ML20205P293
| ML20205P293 | |
| Person / Time | |
|---|---|
| Site: | University of California - Irvine |
| Issue date: | 05/06/1986 |
| From: | Elin J, Morrill P NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | |
| Shared Package | |
| ML20205P288 | List: |
| References | |
| 50-326-OL-86-01, 50-326-OL-86-1, NUDOCS 8605210318 | |
| Download: ML20205P293 (100) | |
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EXAMINATION REPORT f Facility Docket No: 50-326 Exam Report No.: 50-326/0L-86-01 Facility Licensee: University of California, Irvine U.C. Irvine Nuclear Reactor Facility Irvine, California 92717 1
Facility License No.: R-116
. Examinations administered at the U.C. Irvine Research Reactor, Irvine, California.
1 Chief Examiner: -
Philip J Mo rill, Licensirig Examiner Date Signed Approved by: a b John El n, Op rations Section, Chief Date Signed Summary:
Examinations administered on April 8-9, 1986.
Written and oral examinations were administered to two RO candidates and '
one SRO candidate. The candidates passed these examinations.
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l 8605210318 860507
' $DR ADOCK 05000326 PDR b
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Resolutions to Facility Comments Irvine Research Reactor April 8,1986 R0 Examination Answer A.01 Typo. Zinc-hydride changed to zirc-hydride. ,
Answer A.05 The following statement was added to the answer key:
" Aluminum can containing source displaces moderator, therefore causing competing effects."
Question A.09 The following statement is noted at the end of the question in the answer key: "The facility recommends adding
' momentarily' between the words 'becomes' and ' infinite'."
Answer B.04 Changed to accept outer ring fuel elements, E, or G ring.
Question B.08 Changed to read "... as compared with the other control rods?"
Answer B.09 Full credit given for " pits have been dug."
Answer C.10 The following statement was noted after the answer: " Facility points out that 5-8 minutes is closer to the observed time."
Answer C.12 Changed to read "Because it takes several minutes..."
Question D.02 Changed to read "... what type of detector each is fed from."
Answer D.03c. The following statement was added: " Accept a description of rod and motor being in phase."
Ar.3wer D.05 Answer changed to FALSE. Neither reg nor control rod will withdraw when both are pushed.
Question D.10 Typo. Comarator changed to comparator.
Answer E.03 No change.
Answer E.08 Changed to also accept "outside reactor wall or inside the rabbit room."
Answer F.05 No change.
Answer G.04 No change.
Answer G.07 No change.
Answer G.10 Changed to read "30 mr."
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Resolutions to Facility Comments Irvine Research Reactor April 8, 1986
, SRO Examination 4
I Answer H-4(a) 1-135 is also a fission product. Agree, comment noted.
Question H-7 Change 3rd line to' read "briefly explain how each of
'these". Agree. The candidate did not question the omission.-
Question I-l The candidate may match one per one. A' gree, comment noted and partial credit given for that case.
Answer J-3 Compensated ion chamber may not be:affected at 100W.
'1 Agreed to give-partial credit to reflect this.
Answer J-6(3) Place " East" in' parentheses and add " window wall" and " corridor wall" which all are the same wall.
Agree, comment accepted.
Answer J-6(4) Place " South" in parentheses. Agree, commentfaccepted.
Answer J-9 "(d)" is also a correct answer. Agree, comment accepted.
Answer K-4 Dimensions are not correct. Reference material not accurate. Agreed to change key based on facility drawing furnished by Dr. Miller.
Answer K-7(B) Add "or when significant heat is generated in the sample".
Agree, comment. accepted.
Answer L-5 Add "At-least" before "I for every 5 people". Agree,.
comment accepted.
Answer L-6 Answer (a) and (b) could be combined. Agree, comment noted and accepted.
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U.S. NUCLEAR REGULATORY COMMISSION REACTOR OPERATOR LICENSE EXAMINATION Facility: Irvine Research Reactor Reactor Type: Test MRSTER A9swER KEY Date Administered: April 8, 1986
[
1 I Exan'iner: Huenefeld Candidate: Answer Key
- INSTRUCTIONS TO CANDIDATE
Use seperate paper for the answers. Write answers on one side only.
3taple question sheet on top of the answer sheets. Points for each question tre indicated in parenthesis after the question. The passing grade requires at least 70% in each category. Examination papers will be picked up six (6) hours after the examination starts.
Category % of Candidate's % of Value Total Score Cat. Value Category 15.1 15.1 A. Principles of Reactor Operation 13.5 13.5 B. Features of Facility Design 13.75 13.75 C. General Operating Characteristics
- 14.75 14.75 D. Instruments and Controls 14.4 14.4 E. Safety and Emergency Systems 14.5 14.5 F. Standard & Emergency Operating Procedures 14.0 14.0 G. Radiation Control and Safety 100 TOTALS
. Final Grade % l l !
) All work done on this examination is my own; I have neither given nor received l' l aid.
1 Candidate's Signature l
i Page 1 Irvine Research Reactor April 8,1986 Points Available A. PRINCIPLES OF REACTOR OPERATION (15.1) 00ESTION A.01 The " cell effect" is an important contributor to the pronpt negative temperature coefficient. Give a brief explanation of the cell effect. (2.0)
ANSWER A.01 When fuel temperature increases, the zirc-hydride temperature follows instantaneously, thus increasing the number of bound hydrogen atoms in excited levels. This increases the probability of speeding up neutrons resuiting in hardening of the neutron spectrum. This ultimately causes a decrease in fission probability... ergo a prompt reduction in reactivity. [+2.0]
Reference (s) A.01
- 1. Instruction Manual (IM) for the UCI TRIGA Reactor, p. 3-30.
