ML20056C360
| ML20056C360 | |
| Person / Time | |
|---|---|
| Site: | Kansas State University |
| Issue date: | 05/05/1993 |
| From: | Caldwell J, Isaac P Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20056C359 | List: |
| References | |
| 50-188-OL-93-01, 50-188-OL-93-1, NUDOCS 9305200100 | |
| Download: ML20056C360 (3) | |
Text
{{#Wiki_filter:- 1 l i ENCLOSURE I ; l U. S. NUCLEAR REGULATORY COMMISSION OPERATOR LICENSING RE0VAllFICAT10N EXAMINATION REPORT t REPORT NO.: 50-188/0L-93-01 t FACILITY DOCKET NO.: 50-188 . FACILITY LICENSE NO.: R-88 FACILITY: Kansas State University 1 EXAMINATION DATES: April 28-29, 1993 EXAMINER: Patrick Isaac, Chief Examiner SUBMITTED BY: g' ,h' ,- 8[5/f1 Fr i Is C f Examiner Date APPROVED BY: % Ji? s L. Cald Ell TChief 5/543 / Date . N -Power Reactor Section 0 erator Licensing Branch i Division of Reactor Controls and Human Factors, Office of Nuclear Reactor Regulation
SUMMARY
Written and Operating requalification examinations were administered to one Senior Reactor Operator (SRO). The SRO passed the examinations. , I 6 t 9305200100 930505 PDR ADOCK 05000188 V PDR l
l 1 l r REPORT DETAILS
- 1. Examiners- i Patrick Isaac, Chief Examiner !
John E. Kirkland, Reactor Supervisor l
- 2. Results: i t
R0 SR0 Total i (Pass / Fail) (Pass / Fail (Pass / Fail) ! NRC Grading: N/A 1/0 1/0 f i Facility Grading: N/A 1/0 1/0 [ t t
- 3. Written Examination: i i
i The written examination was administered on April-28, 1993 to one Senior l Reactor Operator. The SRO passed the written examination. , 4I l
- 4. Operating Tests:
Operating Tests were administered on April 29, 1993. The SR0 passed the ; operating test. ! l l 5. Exit Meeting: j 5 Personnel attending: i t Mr. Patrick J. Isaac, NRC Examiner l Mr. John E. Kirkland, Reactor Supervisor i The exit meeting was conducted on April 29, 1993. There were no generic concerns raised by the examiners. The NRC Examiner noted the good ; physical condition of the plant. l i 1
.- . ENCI.0SURE 2 a
SENIOR REACTOR OPERATOR REQUALIFICATION EXAM Written Examination April 28.1993
Theo_rv Thermodynamics. and Facili?v Operating Characteristics Page 1 l l QUESTION: 01 , When a control rod is inserted into the cor.:, ' .' does the thermal utilization factor (f) , change and why?
- a. f decreases due to a decrease in poison cross section
- b. f decreases due to an increase in poison crcss section
- c. fincreases due to a decrease in poison cross section
- d. fincreases due to an increase in poison cross section !
i QUESTION: 02 Assuming that the effective neutron lifetime in the TRIGA core is 40 s, what is the reactor period for a prompt critical reactor? l
- a. 0.06 s I
- b. 0.01 s -l
- c. 0.006 s
- d. 0.001 s QUESTION: 03 j The ratio of a radionuclide is found to decrease by 30% in one week. Which of the !
following is the best estimate of the radionuclide's half-life? ;
- a. 443.8 hours i i
- b. 326.5 hours ,
- c. 219.5 hours
- d. 96.7 hours !
f QUESTION: 04 , Which of the following materials would not be a good choice for a TRIGA control rod? ,
- a. Beryllium
- b. Boron :
- c. Cadmium -!
- d. Hafnium ,
i (" SECTION A CONTINUED ON NEXT PAGE **) l 1
Theory. Thermodynamics. and Facility Operatine Characteristics Page 2 I QUESTION: 05 1 Which of the following best describes the effect ofloading fuel from the SOURCE to the DETECTOR during initial fuel loading?
