00) Which OllE of the following detectors is set at full scale for the pulse modo of operation? A. R1 and CAM B. SGM and CAM C. R1 and R5 D. SGM and RS (***** CATEGORY B CONTINUED ON 11 EXT PAGE *****)
,,n.-. , , , -,. , . _ _ , ,
-~.---- , .- r----,n-, , ,, ., ,,.,e ., , . . _ . , . _ . . , _ ,
B. NORMAL /EMERG PROCEDURES & RAD CON Page 20 l . QUESTION: 004 (1.00) Which ONE of the following individual (s) can initiate and approve a temporary change to a surveillance procedure on a nuclear saf ety system? A. Any 0 with subsequent review and approval of the on duty SRO B. Only an SRO with subcequent review and approval of the Reactor Operations Supervisor sc5
- c. Any RO with the subsequent approval of the Reactor Facility Director D. Only an SRO with the subsequent approval of the Reactor Facility Director QUESTION: 005 (1.00)
Which ONE of the following may authorize the downgrading and termination of an emergency? A. ERT Commander 11 B . AFRRI Director
,,C. ECP Commander
,'D.
Emergency coordinator QUESTION: 006 (1.00) In accordanew with Operating Procedure VIII, Tab F1, Square Wave Operation (Mode II - Subcritical), which ONE of the following is the maximum power at which the SQUARE WAVE mode may be used? A. 200 KW B. 500 KW C. 1000 KW D. 5000 KW (***** CATEGORY B CONTINUED ON NEXT PAGE *****)
U(. NORMAL /EMERG PROCEDURES & RAD CON Page 21 QUESTION: 007 (1.00) In accordance with the Emergency Plan, which ONE of the following is the PRIMARY assembly point for the Emergency Response Team (ERT)? A. Emergency Response Center B. Reactor Director's Office C. Reactor Control Room D. Front Patio QUESTION: 008 (1.00) Which ONE of the following fuel elements is removed to permit the use of the Core Experimental Tube ? A. Cl2 B. D18 C. T28 D. E23 QUESTION: 009 (1.00) In accordance with the AFRRI Emergency Action Procedures, Appendix B, Personnel Rosters, which ONE of the following positions is on the ECP Roster? A. HAZMAT Coordinator B. Operations Coordinator C. Special Assesment Coordinator D. Emergency Coordinator 1 (***** CATEGORY B CONTINUED ON NEXT PAGE *****)
D. NORMAL /EMERG PROCEDURES & RAD CON Page 22 QUESTION: 010 (1.00) Which ONE of the following APRRI technical specifications terms decribes the introduction of a signal into the channel to verify that it is operable? A. Channel Check B. Channel Test C. Channel calibration D. Functional Test QUESTION: 011 (1.00) Which ONE of the following is the maximum allowable CAM reading cbove background prior to opening an exposure room? A. 200 cpm B. 2000 cpm C. 200 cps D. 2000 cps QUES"/ ION: 012 (1.00) Which ONE of the following EMERGENCY CLASS designations is declared if a fire alarm occurs not involving the reactor facility? A. Class O B. Class 1 C. Class 2 D. Class 3 (***** CATEGORY B CONTI!TUED ON NEXr PAGE *****)
B. NdRMAL/EMERG PROCEDURES & RAD CON Page 23 1 i QUESTION: 013 (1.00) Which ONE of the following is the expected control rod positions when performing a K-excess determination if the reactor is brought critical using the regulator rod? A. Safety rod at 100% Shim rod at 100% Transient rod at 25% B. Safety rod at 100% ) Shim rod at 25% Transient rod at 100% C. Safety rod at 50% f Shim rod at 50% Transient rod at 100% D. Safety rod at 50%
)
Shim rod at 100% Transient rod at 25% QUESTION: 014 (1.00) A point source produces 5 mr/hr gamma at a distance of 50 feet. Which ONE of the following is the distance from the source that a moasured reading of 100 mr/hr would occur? A. 7 feet B. 10 feet C. 11 feet D. 20 feet (***** CATEGORY B CONTINUED ON NEXT PAGE *****)