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-Section A Continued on Next Page-l
o Page 2 Irvine Research Reactor April 8, 1986 Points Available QUESTION A.02 If heat flux at the surface of the fuel element is sufficiently large, then small bubbles will form at nucleation sites. This is called nucleate boiling.
- a. Should heat flux be increased by a' sufficient amount, a transition in the type of boiling occurs. What type of boiling occurs, and what are the resulting heat transfer ramifications? (2.0)
- b. How would a decrease in pool depth affect the potential for a transition in the type of heat transfer? Explain. (1.0)
ANSWER A.02
- a. Burn-out or stable film boiling. When this type of boiling occurs the heat transfer coefficient at the fuel surface is severely reduced resulting in a fuel temperature excursion. [+2.0]
- b. It would increase the potential for burnout by lowering the ambient pressure at the fuel clad wall. [+1.0]
Reference (s) A.02
- 1. Instruction Manual (IM) for the UCI TRIGA Reactor, p. 3-12.
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-Section A Continued on Next Page-l
O Page 3 Irvine Research Reactor April 8,1986 Points Available OVESTION A.03 If reactor power (neutron countrate) is increasing linearly (NOT exponentially) with no rod motion, what can you say about the reactivity in the core? (1.5)
ANSWER A.03
[or Source craicA.L )
A linear increase in/countrate can occur only if the reactor is exactly critical. That is, with K = 1, a constant amount of neutrons are being added each generation. [+1.5]
Reference (s) A.03
- 1. Instruction Manual (IM) for the UCI TRIGA Reactor, p. 3-25.
QUESTION A.04 When making changes to core configuration it is sometimes useful to make a 1/R plot. Is a 1/R plot more conservative if it has a concave upward shape OR a concave downward shape? (0.5)
ANSWER A.04 Concave upward [+0.5]
Reference (s) A.04
- 1. Instruction Manual (IM) for the UCI TRIGA Reactor, p. 3-59.
-Section A Continued on Next Page-
Page 4 Irvine Research Reactor April 8,1986 Points Available OUESTION A.05 Does the neutron source used in your reactor also affect the reactivity of the core? Explain. (1.5)
ANSWER A.05 Yes [+0.5]. The source itself is composed of fissionable material. E,+1.0] Aluminum can containing source displaces moderator, therefore causing competing effects.
Reference (s) A.05
- 1. Instruction Manual (IM) for the UCI TRIGA Reactor, p. 5-25a.
QUESTION A.06 A fissionable sample is to be irradiated. In which irradiation location would it have the greatest reactivity? Why? (1.5)
ANSWER A.06 It would be worth more if inserted into the central thimble because of the higher flux in the center of the core. [+1.5]
Reference (s) A.06
- 1. Instruction Manual (IM) for the vL'. TRIGA Reactor, p. 5-32.
-Section A Continued on Next Page-
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Page 5 Irvine Research Reactor April 8, 1986 Points Available OUESTION A.07 Define "1.5-folding time" as used in the reactor control rod reactivity worth calibration procedure. (1.0)
ANSWER A.07 1.5 folding time is the amount of time to increase neutron countrate by a factor of 1.5. [+1.0]
Reference (s) A.07
QUESTION A.08 Answer TRUE or FALSE.
It is expected that rotation of fuel elements in the core would NOT effect control rod worth. (0.5)
ANSWER A.08 FALSE [+0.5]
Reference (s) A.08
-Section A Continued on Next Page-
Page 6 Irvine Research Reactor April 8,1986 Points Available QUESTION A.09 The reactor is at a power level several orders of magnitude below the point of adding heat with a positive stable 10 second period established. If rods are inserted continuously until period becomes infinite, and then the rod insertion is immediately stopped, will the reactor be critical, supercritical, or subcritical? Explain. (The facility recommends adding
' momentarily' between the words 'becomes' and ' infinite'.) (2.0)
ANSWER A.09 The reactor will be supercritical. Because the reactor is
" prompt subcritical", the insertion of negative reactivity
' will cause prcmpt power to turn before causing delayed power to turn. The "subcritical effect" of the prompt neutrons is prevalent because prompt neutrons comprise about 99% of all
' neutrons in the reactor. [+2.0]
Reference (s) A.09
- 1. Instruction Manual (IM) for the UCI TRIGA Reactor, QUESTION A.10 Define shutdown margin. (1.6)
ANSWER A.10 i The mininium shutdown reactivity necessary to provide confidence that 1) the reactor can be made subcritical by means of the control and safety systems, starting from any permissible ,
operating conditions, and 2) the reactor will remain subcritical ;
without further operator action. [+1.6] :
Reference (s) A.10
- 1. W.S.U. TRIGA Technical Specifications.
-Section A Continued on Next Page-l l
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Page 7 Irvine Research Reactor April 8, 1986 Points '
~l Available B. FEATURES OF FACILITY DESIGN (13.5)
QUESTION B.01 What three (3) design features ensure that the reactor room, Ta56ratory, and counting room act as a confinement area for ;
contaminated air during normal operations? (1.5)
ANSWER B.01
- 1. All penetrations into this area are sealed. [+0.5] ,
- 2. The Loading Dock and Control Room doors have weather seals.
[+0.5]
- 3. The ventilation system is designed to maintain a negative air pressure in this area. [+0.5]
Reference (s) B.01 ,
- 1. Instruction Manual (IM) for the UCI TRIGA Reactor, p. 4-8.