- a. same effect as loading from DETECTOR to SOURCE
- b. if the same number of fuel elements are added each time, the i
estimation will not change after the first loading
- c. leads to an under-estimation of the number of elements needed for criticality
- d. leads to an over-estimation of the number of elements needed for criticality QUESTION: 06 How would reactor power be affected if the Rotary Specimen Rack (RSR) flooded?
- a. power would remain constant .
- b. power would increase !
- c. power would decrease
- d. power would increase, then decrease back to its initial value- ,
due to the power coefficient . ! t QUESTION: 07 i Using the parameters associated with the TRIGA cooling system, what would be the l temperature difference across the SECONDARY side of the heat exchanger if the primary sidc temperature difference were 5 C.
- a. 2.8 C !
- b. 3.1 C l
- c. 8.0 C
- d. 8.8 C i
I (** SECTION A CONTINUED ON NEXT PAGE **) t
. Theorv. Thermodynamics, and Facility Operating Characteristics Page 3 !
OUESTION: 08 l Which of the following reaction products carries off the most amount of fission energy?
- a. kinetic energy of fission fragments
- b. fast neutrons
- c. fission gamma energy :
i
- d. fission product beta energy -f OUESTION: 09 i
Which of the following best describes how and why the total delayed neutron fraction (S) differs from the effective delayed neutron fraction (S,n)? i
- a. S is lower due to a fewer number of delayed neutrons .
- b. S is higher due to a lower number of delayed neutrons I
- c. # is lower due to lower energies of delayed neutrons
- d. S is higher due to lower energies of delayed neutrons l i
QUESTION: 10 A cm' sample of Uranium with a 233 U number density of 10" atoms em is inserted into the l RSR with a reactor power level of 250 kW. What is the resulting fission reaction rate? l (a, = 678 b, o, = 577 b)
- a. 3.4 x 10" fissions em 's .
- b. 2.9 x 10" fissions ems2 :
- c. 1.2 x 10" fissions ems-'
- d. 1.0 x 10" fissions em-5 s' I
t a' i
~
?
?
(** SECTION A CONTINUED ON NEXT PAGE **) 0 b i
Theory. Thermodynamics. and Facility Operatine Characteristics Page 4 l I i QUESTION: 11 j Which of the following best describes the process by which the Am-Be neutron source produces neutrons? ! i
- a. (7,p) reaction of the Americium j
- b. (y,p) reaction of the Beryllium ;
- c. (a,n) reaction of the Americium
- d. (a,n) reaction of the Beryllium {
i
. i QUESTION: 12 l Which of the following best describes the process / mechanism that produces coolant flow !
through the core during operation?
- a. forced convection ,
- b. free convection
- c. conduction 1
- d. radiation j QUESTION: 13 {
Consider elemental Uranium (A = 238.07) with a mass density of 18.9 g em-8, a, = 8.3 b, 3 and a, = 7.68 b. What is the total macroscopic cross section of the Uranium j
- a. 0.03 cm-'
- b. 0.367 cm-'
- c. 0.397 cm-'
- d. 0.765 cm
QUESTION: 14 , Which of the following best describes Xenon behavior following a SCRAM?
- a. Xe increases mainly due to I decay exceeding Xe decay
- b. Xe decreases mainly due to Xe decay exceeding I decay _
i
- c. Xe decreases mainly due to the loss of fission production
- d. Xe increases mainly due to decreased loss by absorption ] l
(" SECTION A CONTINUED ON NEXT PAGE ") l T
' Theory. Thermodynamics and Facility Operatine Characteristics Page 5
. i i QUESTION: 15 ; The reactor is initially at 250 kW and a SCRAM occurs which decreases power to I kW ' in the first minute following the SCRAM. What is the approximate steady state power four minutes after the SCRAM?
- a. 963 W
- b. 951 W ,
- c. 105 W ,
- d. 50 W QUESTION: 16 What is meant by the statement "the thermal flux energy spectrum is 'hard' in a TRIGA -
reactor core? ,
- a. average neutron energy is lower than normal fission spectrums .;
- b. average neutron energy is higher than normal fission spectrums
- c. flux density is lower than other 250 kW cores
- d. flux density is higher than other 250 kW cores ,
QUESTION: 17 l Which of the following best describes why zirconium hydride contributes to the inherently ! large negative temperature coefficient? l
- a. The mass of the zirconium prevents some neutrons from r slowing down to thermal energies !