B. N0RMAL/EMERG PROCEDURES & RAD CON Page 24 QUESTION: 015 (1.00) Which ONE of the following is the whole body QUARTERLY radiation oxposure limit in accordance with 10 CTR 20? A. 1000 mrom B. 1250 mrem C. 1850 mrem E 2000 mrem QUESTION: 016 (1.00) Which ONE of the following describes the ATRRI Technical Specification definition of REACTOR SHUTDOWN? A. All rods are inserted and the reactor is suberitical by at least $1.00 of reactivity B. The consolc key is removed and no maintenance or work is in progress that involves movement of fuel elements in the core or movement of any control rod. C. All control rods are inserted and the console key has been removed and in the possession of the SRO D. The reactor is suberitical by at least $0.50 of reactivity. (***** CATEGORY B CONTINUED ON NEXT PAGE *****)
B. Fage 25 l NCRMAL/EMERG PROCEDURES & RAD CON QUESTION: 017 (1.00) Which ONE of the following describes the required minimum staff when the reactor is NOT " secured"? A. One RO and one SRO on site and a Radiation Control Technician on call B. One RO or SRO present in the control room and a Radiation Control Technician on site and another person within the AFRRI complex to assist C. One RO or SRO present in the control room, an SRO and Radiation Control Technician on call and another person within the AFRRI complex to assist D One RO or SRO present in the control room and a Radiation control Technician and another staff person on call to assist QUESTION: 018 (1.00) Which ONE of the following is the maximum temperature allowed in a standard TRIGA fuel element in accordance with the AFRRI HARK-F Technical Specifications? A. 400 dog C B. 600 deg C C, 800 deg C D. 1000 deg C (***** CATEGORY B CONTINUED ON NEXT PAGE * * * * *)
B. Page 26 HQRMAL/EMERG PROCEDURES & RAD CON I QUESTION: 019 (1.00) Which ONE of the following evolutions requires a completed REACTOR USE REQUEST? A. Maintenance in Exposure Room fl when the reactor is secured. B. Calibrating the multirange linear power channel. C. Performing an experiment that has previously been performed safely. D. Performing pulsing operations for reactor operator training. QUESTION: 020 (1.00) Which ONE of the following conditions will result in a ROD WITHDRAWAL PREVENT interlock action? A. Reactor pool level indicates 13.5 feet. B. Reactor power level indicates 850 watts. C. Reactor period indicates 7 seconds. D. Reactar pool inlet water temperature indicates 63 deg C (***** END OF CATEGORY B *****)
C. PLANT AND RAD MONITORING SYSTEMS Page 27
-QUESTION: Col (1.00)
Which ONE of the following describes the operation of the interlock system for the lead shielding doors? A. The limit switches on the reduction gears provide only indication and are not part of the interlock system. B. The control rod magnets cannot be energized unless the shielding doors are fully open. C. The shield doors must be full open to relocate the fuel support carriage. D. Fuel support carriage stops 6 inches prior to reaching the fully closed doors. QUESTION: 002 (1.00) Which ONE of the following conditions will NOT initiate a reactor scram? A. 20 % loss of voltage to safety channels. B. Pulse time in excess of 15 seconds. C. 20% loss of high voltage to the operation 1 channel D. Reactor power level in excess of 1.1 MW. l l QUESTION: 003 (1.00) \ Which ONE of the-following air operated components operates on 80 psi-air pressure? A. Transient Rod B. Air compressor tank nornal pressure C._ Air damper pressure D. Load shield door bearing pressure l l (***** CATEGORY C CONTINUED ON NEXT PAGE *****) ~ 2 w.-- #- - , _ r _v er ,,- y_. ,,,.ry-- _- ,- -- g y---- y ec-+ -,,_-