QUESTION B.02 What type of material lines the reactor pit? (0.5)
ANSWER B.02 '
t Aluminum [+0.5]
1 Reference (s) B.02
- 1. Instruction Manual (IM) for the UCI TRIGA Reactor, p. 4-5.
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-Section B Continued on Next Page-s
Page 8 Irvine Research Reactor
< April 8, 1986 Points Available QUESTION B.03 What' design features provide for neutron reflection in the radial and the axial direction in your reactor? (2.0)
ANSWER B.03 The end sections of the fuel rods are made of graphite, this provides axial reflection. Radial reflection is provided by a graphite jacket enclosed in aluminum surrounding the core.
'[+2.0] .
- t Reference (s) B.03
- 1. Instruction Manual (IM) for the UCI TRIGA Reactor, p. 5-5.
QUESTION B.04 Into which general area of the core does the pneumatic transfer system deposit samples? (1.0)
ANSWER B.04 The outer ring of fuel elements, E or G ring. [+1.0]
Reference (s) B.04 q 1. Instruction Manual (IM) for the UCI TRIGA Reactor, p. 5-6.
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-Section B Continued on Next Page-
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Page 9 Irvine Research Reactor April 8, 1986 Points Available QUESTION B.05 Draw a basic schematic of the Pneumatic-Electro mechanical Trinsient Rod Drive showing the bottom limit, the air supply hose with the three-way valve, the ball nut, the worm gear, the piston, and the externally threaded cylinder with vent holes. (2.5)
ANSWER B.05 a.
""5"" a l
- assen an ant
.. - ,V - /
11;I ! il!i d ,,q n e N#
unsus GEAA/ l
_1 i-
~.'- _
a &=
Pt115. 00 s W
, L**
g omi.n m w.. mi . . e i, . w.m
[+2.5]
Reference (s) 8.05
- 1. Instruction Manual (IM) for the UCI TRIGA Reactor, p. 5-17.
-Section B Continued on Next Page-
Page 10 Irvine Research Reactor April 8, 1986 Points Available QUESTION B.06 What design feature ensures that control rods will not drop out of the bottom of the core? (1.0)
ANSWER B.06 A 1/2 in, aluminum safety plate is welded in place below the bottom grid plate. [+1.0]
Reference (s) B.06
- 1. Instruction Manual (IM) for the UCI TRIGA Reactor, p. 5-24.
QUESTION B.07 Answer TRUE or FALSE.
The purification system is particularly useful in removing mercury and copper metals. (0.5)
ANSWER B.07 FALSE. (These materials will not be removed, and therefore, special care must be taken not to introduce them). [+0.5]
Reference (s) B.07
- 1. Instruction Manual (IM) for the UCI TRIGA Reactor, p. 5-32b.
-Section B Continued on Next Page-(
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. Page 11 Irvine Research Reactor April 8,1986 Points Available QUESTION B.08 J
Wh oes d the fast transient rod have double the length of the poison section as compared with the other control rods? (1.5)
ANSWER B.08 So that initial acceleration on fast removal is achieved with no change in reactivity. [+1.5]
Reference (s) B.08
- 1. Instruction Manual (IM) for the UCI TRIGA Reactor, p. 5-5.
QUESTION B.09 What facility feature allows the monitoring of ground water beneath the Physical Sciences building? (1.0)
ANSWER B.09 Two deep pits have been dug and supplied with metered pumps.
[+1.0]
Reference (s) B.09
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-Section B Continued on Next Page-
-, ,. -, ,. =___ - - - , _ . . -- - - - - - .- -
Page 12 Irvine Research Reactor April 8,1986 Points Available QUESTION B.10 What design feature reduces the dose from N 16 produced in the cooling water for the neutron generator facility? (1.0)
ANSWER B.10 Concrete block shielding [+1.0]
Reference (s) B.10
- 1. Instruction Manual (IM) for the UCI TRIGA Reactor, p. 4-6.
QUESTION B.11 Because of the relatively high concentration of U238, what fissionable isotope is produced during reactor operation? (1.0)
ANSWER B.11 Pu-239 [+1.0]
Reference (s) B.11
-End of Section B-
Page 13 Irvine Research Reactor April 8,1986 Points Available C. GENERAL OPERATING CHARACTERISTICS (13.75)
QUESTION C.01 The TRIGA Mark I reactor is slightly undermoderated. This means that: (Selectone) (1.0)
(a.) pool depth is not sufficient enough to cause an increase in water density.
(b.) there is no reflector around the core.
(c.) a lowering of the water density will produce a negative reactivity response.
(d.) there are less hydrogen atoms than uranium atoms within the core.
ANSWER C.01 (c.) [+1.0]
Reference (s) C.01
- 1. Instruction Manual (IM) for the UCI TRIGA Reactor, p. 3-26.
-Section C Continued on Next Page-
Page 14 Irvine Research Reactor April 8, 1986 Points Available QUESTION C.02 The TRIGA reactor, when at or above the power level corresponding to the addition of sensible heat, is much more nearly linear than exponential in its response to reactivity changes. Why is this? (2.0)
ANSWER C.02 The long delay times for transfering heat to the core cooling water coupled with the large prompt negative temperature coefficient make it necessary to continuously add positive reactivity to increase the power. [+2.0]
Reference (s) C.02
- 1. Instruction Manual (IM) for the UCI TRIGA Reactor, p. 3-31.
QUESTION C.03 Answer TRUE or FALSE.