- b. Neutrons are caught in the interstitials between the zirconium l and hydrogen atoms which prevent them from being absorbed {
in the fuel
- c. Neutrons are absorbed in the zirconium instead of the fuel j
- d. The hydrogen may increase the neutron energy due to increased vibrational energy states at higher temperatures l, i
i 5 I (" SECTION A CONTINUED ON NEXT PAGE ") j 3 l
"' ~ Theory. Thermodynamics. and Facility Operating Characteristics Page 6 i i i QUESTION: 18 Which of the following is not a necessary property for a good moderator? j
- a. High scattering cross section ,
- b. High energy loss per collision ,
~
- c. High absorption cross section
- d. Low absorption cross section QUESTION: 19 The reactor is initially critical with the following conditions: :
Power = IW Shim Rod position = 550 i Water temperature = 20 C Reg Rod position = 275 : Pulse Rod fully withdrawn Using the attached rod worth curve for the Reg Rod, what is the rod position required to , achieve a stable reactor period of +10 s?
- a. 307 b -. 340
- c. 368 !
- d. 397 QUESTION: 20 P After the transient in the previous problem is completed, what would be the approximate steady state reactor power?
- a. 40 kW ;
- b. 30 kW
- c. 20 kW ;
- d. 10 kW i
(** END OF SECTION A **) i
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1 Normal / Emergency Procedures and Radiation Control Page 8 QUESTION: 01 A "Co point source of unknown strength with two gamma-rays with energies of 1.2 and 1.3 Mev is covered by a % inch lead shield, and a radiation intensity of 100 mR/h is measured 25 feet away. Which of the following is the best estimate of the strength of the source? t You may neglect buildup. (for lead, p/p = 2.1 in2lbm, p = 0.41 lbm in~') ;
- a. 4.2 Ci l
- b. 5.2 Ci ;
- c. 10.3 Ci
- d. 15.6 Ci :
I QUESTION: 02 A person is exposed (front to rear) for 30 seconds to a broad beam of 1-MeV pilotons. A personnel dosimeter, calibrated to read (deep) dose equivalent index, indicates 175 mrem. Which of the following is the best estimate of the effective dose equivalent incurred by the 2 person? (N (A4P) = 4.6 x 10* cSv cm ,2 %u = 5.07 x 10* cSv cm )
- a. 128 mrem ;
~
- b. 157 mrem
- c. 175 mrem ,
- d. 193 mrem F
QUESTION: 03 j , Which of the following is a proper choice for the quality factor of neutrons if the neutron energy is unknown? ,
- a. 1
- b. 5
- c. 10 i
- d. 50 l i
l r l (** SECTION B CONTINUED ON NEXT PAGE **) n
i l Normal / Emergency Procedures and Radiation Control Page 9 l l QUESTION: 04 ) 1 In order for the reactor to be operated, which of the following nuclear instruments must l be functioning?
- a. log count rate, linear, percent po.ver
- b. log count rate, log, percent power !
- c. log, linear, percent power !
e
- d. log count rate, log, linear, percent power )
QUESTION: 05 : A terrorist phones in a bomb threat to the reactor facility. Which of the following , emergency classifications should the emergency director assign?
- a. General Emergency
- b. Site Emergency
- c. Alert .
i
- d. Unusual Event j QUESTION: 06 -
After a pulse of the reactor has been performed, the reactor will SCRAM when the mode l selector switch is taken from PULSE to STEADY STATE. Which of the followmg ; SCRAM's occurs when the mode selector switch is moved?
-l
- a. period
- b. linear power
- c. percent power ;
- d. fuel temperature l 2
r (** SECTION B CONTINUED ON NEXT PAGE ") i i i
Eqrmal/ Emergency Procedures and Radiation Control Page 10 OUESTION: 07 i Which of the following statements is not true?