Co PLANT AND RAD MONITORING SYSTEMS Page 28 j l QUESTION: 004 (1.00) Which ONE of the following is the type of detector used in the i stack gas monitor? ) A. GM tute B. Scintillation detector C. Proportional detector D. Ionization chamber QUESTION: 005 (1.00) Which ONE of the following is the reactor power limit if the purification system inlet water temperature exceeds 60 deg C.? A. 1000 watts B. 5000 watts C. 10000 watts D. 50000 watts QUESTION: 006 (1.00) Which ONE of the following is the maximum amount of explosive material which can be placed in an exposure facility? A. 10 mg. B. 25 mg C. 10 grams D. 25 grams (***** CATEGORY C CONTINUED ON NEXT PAGE *****)
C. Page 29 l PLANT AND RAD MONITORING SYSTEMS , QUESTION: 007 (1.00) Which ONE of the following fission products are most likely to be released from the POOL following a fuel element failure? A. Heavy Metals and argon B. Low Z materials and uranium C. Noble gases and Iodine D. Transuranium elements and zirconium QUESTION: 008 (1.00) Which ONE of the following describe the types of detectors located in the water monitor box? A. PH, conductivity and flow rate B. Conductivity, gamma activity and temoerature C. Gamma activity, temperature and flow rate D. Ph, temperature and flow rate QUESTION: 009 (1.00) Which ONE of the following is the design purpose of the lead shielding doors in the reactor *Tnk? A. Prevent gamma streaming to adjacent areas when performing irradiations in Exposure Room #1 B. Prevent gamma streaming from stored irradiated fuel elements when performing gamma spectrometry C. Prevent gamma streaming from effecting neutron source calibration D. Prevent gamma streaming from the core on loss of pool water while repairs are made (***** CATEGORY C CONTINUED ON NEXT PAGE *****)
Page 30 C. PLANT AND RAD MONITORING SYSTEMS l . i QUESTION: 010 (1.00) The cadmium-gadolinium.(Cd-Gd) shields mounted on the pool tank projection are designed to reduce which ONE of the following
. types of radiation?
A. Fast Neutrons B. Therral Neutrons C. Beta particles D. Gamma radiation QUESTION: 011 (1.00)
he Constant Air Monitors (CAMS) are
, most sensitive to which ONE of the following types of radiati;n?
A. Noble Gases B. Nitrogen-16 C. Fission Fragments D. Argon-41 QUESTION: 012 (1.00) The reactor ventilation air filters should be changed when which ONE of the following differential pressures is reached? A. 3.6 inches of water B. 3.6 inches of mercury C. 3.6 psia D. 3.6 psig (***** CATEGORY C CONTINUED ON NEXT PAGE *****)
C. PLANT AND-RAD MONITORING SYSTEMS Page 31 QUESTION: 013 (1.00) The AFRRI TRIGA reactor is operating at 50% power steady state with the primary and secondary water system operating normally when a primary water systeia heat exchanger tube leak necurs. Which ONE of the following events is a result of this malfunction? A. Reactor power decreases B. Reactor power increases C. Reactor pool level decreases D. Reactor pool level increases QUESTION: 014 (1.00) Which ONE of the following nuclides is the largest contributer to the stack gas monitor reading during operation? A. Nitrogen-13 B. Oxygen-15 C. Nitrogen-16 D. Argon-41' l l QUESTION: 015 (1.00) l Which ONE of the following radiation monitoring devices will l initiate a closure of the reactor room ventilation supply and ! cxhaust dampers? A. RAM R-1 Pool Surface B. RAM R-6 On the Air Exhaust-Duct C. Primary CAM In Reactor Room D. RAM E-3 In Prep Area (***** CATEGORY C CONTINUED ON NEXT PAGE *****)
, ,,. -- n...,.. -,, --w- ,,,