The bath coefficient in TRIGA has been found to be small but positive in the room temperature region. (0.5)
ANSWER C.03 TRUE [+0.5]
Reference (s) C.03
- 1. Instruction Manual (IM) for the UCI TRIGA Reactor, p. 3-32.
Section C Continued on Next Page-l-
- -. ~ w --- -
,, , --,-s- r e ---- -
- Page 15 Irvine Research Reactor April 8,1986 Points Available QUESTION C.04 l If a line supplying nitrogen to an experiment in the core were to break, causing bubble formation within the core lattice,
! the core reactivity would: (Selectone) (0.75) l
- (a.) increase (b.) decrease (c.) remain unchanged ANSWER C.04 (b.) [+0.75]
Reference (s) C.04
- 1. Instruction Manual (IM) for the UCI TRIGA Reactor, p. 3-32.
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-Section C Continued on Next Page- .
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l Page 16 Irvine Research Reactor April 8,1986 Points
- Available OUESTION C.05 If the pneumatic transfer tube were to flood, the reactivity of the core would: (Select one) (1.0)
(a.) increase by about 0.001% AK/K (b.) decrease by about 0.001% AK/K (c.) increase by about 0.1% AK/K (d.) decrease by about 0.1% AK/K ANSWER C.05 (c.) [+1.0]
Reference (s) C.05
- 1. Instruction Manual (IM) for the UCI TRIGA Reactor, p. 3-35.
QUESTION C.06 Answer TRUE or FALSE.
The equilibrium reactivity of Xe138 at 10 kW is approximately 50% of the reactivity associated with the equilibrium activity of Xetas at 1 MW (1000 kW). (0.5)
ANSWER C.06 FALSE (not even close) [40.5]
Reference (s) C.06
- 1. Instruction Manual (IM) for the UCI TRIGA Reactor, Figure 3.10, p. 3-37.
-Section C Continued on Next Page-
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Page 17 Irvine Research Reactor April 8,1986 Points Available QUESTION C.07 A pulse is only allowed from a power level below one (1) kilowatt. What is the parameter of concern regarding the need for this limitation? (1.0)
ANSWER C.07 Fuel temperature (the heat from a pulse is added to that already in the fuel before the pulse). [+1.0]
Reference (s) C.07
- 1. Instruction Manual (IM) for the UCI TRIGA Reactor, p. 3-39.
-Section C Continued on Next Page-
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Page 18 Irvine Research Reactor ApriI 8, 1986 Points Available J
QUESTION C.08 Which of the following best describes how the total energy released, and the peak power achieved, vary with the reactivity 1
inserted to cause a pulse? (Selectone). (1,0)
- (a.) total energy varies as the square of reactivity, peak power varies linearly with reactivity.
t (b.) total energy varies linearly with reactivity, peak power varies as the square of reactivity.
1 (c.) both total energy and peak power vary as the square of reactivity.
(d.) both total energy and peak power vary linearly with
- reactivity.
- ANSWER C.08 (b.) [+1.0]
Reference (s) C.08 :
- 1. Instruction Manual (IM) for the UCI TRIGA Reactor, p. 3-41.
QUESTION C.09 At what radial position within the fuel rod does the highest temperature occur during a pulse? (1.0)
ANSWER C.09 Near the outer edge of the fuel rod. [+1.0]
i Reference (s) C.09 :
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- 1. Instruction Manual (IM) for the UCI TRIGA Reactor, p. 3-54. l
-Section C Continued on Next Page-f
, _ - . . . . - _ . . ~ _ , . _ . _ . _ . . _ _ . _ - . _ _ _ _ . , _ . . _ _ , _ - _ . . . . . _ _ . . . . _ , . . _ _ . . . , , . . _ _ . . . _ _ . . . . . . _ . , _ . . _
. Page 19 Irvine Research Reactor April 8, 1986 Points Available QUESTION C.10 After a pulse, about how long will it take for fuel temperature to return to equilibrium with the surrounding pool water?
(Selectone). (1.0) i (a.) 0.1 second (b.) I second ,
(c.) 10 seconds (d.) 1 minute ANSWER C.10 (d.) [+1.0] (Facility points out that 5-8 minutes is closer totheobservedtime.)
- Reference (s) C.10
- 1. Instruction Manual (IM) for the UCI TRIGA Reactor, Figure 3.21, p. 3-54.
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-Section C Continued on Next Page-i
i Page 20 Irvine Research Reactor April 8,1986 Points
- Available QUESTION C.11 Why is it necessary to SCRAM the reactor following a pulse? (1.5)
ANSWER C.11 Because occur an uncontrolled following the pulse as addition of positive fuel temperature reactivity w[+ill1.5]
decreases.
Reference (s) C.11
- 1. Instruction Manual (IM) for the UCI TRIGA Reactor, Theory Section.
QUESTION C.12 The startup procedure directs that a calculation of core excess be conducted after allowing " sufficient time" at low power for stabilization. Why do you have to wait for stabilization? (1.5)
ANSWER C.12 Because it takes several minutes for delayed neutrons to come into equilibrium. This necessitates making small control rod adjustments to ensure that reactor power has been loaded. [+1.5]
Reference (s) C.12 .
-Section C Continued on Next Page-
Page 21 Irvine Research Reactor Apri1 8, 1986 Points Available QUESTION C.13 What is the maximum allowable core excess including experiments? (1.0)
ANSWER C.13
$3.00 [+1.0]
Reference (s) C.13
-End of Section C-L
Page 22 Irvine Research Reactor April 8, 1986 Points Available D. INSTRUMENTS AND CONTROLS (14.75)
QUESTION D.01 Where is the continuous air monitor that actuates the emergency purge system physically located? (1.0)
ANSWER D.01
. Adjacent to the reactor bridge. [+1.0]
Reference (s) 0.01
- 1. Instruction Manual (IM) for the UCI TRIGA Reactor, p. 4-13.