- a. source material does not include special nuclear material
- b. special nuclear material does not include source material
- c. byproduct material does not include special nuclear material
- d. byproduct material does not include source material QUESTION: 08 Which of the following methods of waste disposal is not authorized? ,
- a. decay in storage i
- b. effluent release
- c. incineration j
- d. burial -
OUESTION: 09 Which of the following reactor facility conditions does not require the use of personnel neutron dosimetry in the reactor bay? I
- a. anytimc the reactor is operating
- b. anytime a beamport or thermal column is open 252 i
- c. anytime the Cf source is in operation
- d. anytime an escorted tour is conducted r
OUESTION: 10 Control rod drop times are being measured. Which of the following methods are used to initiate the dropped rod?
- a. remove magnet power
- b. percent power SCRAM
- c. period SCRAM ,
- d. SCRAM power SCRAM
(** SECTION B CONTINUED ON NEXT PAGE **) ; 1
( Normal / Emergency Procedures and Radiation Control Page 11 QUESTION: 11 ! During a power calibration, indicated linear power indicates 0.85 x 2.5 x 105, and the pool l water temperature has increased 5.8 C in 30 minutes. Which of the following statements . conecrning power levels is correct? {
- a. indicated power is less than calculated power, and the linear !
channel needs adjustment j
- b. indicated power is less than calculated power, and the linear channel does not need adjustment ,
- c. indicated power is greater than calculated power, and the linear channel needs adjustment -
- d. indicated power is greater than calculated power, and the l linear channel does not need adjustment :
r QUESTION: 12 ! t Which of the following types of radiation is the least penetrating? l
- a. alpha l
- b. beta
- c. gamma l'
- d. fast neutrons i
QUESTION: 13 Under which of the following conditions is an unlicensed person allowed to manipulate the reactor controls? :
- a. under the direct supervision of a licensed operator during a ;
reactor tour
- b. when the Chairman of the Reactor Safeguards Committee is 1 present in the control room i
- c. under the direct supervision of a licensed operator as part of ;
an individuals training for licensing ,
- d. upon approval by the Reactor Safeguards Committee l
i (** SECTION B CONTINUED ON NEXT PAGE ")
~' '
' Normal / Emergency Procedures and Radiation Control Page 12 l
QUESTION: 14 ; During calibration of the CAM, a Mc source is used and gives a reading on the CAM of 400 cpm. Which of the following is the correct alarm setpoint?
- a. 378 cpm
- b. 426 cpm
- c. 488 cpm
- d. 514 cpm QUESTION: 15 A "Co source is counted for 30 s using a HPGe detector with no dead time, and the area under the 1.2 MeV peak is 120,000 counts. Assuming a yield of 1 for 1.2 MeV gamma-rays and a detector efficiency of 6%, which of the following is the best estimate of the activity <
of the "Co sample?
- a. 0.46 pCi
- b. 0.87 pCi
- c. 1.80 pCi
- d. 2.58 pCi QUESTION: 16 Which of the following statements best describes alpha radiation?
- a. for the same curie content, alpha radiation poses a greater !
internal hazard than beta or gamma radiation '
- b. alpha particles have a higher quality factor than gamma-rays, ;
but a lower quality factor than beta particles
- c. alpha particles damage the body mainly due to their high net ' )'
negative charge
- d. alpha particles penetrate further than beta particles l
I i (** SECTION B CONTINUED ON NEXT PAGE **); l
P
~'
' Normal / Emergency Procedures and Radiation Control Page 13 4
i QUESTION: 17 A fuel element is being transferred from a storage rack to a NEW position in the core. ( Which of the following actions are required prior to putting the element into the core?
- a. the fuel element must be gaged
- b. the fuel element serial number must be verified
- c. the fuel element must be gaged and the serial number must be verified
- d. the fuel element is neither gaged nor the serial number verified ,
QUESTION: 18 Who's permission is required prior to using the D2 O calibration facility?
- a. the Chairman of the Reactor Safeguards Committee i
- b. the Radiation Safety Officer
- c. the Facility Director
- d. the Reactor Supervisor QUESTION: 19 .
Radiation levels measured 10 feet from a point gamma-ray source indicates 50 mR/h. A worker needs to work 2.5 feet from the source. Which of the following is the longest time the individual can work without exceeding his quarterly dose limits, assuming no previous , exposure during the quarter?