C.. PEANT AND RAD MONITORING SYSTEMS Page 32 QUESTION: 016 (1.00) Most of the penetrations into the reactor room are sealed and cannot be opened. Which ONE of the following is the exception? A. Control room air conditioner B. Windows between the control room and adjacent offices C. Conduit running through " expansion" penetrations D. Piping which penetrates to ano':her contained area QUESTION: 017 (1.00) Which ONE of the following describes the range covered and the operation of the nuclear instrurientation WIDE RANGE LGG CHANNEL? A. Range 0.1 watt to 1.0 MW (eight decades) The lower six decades use a pulse count technique; the upper four decades use a campbelling technique. B. Range 0.001 watt to 1.0 MW (ten decades) The lower four decades use a pulse count technique; the upper six decades use a campbelling technique. C. Range 0.001-watt to 1.0 MW (ten decades) The lower six-decades use a pulse count technique; the upper four decades use a campbelling technique. D. Range 0.1 watt to 1.0 MW (eight decades) The lower four decades use a pulse count technique; the upper six decades use a campbelling technique. (***** CATEGORY C CONTINUED ON NEXT PACE *****)
C. Page 33 P(ANT AND RAD MONITORING SYSTEMS 4 j QUESTION: 018 (1.00) Which ONE of the following is the reason air pressure at 9 psi is supplied to the shield door bearings? A. Prevents grease from escaping from the bearings and binding the door if the seals fail B. Prevents air leakage from the reactor tank to the outside atmosphere through the bearings C. Provides a lifting " cushion" to minimize bearing wear during door operation D. Provides a seal to minimize the ingress of water into the door bearing housings if the seals fail QUESTION: 019 (1.00) Which ONE of the following conditions must be satisfied before the Exposure Room #2 plug door can be opened? A. Reactor core is in POS I and the lead shield doors are c'.osed. B. Reactor core is in POS II and the lead shield doors are closed. C. Reactor core is in POS III and the lead shield doors are open. D. Reactor core is in POS II and the lead shield doors are open. (***** CATEGORY C CONTINUED ON NEXT PAGE *****) .
J PtANT AND RAD MONITORING SYSTEM" Page 34 QUESTION: 02r '1.00) In accordant, 4th Procedure VII, REACTOR CORE LOADING AND UNLOADING, which ONE of the following is the correct core unloading sequence? A. The core is unloaded starting with "F" ring and ending with the "B" ring. B. The core is unloaded starting with "B" ring and ending with the "F" ring. C. he core is unloaded starting with "Al" ring and ending with the "F" ring. D. The core is unloaded starting with "F" ring and ending with the "Al" ring. l' I i (***** END OF CATEGORY C *****) (********** END OF EXAMINATION **********) i
A. RN THEORY, THERMO & FAC OP CHARS Page 35 ANSWER: 001 (1.00)
- 1. c
REFERENCE:
Fundamentals of Nuclear Reactor Engineering (Pg 62-65) ANSWER: 002 (1.00) D. REFERE!1CE: Fundamentals of Nuclear Reactor Engineering (Pg 8) MISWER: 003 (1.00) C.
REFERENCE:
AFRRI Technical Specifications 3.1.3.a (pg 8) MISWER: 004 (1.00) C.
REFERENCE:
Fundamentals of Nuclear Reactor Engineering, (pg 14) ANSWER: 005 (1.00) D. (***** CATEGORY A CONTINUED ON NEXT PAGE *****)
A.- RX THEORY', THERMO & FAC OP CHARS- Page 36
REFERENCE:
Fundamentals of Nuclear Reactor Engineering, (pg 55) ANSWER: 006 (1.00) C.
REFERENCE:
Operations manual for the AFRR1 TRUGA Mark-F Reactor (pg 37)
- ANSWER: 007 (1.00)
C.
REFERENCE:
Tundamentals of Nuclear Reactor Engineering (pg 23) ANSWER: 008 (1.00) B.
REFERENCE:
AFRRI TRIGA MARK-F Reference Package ANSWER:- 009 (1.00) C. (***** CATEGORY A CONTINUED ON NEXT PAGE *****)
_ _ _ _ . ~ . . _ . . _ . . _ _ . . _ . _ _ _ __ _ _._ _ ._-._ _ - RX. THEORY, THERMO & FAC OP CilARS Page 37 A.
REFERENCE:
AFRRI TRIGA MARK-F Reference Package, Power Coefficient of R2 activity Curve ANSWER: 010 (1.00) D.
REFERENCE:
Fundamentals of Nuclear Reactor Engineering (pg 85) ANSWER: 011 (1.00) A. .