QUESTION D.02 Name the five (5) ranges of neutron countrate (power) indication and state what type of detector each is fed from. (2.5)
ANSWER D.02 i
- 1. source range (fission counter) - fission chamber j
- 2. log n recorder - compensated ion chamber
- 3. linear recorder - compensated ion chamber ;
- 4. percent power - uncompensated ion chamber
- 5. peak power - uncompensated ion chamber
[+0.5] each ,
Reference (s) D.02
- 1. Instruction Manual (IM) for the UCI TRIGA Reactor, p. 6-3.
-Section D Continued on Next Page-l
Page 23 Irvine Research Reactor April 8,1986 Points Available QUESTION D.03 Describe what condition will result in illumination of the following switches:
! a. DOWN switch (0.5)
- b. UP switch (0.5)
- c. CONT /0N switch (1.0)
ANSWER D.03
- a. control rod and drive are at lower limit [+0.5]
- b. control rod drive is at upper limit [+0.5]
- c. CONT side - contact between magnet and armature ON side - magnet power is energized [+1.0]
(Accept a description of rod and motor being in phase.)
Reference (s) D.03
- 1. Instruction Manual (IM) for the UCI TRIGA Reactor, p. 6-8.
QUESTION D.04 What happens to a withdrawn rod if its CONT /0N pushbutton is depressed? (1.0)
ANSWER D.04 It will fall into the core. [+1.0]
Reference (s) D.04
- 1. Instruction Manual (IM) for the UCI TRIGA Reactor, p. 6-8.
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-Section 0 Continued on Next Page-
Page 24 Irvine Research Reactor April 8, 1986 Points Available QUESTION D.05
. Answer TRUE or FALSE.
Pushing two (2) UP switches will result in the withdrawal of only one (1) of the two (2) rods. (0.5)
ANSWER D.05 l FALSE. [+0.5] (Neither reg nor control rod will withdraw when both are pushed.)
Reference (s) D.05
- 1. Instruction Manual (IM) for the UCI TRIGA Reactor, p. 6-9.
I OVESTION D.06 After depressing the ARM button and the FIRE button, how may the fast transient rod be inserted without affecting the position of the other rods? (1.0)
ANSWER D.06 By again pushing its ARM button. [+1.0]
l Reference (s) D.06
- 1. Instruction Manual (IM) for the UCI TRIGA Reactor, p. 6-14.
-Section D Continued on Next Page-
. Page 25 Irvine Research Reactor April 8,1986 Points Available QUESTION D.07 When fired out of the core, the adjustable transient rod takes as the. fast transient rod to insert its reactivity.
(a.) twice the time (b.) the same time (c.) half the time (d.) one quarter of the time ANSWER D.07 (a.) [+1.0]
Reference (s) D.07
- 1. Instruction Manual (IM) for the UCI TRIGA Reactor, p. 6-14.
QUESTION D.08 When in the pulse mode of operation, what indication does the log power recorder provide? (1.0)
ANSWER D.08 Fuel temperature. [+1.0]
Reference (s) 0.08
- 1. Instruction Manual (IM) for the UCI TRIGA Reactor, p. 6-16.
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-Section D Continued on Next Page-f i
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- Page 26 Irvine Research Reactor April 8, 1986 Points Available OUESTION D.09 Is the range of your period meter sufficient to allow observance of the constant negative period that occurs after a reactor scram? Explain. (1.5)
ANSWER D.09 Yet
-NS, [+0.5] the lower end of the period meter is -30 seconds.
The 'en;; :t.....i....
6,,,_i,s. 'P!:d del:y:d
.. . "^ ---- n:;tror,
" -- ' 'pre ;r:cra have a 55 :::cr.d -} STET-
[+1.0]
(bhN5076EE YdErhd? "0 REC PT" " ~
Reference (s) D.09
- 1. Instruction Manual (IM) for the UCI TRIGA Reactor, p. 6-17.
QUESTION D.10 Which of the following three (3) sources of information is NOT used by the comparator circuit in the servo amplifier while in automatic operation? (Selectone.) (0.75)
(a.) power demand from the power demand potentiometer (b.) reactor power information from the log power channel (c.) reactor period information from the period circuit ANSWER D.10 (b.) [+0.75]
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Reference (s) D.10 '
- 1. Instruction Manual (IM) for the UCI TRIGA Reactor, p. 6-17.
-Section D Continued on Next Page-
._ ~ . . - .- - - . - _ - . - , - . . . . . . _ .1
Page 27 Irvine Research Reactor April 8,1986 Points Available QUESTION D.11 List five (5) of the seven (7) interlocks associated with reactor control. (2.5)
ANSWER D.11
- 1. To ensure minimum source strength before control rods can be withdrawn.
- 2. To prevent withdrawal of two control rods simultaneously by manual control.
- 3. To ensure that pulsing cannot occur with reactor power greater than 1 kw.
- 4. To ensure that the range switch is on 250 kw range before initiating a pulse.
- 5. To prevent application of air to the fast transient rod in the steady-state mode unless all other rods are fully inserted.
- 6. To prevent application of air to the adjustable transient rod in the steady-state mode unless the cylinder is in the "down" position.
- 7. To prevent movement of any control rod except transient rods in pulsing mode.
Any five (5) [+0.5] each, +2.5 max.