- a. 1.0 h
- b. 1.5 h
- c. 2.0 h >
- d. 2.5 h ;
t i i (** END OF SECTION B **) i
' Plant and Radiation Monitoring Systems Page 14 t
OUESTION: 01 ! Regarding the Shim and/or Reg Rod, the blue light is off, the red light is off, the white i light is off, and the yellow light is off. Which of the following best describes the condition of the control rod and control rod drive? ;
- a. the rod is full down, the rod drive is full down, the magnets are energized, and the rod and drive are in contact
- b. the rod is full down, the rod drive is in an intermediate position, and the magnet is de-energized
- c. the rod and rod drive are in contact, with magnets energized, in an intermediate position l
- d. the rod and rod drive are fully inserted with magnets energized !
t OUESTION: 02 Which of the following radiation detectors does not have an output intensity (current or l pulse height) proportional to the incident radiation energy? ;
- a. GM tube !
- b. ion chamber
- c. scintillation !
- d. proportional ;
.l OUESTION: 03 .
Which of the following mechanisms may not be used to remove control console power? ) I
- a. power switch on the console
- b. line conditioner 1
- c. reactor key
- d. control breaker l
(** SECTION C CONTINUED ON NEXT PAGE **)
'~ '
Plant and Radiation Monitoring Systems Page 15 , QUESTION: 04 The RO-3C (Rad Owl) instrument is used to measure which types of radiation?
- a. # only
- b. s and y only
- c. y only !
- d. o and B only QUESTION: 05 What type of detector is the Model 12-4 (REM ball)?
- a. GM tube
- b. ion chamber
- c. scintillation ;
- d. BF3 proportional i
QUESTION: 06 A fission chamber is used to supply input pulses to which of the following power channels?
- a. log count rate l
- b. linear power
- c. log power
- d. percent power [
QUESTION: 07 A full scale reading on the activity meter located on the bottom portion of the console corresponds to which of the following dose rates? ;
- a. 1 R/h
- b. 500 mR/h
- c. 100 mR/h i
. d. 50 mR/h ;
(** SECTION C CONTINUED ON NEXT PAGE **)- l
- Plant and Radiation Monitoring Systems Page 16 QUESTION: 08 If the mode selector switch on the control console is moved from STEADY STATE to .
PULSE mode, which of the following action does NOT occur?
- a. the pulse rod is the only rod which can be moved
- b. the two-second time delay on the pulse rod is engaged
- c. the percent power SCRAM is rendered inoperative
- d. fuel temperature 2 reads directly on the dual meter without having to use the toggle switch QUESTION: 09 (2 p =t:y Match the appropriate measurement techniques employed to obtain the corresponding measurement on the control console.
t
- a. fuel temperature 1. thermocouple
- b. primary water temperature 2. GM tube '
- c. primary conductivity 3. titanium electrode
- d. pool water activity 4. nickel-alloy thermistor QUESTION: 10 I
The gamma-rays incident upon the log count rate channel do not cause a pulse to be counted. Which of the following best describes the reason gamma pulses are not counted?
- a. the log count rate detector has compensating voltage to ;
subtract gamma pulses from the signal
- b. the log count rate detector allows gamma-rays to pass through i the detector with no interaction j
- c. the log count rate detector counts only the large neutron pulses !
and does not count the smaller gamma pulses because of a ] pulse-height discriminator -
- d. the number of gamma-rays present are much smaller than the number of neutrons, thus statistically, the number of gamma i pulses are lost due to numbers !
l l l (** SECTION C CONTINUED ON NEXT PAGE ") i 1 i
.. ? . Plant and Radiation Monitoring Systems Page 17 ,
QUESTION: 11 l What does the small red light just to the lower left of the strip chart recorder indicate?
- a. high pool water activity i
- b. the light beam across the stairs leading to the O' level has been broken indicating someone has walked from the 0' to the 12' l level or from the 12' level to the O' level .
- c. the period SCRAM has been bypassed
- d. the lower level reactor bay door is open l,
QUESTION: 12 The Gadora detectors use a scintillation detector for radiation measurement. Which of the : following describes the output of the Gadora? .