REFERENCE:
Fundamentals of Nuclear Reactor Engineering (pg 120) 'l-ANSWER: 012 (1.00) ll A.
REFERENCE:
- AFRRI TRIGA MARK-F Reference Package, Reactor Parameters
'l i ANSWER: 013 (1.00) B.
REFERENCE:
L Fundamentals of Nuclear Reactor Engineering (pg 63) I (***** CATEGORY A CONTINUED ON NEXT PAGE *****) l .- - . - _ __ , __
A. RX THEORY, THERMO 6 FAC OP CHARS Page 38 ANSWER: 014 (1.00) D.
REFERENCE:
Fundamentals of Nuclear Reactor Engineering, C. 3, Para. 85.(pg 76) ANSWER: 015 (1.00) C.
REFERENCE:
Fundamentals of Nuclear Reactor Engineering, (pg 69) ANSWER: 016 (1.00) A.
REFERENCE:
. Safety Analysis Report (pg 4-16)
ANSWER: 017 (1.00) A.
REFERENCE:
-Safety Analysis Report (p 4-27)
- ANSWER
- 018 (1.00)
C. l [ (***** CATEGORY A CONTINUED ON NEXT PAGE *****)
, _ . . . .. - .- .~ .. _ - . _ _ _ _ . .
A,- RX THEORY, THERMO & FAC OP. CHARS Page 39
REFERENCE:
l Safety Analysis Report,-section 4.16.3 (pg 4-39) l ANSWER: 019 (1.00' A.
REFERENCE:
Safety Analysis Report, section 4.7, (pg 4-12) ANSWER: 020 (1.00) c.
REFERENCE:
AFRRI Question Bank l [ (***** END OF CATEGORY A *****) ,
B. NORMAL /EMERG PROCEDURES & RAD CON Page 40 1 I l 1 l ANSWER: 001 (1.00)
.A..
REFERENCE:
.AFRRI Emergency Response Guidebook J
ANSWER: 002 (1.00) C..
REFERENCE:
AFRRI TRIGA MARK-F Operating Procedure I Tab A,section 8.a ANSWER: 003 (1.00) C.
REFERENCE:
AFRRI TRI3A MARK-F Operating Procedure VIII, Tab G, step 2 ANSWER: 004 (1.00) C.
REFERENCE:
AFRRT TRIGA MARK-F Technical Specification 6.3.2 (***** CATEGORY B CONTINUED ON NEXT PAGE *****)
B. NORMAL /EMERG PROCEDURES & RAD CON Pac e 41 i l 1 ANSWER: 005 (1.00) C.
REFERENCE:
AFRRI TRIGA MARK-F Emergency Plan, Section 3.1.1,pg 3-1 ANSWER: 006 (1.00) B.
REFERENCE:
AFRRI TRIGA MARK-F Operating Procedure VIII, Tab F-1 ANSWER: 007 (1.00) C. REFEREi?CE:-
.AFRRI TRIGA MARK-F Emergency Plan, Section 6.2, pg 6-1
!. ANSWER: 008 (1.00). C.
REFERENCE:
!- AFRRI TRIGA MARK-F Operating Procedures, Procedure I, Tab B, L- section 1.e l l ANSWER: . 009 (1.00T D. (***** CATEGORY B CONTINUED ON NEXT PAGE *****)
B. HORMAL/EMERG PROCEDURES & RAD. CON. Page 42
REFERENCE:
AFRRI Emergency Action Procedures, Appendix B, Personnel
-Rosters, pg B-1 ANSWER: 010 (1.00)
B.
REFERENCE:
AFRRI Technical Specifications 1.4, pg 1 -ANSWER: 011 (1.00) B.
REFERENCE:
AFRRI TRIGA MARK-F Reactor Operating Procedures, Procedure I, Tab A, section 3.a ANSWER: 012- (1.00) A.