Reference (s) D.11
- 1. Instruction Manual (IM) for the UCI TRIGA Reactor, p. 6-25.
-End of Section D-i
Page 28 Irvine Research Reactor April 8,1986 Points Available E. SAFETY AND EMERGENCY SYSTEMS (14.4)
QUESTION E.01 State the four (4) automatic actions that take place when the emergency purge system is actuated by the continuous air monitor. (2.0)
ANSWER E.01
- 1. The emergency exhaust fan starts, discharging through a filter. [+0.5]
- 2. Isolation dampers automatically close the air supply to the confinement area. [+0.5]
- 3. The non-emergency exhaust fans are switched off. [+0.5]
- 4. The pneumatic transfer system blower is switched off.
[+0.5]
Reference (s) E.01
- 1. Instruction Manual (IM) for the UCI TRIGA Reactor, p. 4-13.
4
?
i i
i i
-Section E Continued on Next Page- t i
k l
Page 29 Irvine Research Reactor April 8, 1986 Points Available QUESTION E.02 List all eight (8) signals, actions, ~or events that will cause
~
a SCRAM. (Setpoints not required.) (2.4)
ANSWER E.02
- 1. power level ... CIC
- 2. power level ... UIC
- 3. reactor period
- 4. manual
- 5. ion chamber power supply failure
- 6. console power failure
- 7. fuel temperature
- 8. seismic
[+0.3] each Reference (s) E.02
- 1. Instruction Manual (IM) for the UCI TRIGA Reactor, p. 6-25.
I i
-Section E Continued on Next Page-
Page 30 Irvine Research Reactor April 8, 1986 Points Available QUESTION E.03 What two (2) locations monitor the reactor pool water level alarm? (2.0)
ANSWER E.03 The facilit desk [+1.0]y central monitor [+1.0] and the UCI police dispatch Reference (s) E.03
QUESTION E.04
- a. Where are emergency protective clothing and decontamination apparatus stored? (1.0)
- b. Where are breathing apparatus and first aid equipment stored? (1.0)
ANSWER E.04
- a. Across the hall from the control room. [+1.0]
- b. Hallway outside the office door, [+1.0]
Reference (s) E.04
-Section E Continued on Next Page-l l
l l l
- 1 L_ _____.___.______________
Page 31 Irvine Research Reactor April 8,1986 Points Available QUESTION E.05 According to the Emergency Plan for the Reactor Emergency Organization, who is immediately above and immediately below the reactor operator in the information flow chain of of command? (2.0)
ANSWER E.05 Above - Senior Reactor Operator CSS [+1.0]
Below - Reactor Radiological Safety Staff [+1.0]
Reference (s) E.05
- 1. UCI Emergency Plan, p. 3-2.
QUESTION E.06 List +l" four (4) cate aries of Emergency Classification. (2.0)
ANSWER E.06
- 1. Unusual event [+0.5]
- 2. Alert [+0.5]
- 3. Site area emergency [+0.5]
- 4. General emergency [+0.5]
Reference (s) E.06
- 1. UCI Emergency Plan.
4
-Section E Continued on Next Page-
Page 32 Irvine Research Reactor April 8, 1986 Points Available i
QUESTION E.07 I Who should be contacted to implement an evacuation of the F5Fsical Sciences building should it become necessary? (1.0)
ANSWER E.07
- Campus Police Department [+1.0]
l Reference (s) E.07 '
i
QUESTION E.08 Where is the emergency shower located? (1.0)
ANSWER E.08 Outside of the control room near the emergency exit, outside reactor wall, and inside the rabbit room. [+1.0]
Reference (s) E.08 i
-End of Section E-t e
L 1
i h
1
. - - - - - - - - - . , , , , . - - , - - . , , , , . . . _ - , - - . . , , , . - , . - - . , , . - , , ,.------w., ,r-- - . - - - . v.w-. - , -, . ~ , ,- nw
)
l Page 33 Irvine Research Reactor April 8,1986 Points Available F. STANDARD AND EMERGENCY OPERATING PROCEDURES (14.5)
OVESTION F.01 For the Fast Transient Rod, only the rod worth is experimentally determined. (Selectone). (0.5) i (a.) Integral (b.) Differential ANSWER F.01 (a.) [+0.5]
~
Reference (s) F.01
QUESTION F.02 The shim and Reg rods have such a high total worth that the worth at the lower end cannot be measured. How is the total ,
worth estimated? (1.5)
ANSWER F.02 By doubling the integrated worth obtained for the exact halfway position on the rod. [+1.5]
Reference (s) F.02 i
l
-Section F Continued on Next Page- l
)
i I
s Page 34 Irvine Research Reactor April 8,1986 Points Available OUESTION F.03 The procedure for the installation and removal of reactor core components lists two (2) requirements for manual movement or complete removal of a control rod. State one (1) of these two (2) requirements. (1.0)
ANSWER F.03
- 1. The shutdown rods left in-core are worth at least TWICE the available core excess reactivity.
- 2. The reactor will remain shutdown if both the rods being worked on and the most reactive remaining rod were both removed by some accident.
Either of the above [+1.0].
Reference (s)'F.03
t OUESTION F.04 According to the SOPS, under what two (2) conditions should !