- a. rad /h (or metric equivalent)
- b. rem /h (or metric equivalent) :
- c. roentgen per hour (or metric equivalent)
- d. counts per minute QUESTION: 13 l Which of the following is a function of the compressed air system? ,
- a. standard control rod motion 3
- b. secondary water control system
- c. rabbit sample transfer system
- d. automatic fire control system 1
i I l i (** SECTION C CONTINUED ON NEXT PAGE **) i
. Plant and Radiation Monitorine Systems Page 18 QUESTION: 14 Which of the following best describes the conditions which would cause the red light in the i hallway outside of the control room to illuminate? I
- a. either a RAM or CAM alarm in the reactor bay ;
- b. both a RAM and CAM alarm in the reactor bay ;
- c. either low pool water level or high sump level )
- d. either high activity or high conductivity of the primary QUESTION: 15 i The Continuous Air Monitor (CAM) is set to alarm at which of the following levels?
- a. the MPC of ""I in air
- b. the MPC of Ar in air
- c. the MPC of N in air l l
- d. the MPC of'H m air :
i QUESTION: 16 While performing a reactor bay-side checkout, the 22'Ra source is used to check the j
. response of the RAM's. Which of the following best describes the placement of the source .
and the expected reading of the RAM's? !
- a. a reading of approximately 2 mR/h 12" from the RAM ;
1
- b. a reading of approximately 2 mR/h 18" from the RAM ;
- c. a reading of approximately 10 mR/h 12" from the RAM ']
- d. a reading of approximately 10 mR/h IS" from the RAM !
'l I
i i (** SECTION C CONTINUED ON NEXT PAGE ")- l l 1
** Plant and Radiation Monitorine Systems Page 19 l
QUESTION: 17 ; Which of the following will NOT occur if the compressed air pressure falls below . approximately 45 psig?
- a. a warning light illuminates on the control console
- b. a warning light illuminates near the air compressor
- c. the pulse rod and shock absorber gradually insert into the core i if the pulse rod and shock absorber are withdrawn
- d. the air compressor will be running, if functioning properly QUESTION: 18 !
Which of the following is a true statement concerning the secondary cooling system?
- a. if the cooling system is not operable, the projected maximum temperature of the pool water must be calculated prior to any yeactor operations
- b. the cooling system must be operating prior to any reactor !
operations -
- c. the cooling system must be operable prior to any reactor operations ;
- d. the primaiy cooling system must be operating even if the secondary cooling system is not ,
QUESTION: 19 ' Which of the following describes why the control console has two indications of fuel i temperature, FT1 with a limit of 400 C, and FT2 with a limit of 450 C? ,
- a. FT1 measures fuel temperature during STEADY STATE operation only, and FT2 measures fuel temperature during i PULSE operation only
- b. FT1 measures E-ring fuel temperature only, and'FT2 measures B-ring fuel temperature only
- c. FT1 will indicate a warning light when its limit is reached, !
while FT2 will SCRAM when its limit is reached j
- d. FT1 limit is set so that the FT2 limit should not normally be ,
reached - i (** END OF SECTION C ") : (" END OF EXAM ") ; k ~
r EXAMINATION KEY FOR THE REQUALIFICATION EXAM FOR DR. RICHARD FAW Section A Section B Section C !
- 1. b 1. b 1. b I
- 2. c 2. b 2. a ;
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- 3. b 3. c 3. c i
- 4. a 4. a 4. b !
- 5. d 5. d 5. d l
- 6. c 6. a 6. a -
- 7. a 7. d 7. c !
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- 8. a 8. e d7
- 8. b j i
- 9. e 9. d 9. 1,4,3,2 -
- 10. d 10 b 10. e
- 11. d 11. b 11. d j
- 12. b 12. a 12. c ,
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- 13. d 13. c 13. b -!
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- 14. a 14. e 14. c- j
!;. c 15. c 15. a -
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- 16. b 16. a 16. b i
~ l 7. d 17. b 17. b -
- 18. c ~ 18. d 18. c
- 19. d 19. b 19. d
- 20. a 4
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