REFERENCE:
Emergency Classification System and Emergency Action levels, Table 4-1, pg 4-2
~ ANSWER: 013 (1.00)
A.. (***** CATEGORY B CONTINUED ON NEXT PAGE *****) _. - _ =_ , , . _._
l B.. NORIGL/EMERG PROCEDURES & RAD CON- Page=43
REFERENCE:
AFRRI MARK-F Reactor Operating Procedures Sectio- 'II I , Tab D
' ANSWER: 014 (1.00)
C.
REFERENCE:
Equation Sheet ANSWER: 015 (1.00) D. -
REFERENCE:
10 CFR 20.101(a) 1 ANSWER: 016 (1.00) D.
REFERENCE:
AFRRI MARK-F Definition 1.20 , pg 3 ANSWER: 017 (1.00) C.
REFERENCE:
AFRRI MARK-F Technical Specifications 6.1.3.2, pg 30-31 (***** CATEGORY B CONTINUED ON NEXT PAGE *****)
._~ , ._ . . - . ... - - . . _ _ _ _ _ . .. . . . . - ._
B. NORMAL /EMERG PROCEDURES & RAD CON Page 44 ANSWER: 010 (1.00)
- 2. l Y
REFERENCE:
i AFRRI MARK-F Technical Specification 2.1, pg 5 l l ANSWER: 019 (1.00) i C.
REFERENCE:
AFRRI'TRIGA Technical Specification 6.4.2,pg 34 ANSWER: 020 (1.00) D.
REFERENCE:
AFRRI TRIGA SAR, section 4.12, pg 4-31 l l l (***** END OF CATEGORY B *****) l l
C. PrANT AND RAD MONITORING SYSTEMS Page 45 ANSWER: 001 (1.00) C. c A- IA
REFERENCE:
AFRRI TRIGA MARK-F Safe- .nalysis Report Section 4.3, pg 4-6 ANSWER: 002 (1.00) C.
REFERENCE:
AFRRI SAR , pg 4-34/36 ANSWER: 003 (1.00) A.
REFERENCE:
AFRRI TRIGA MARK-F Safety Analysis Report Section 3.7.4, pg 3-48 ANSWER: 004 (1.00) B.
REFERENCE:
AFRRI TRIGA MARK-F Safety Analysis Report 3.6.3.2 , pg 3-42 (***** CATEGORY C CONTINUED ON NEXT PAGE *****) ,
C. PLANT AND RAD MONITORING SYSTEMS Page 40 ANSWER:- 005 (1.00) B
REFERENCE:
AFRRI TRIGA MARK-F Technical Specifications section 3.3.a, pg 12 ANSWER: 006 (1.00) B.
REFERENCE:
AFRRI TRIGA MARK-F Technical Specification 3.6.c, pg 16 ANSWER: 007 (1.00) c.
REFERENCE:
AFRRI TRIGA MARK-F Safety Analysis Report Section 6.3.2.2,pg 6-17 ANSWER: 008 (1.00) B.
REFERENCE:
AFRRI TRIGA MARK-F Safety Analysis Report Section 3.3.3 4 ANSWER: 009 (1.00) D. O,& A (***** CATEGORY C CONTINUED ON NEXT PAGE *****)
l C. PLANT AND RAD MONITORING SYSTEMS Page 47 ) i
REFERENCE:
AFRRI Safety Analysis Report Section 6.6.3, pg 6-21/22 ANSWER: 010 (1.00) D.
REFERENCE:
AFRRI Safety Analysis Report Section 5.2.1, pg 5-4 ANSWER: 011 (1.00) C.
REFERENCE:
AFRRI TRIGA MARK-F Technical Specification 3.5.1 ANSWER: 012 (1.00) A.
REFERENCE:
AFRRI Manual 82.1 pp 63 ANSWER: 013 (1.00) D.
REFERENCE:
AFRRI Safety Analysis Report Section 3.3.6, pg 3-20 (***** CATEGORY C CONTINUED ON NEXT PAGE *****)
C. PLANT AND RAD MONITORING SYSTEMS Page 48 ANSWER: 014 (1.00) D.
REFERENCE:
AFARI Safety Analysis Report Section 3.4.1.2, pg 3-23 ANSWER: 015 (1.00) C.