RED ink be used in the reactor log? (1.0)
ANSWER F.04
, 1. Entries pertaining to fuel changes. [+0.5]
, 2. Underlining changes affecting core reactivity. [+0.5]
Reference (s) F.04
t
-Section F Continued on Next Page-I
Page 35 Irvine Research Reactor April 8, 1986 Points Available OUESTION F.05 Give a short, one paragraph description of how a reactor power calibration is accomplished. (2.0)
T ANSWER F.05 Reactor power is established at a constant high level and the thermal power is calculated by conducting a heat balance on the reactor pool. Ion chamber heights areyadjusted to read ,
the calculated value. [+2.0] fo sa c u ec 4 a nl '
Reference (s) F.05
QUESTION F.06 According to the S0P for startup, core excess is calculated with the fast transient rod and the adjustable transient rod in what position? (0.5)
ANSWER F.06 Both up. [+0.5]
Reference (s) F.06
l
-Section F Continued on Next Page-
)
Page 36 Irvine Research Reactor April 8, 1986 Points Available QUESTION F.07 According to the SOPS, what are the staffing requirements for operating the UCI reactor? (1.5)
ANSWER F.07 A licensed operator must be at the panel. [+0.5]
A second individual present capable of initiating emergency action. [+0.5]
A senior operator must be present or immediately available within the Phy. Sci. building. [+0.5)
Reference (s) F.07
-Section F Continued on Next Page-T
-. -- - - - , , - ,- -y,,-- - e- r-- , , - , - ,
Page 37 Irvine Research Reactor April 8,1986 Points Available QUESTION F.08 Select from the items below the major concern regarding the irradiation of samples that are fissionable. (Selectone). (1.0)
(a.) Any amount of fissionable samples will insert > $1.00 of positive reactivity.
(b.) Irradiation of fissionable materials may cause production of I281 or Sr".
(c.) Fissionable materials are explosive.
(d.) Fissionable materials may overheat.
ANSWER F.08 (b.) [+1.0]
Reference (s) F.08
- 1. UCI TRIGA SOP, Section 2.4.1, p. 2-6.
QUESTION F.09 Why is core excess calculated at such a low power level during startup (SOP, Section 4.1.2)? (1.0)
ANSWER F.09 So that no reactivity effects caused by temperature change will interfer with the determination of core excess. [+1.0]
Reference (s) F.09
-Section F Continued on Next Page-l l ._
Page 38 Irvine Research Rer. tor April E,1986 Points Available OUESTION F.10 Answer TRUE or FALSE.
A reactor operator may leave the control console with the reactor at power, but only when in automatic control. (0.5)
ANSWER F.lf:
FALSE [+0.5]
Reference (s) F.10
QUESTION F.11 Under what condition is an Authorized User (Category B) permitted to enter the facility? (1.0)
ANSWER F.11 Only when the facility is in a NOT SECURED status. [+1.0]
Reference (s) F.11
t
-Section F Continued on Next Page-
Page 39 Irvine Research Reactor April 8,1986 Points Available OVESTION F.12 In the event that an unauthorized entry is attempted, threatened, the reactor operator is to perform (as or deemed possible,(4) time permits) four actions to " disable" the facility.
State three (3) of these four (4) actions. (1.5)
ANSWER F.12
- 1. SCRAM the Rx and remove the console keys.
- 2. Switch off all circuit breakers and relock the electrical box.
- 3. Remove all handling tools and keys from the facility.
- 4. Switch off the main facility breaker (closet in the Physical Sciences building requiring key).
Any three (3) [+0.5] each.
Reference (s) F.12
-Section F Continued on Next Page-l I
I
. . ~ . . . . , ,-
Page 40 Irvine Research Reactor April 8,1986 Points Available QUESTION F.13 In the event that the building fire alarm sounds, what three (3) actions should the operating staff take? (1.5)
ANSWER F.13
- 1. SCRAM the reactor. [+0.5]
- 2. Evacuate the building taking portable monitors. [+0.5]
- 3. Standby to assist emergency teams. [+0.5]
Reference (s) F.13
-End of Section F-k
Page 41 Irvine Research Reactor April 8,1986 Points Available G. RADIATION CONTROL AND SAFETY (14.0)
QUESTION G.01 To where is the air used by the send / receive station for the pneumatic sample transfer system exhausted? (1.0)
ANSWER G.01 It is exhausted into the main reactor room exhaust system.
[+1.0]
Reference (s) G.01
- 1. Instruction Manual (IM) for the UCI TRIGA Reactor, p. 4-8.
QUESTION G.02 Answer TRUE or FALSE.
During reactor operation for sustained periods at high powers, the loading dock doors should be opened to reduce N16 radiation exposure to operating staff. (0.5)
ANSWER G.02 FALSE [+0.5]
Reference (s) G.02
- 1. Instruction Manual (IM) for the UCI TRIGA Reactor, p. 4-6
-Section G Continued on Next Page-
Page 42 Irvine Research Reactor April 8,1986 Points Available OVESTION G.03 State three (3) of the five (5) locations of the area radiation monitors. (1.5)
ANSWER G.03
- 1. ceiling imediately over reactor core
- 2. ceiling over fuel storage pit area
- 3. east wall of reactor room below window to corridor
- 4. south wall of laboratory B54A
- 5. in pool, adjacent to Lazy-Susan unload tube Any three (3) [+0.5] each, +1.5 max.
Reference (s) G.03
- 1. Instruction Manual (IM) for the UCI TRIGA Reactor, p. 4-14.
-Section G Continued on Next Page-l
Page 43 Irvine Research Reactor April 8, 1986 Points Available OVESTION G.04 Identify the main storage facilities that are provided for the storage of radioactive fuel and/or irradiated materials. (1.5)
ANSWER G.04 There are five (5) storage pits located beneath the monorail transit and a lead shield called an " isotope" cave located on the west wall of the reactor room.