REFERENCE:
AFRRI TRIGA MARK-F Safety Analysis Report, Section 3.6.2 ANSWER: 016 (1.00) A.
REFERENCE:
AFRRI Safety Analysis Report, Section 3.2.4 , pg 3-14 ANSWER: 017 (1.00) C.
REFERENCE:
AFRRI TRIGA MARK-F Safety Analysis Report Section 4.11.2,pg 4-28 ANSWER: 018 (1.00) D. (***** CATEGORY C CONTINUED ON NEXT PAGE *****) ;
C. PLANT AND RAD MONITORING SYSTEMS Page 49
--.4
REFERENCE:
I l AFRRI TRIGA MARK-F Safety Analysis Report Section 3.7.4, pg 3-48 i ANSWER: 019 (1.00) A. REFERENCE. AFRRI SAR , pg 4-28 ANSWER: 020 (1.00) A.
REFERENCE:
AFRRI Operating Procedure VII, Section 3 (***** END OF CATEGORY C *****) (********** END OF EXAMINATION **********)
Page 1
,A. RX THLORY. THERMO & FAC OP CHARS
' ANSWER -K E Y 001 g' 008 B 015 C 002- D 009 C 016 A 003 C 010 D 017 A 004 C 011 A 018 C 005 D 012 A 019 A 006 C 013 B 020 C 007 C 014 D B. NORMAL /EMERG PROCEDURES & RAD CON 001 A 008 C 015 B 002 C 009 D 016 D 003 C 030 B 017 C 004 C 011 B 018 5 d/ 005 C 012 A 019 C 006 B 013 A 020 D 007 C 014 C
O , _C. PLANT AND RAD MONITORING SYSTEMS 001 C ta 0 008 B 015 C 002 C 009 D Cil / 016 A 003 A 010 B 017 C 004 B 011 C 018 D 005 B 012 A 019 A 006 B 013 D 020 A 007 C 014 D (********** END OF EXAMINATION **********) s
TEST CROSS REFERENCE Page 1 e-0:
- SRO Exam 7?? Reactor Orcani zed by Quest ion Number QUESTION VALUE REFERENCE 001 1.00 9000499 002 1.00 9000500 003 1.00 9000501 004 1.00 9000502 005 1.00 9000503 006 1.00 9000504 007 1.00 9000505 008 1.00 9000506 009 1.00 9000507 010 1.00 9000508 011 1.00 9000509 012 1.00 9000510 013 1.00 9000511 014 1.00 9000512 015 1.00 9000513 016 1.00 9000514 017 1.00 9000515 018 1.00 9000516 019 1.00 9000517 020 1.00 9000518 20.00 001 1.00 9000519 002 1.00 9000520 003 1.00 9000521 004 1.00 9000522 005 1.00 9000523 006 1.00 9000524 007 1.00 9000525 008 1.00 9000526 009 1.00 9000527 010 1.00 9000528 011 1.00 9000529 012 1.00 9000530 013 1.00 9000531 014 1.00 9000532 015 1.00 9000533 016 1.00 9000534 017 1.00 9000535 018 1.00 9000536 l
019 1.00 9000537 1 020 1.00 9000538 20.00 001 1.00 9000539 002 1.00 9000540 003 1.00 9000541 l
- TEST CROSS REFERENCE Page 2 e'
SRO Exam ??? Roactor orq anized by Quest ion Nunbor OUESTION VALUE REFERENCE 004 1.00 9000542 005 1.00 9000543 006 1.00 9000544 007 1.00 9000545 008 1.00 9000546 009 1.00 9000547 010 1.00 9000548 011 1.00 9000549 012 1.00 9000550 013 1.00 9000551 014 1.00 9000552 015 1.00 9000553 016 1.00 9000554 017 1.00 9000555 018 1.00 9000556 019 1.00 9000557 020 1.00 9000558 20.00 WWWWmW 60.00 l l - - - - _ - _ _ _ _ - _ _ _ _ _ _ - _ . _.___- _ _-_ _ - __ _ _ _ _ _ _ _ _____}}