Satisfactory answer:
5 storage pits 1 isotope cave (OR.sTcRME RI\ CKS IN Pc0 L)
[+1.5]
Reference (s) G.04
- 1. Instruction Manual (IM) for the UCI TRIGA Reactor, p. 4-15.
QUESTION G.05 Why
_h is the tube used for loading the " Lazy-Susan" offset? (1.5)
ANSWER G.05 It is offset with large radius bends to avoid direct streaming of radiation from the core. [+1.5]
Reference (s) G.05
- 1. Instruction Manual (IM) for the UCI TRIGA Reactor, p. 5-26.
1
-Section G Continued on Next Page-
)
Page 44 Irvine Research Reactor April 8, 1986 Points Available QUESTION G.06 What is the purpose of the cadmium liner in one (1) of the Fast Trinsfer System (FTS) locations? (1.5)
ANSWER G.06 It excludes themal neutrons from reaching the sample. [+1.5]
Reference (s) G.06
- 1. Instruction Manual (IM) for the UCI TRIGA Reactor, p. 5-32a.
QUESTION G.07 Who must be present for handling fuel out of the pool, removal BTlarge experimental systems from the pool or any operation anticipated to have the potential for giving rise to appreciable radiation doses? (1.0)
ANSWER G.07 A qualified health physicist. [+1.0]
AND sEncR. RE Ac0R. cPERATOR.
Reference (s) G.07
-Section G Continued on Next Page-
. Page 45 Irvine Research Reactor April 8,1986 Points Available QUESTION G.08 When moving an irradiated fuel element, how much pool water (in feet) should remain between you and the element? (1.0)
ANSWER G.08
, Any answer greater than 4 feet is acceptable. [+1.0]
Reference (s) G.08
l QUESTION G.09 When a group of visitors not authorized under categories A-C are given a tour, how many dosimeters must be issued? (1.5)
ANSWER G.09 AT LE AS r 1 for every 5 people [+1.5]
Reference (s) G.09
-Section G Continued on Next Page-
Page 46 Irvine Research Reactor April 8,1986 Points Available QUESTION G.10 What is the highest reading that a Personnel Ionization Chamber TFIC)dosimetermayindicatewithoutneedingtoberecharged prior to issuance? (1.0)
ANSWER G.10 30 mr [+1.0]
Reference (s) G.10
QUESTION G.11 What does the acronym ALARA stand for? (1.0)
ANSWER G.11 As low as reasonably achievable. [+1.0]
Reference (s) G.11
-Section G Continued on Next Page-
. - - - . ., , ., , , . _ , . , . . . , - . , , , e -
Page 47 Irvine Research Reactor April 8, 1986 Points Available OVESTION G.12 According to the Reactor or Radiation Release Incident procedure, what two (2) actions should be taken to minimize the potential for environmental release if an airborne radioactivity release is suspected? (1.0)
ANSWER G.12
- 1. Tape over the cracks to doors to the reactor room with masking tape. [+0.5]
- 2. Ensure that the exhaust vents on the roof that are not part of the emergency exhaust system are closed off as far as possible. [+0.5]
/mM EVACUATE cR. TME AD D ITlOPJ AL AC.T 10tJS)
Reference (s) G.12
-End of Section G-
-End of Exam-
%I EQUATION SHEET Where mt = m2 (density)t(velocity)1(area)1 = (density)2(velocity)2(area)2 2
KE = mv 2
PE = mgh PEg + KE +PgV3 = PE +KE +P Y22 l 2 2 where V'= specific volume P = Pressure Q = mcp(Tout -Tin) Q = UA (T,y,-Tstm) Q = m(hi-h2 )
l P = Po10(SUR)(t) P = Po et /T SUR = 26.06 T = (B-p)t T p delta K = (K,ff-1) CR 1 (1-K,ffg) = CR2 (1-Eeff2) CR = S/(1-K,ff)
(1-K,ff1) (1-K,77) x 100x SDM =
M = (1_Keff2y K,ff 3 ____________________________________________________________________________
decay constant = (2) , 0.693 A1 = A0 e-(decay constant)x(t) 1/2 1/2 Water Parameters Miscellaneous Conversions 1 gallon = 8.345 lbs 1 Curie = 3.7 x 10 10 dps 1 gallon = 3.78 liters 1 kg = 2.21 lbs 1 ft 3= 7.48 gallons I hp = 2.54 x 103 Btu /hr 3 6 Density =62.4lbg/ft 1 MW = 3.41 x 10 Btu /hr l Density = 1 gm/cm 1 Btu = 778 ft-lbf l Heat of Vaporization = 970 Btu /lbm Degrees F = (1.8 x Degrees C) + 32 I Heat of Fusion = 144 Btu /lbm 1 inch = 2.54 centimeters l 1 Atm = 14.7 psia = 29.9 in Hg g = 32.174 ft-lbm/lbf-sec 2 4
. ,r--. . _ . , ,- - . , , - - - , , . , . . . , _ , . , , ,,_-..--,..,-,- . ..- -. - - . _.._. .,-, ,2- , , - , , , , , --,.,,[.,m... - . . . .
'?
7 U.S. NUCLEAR REGULATORY COMMISSION SENIOR REACTOR OPERATOR LICENSE EXAMINATION Facility: UC IRVINE Reactor Type: TRIGA Date Administered: APRIL 8, 1986 Examiner: P. MORRILL Candidate: CO R R EcTED K EY INSTRUCTIONS TO CANDIDATE Use separate paper for the answers. Writer answers on one side only. Staple question sheet on top of the answer sheets. Points for each question are indicated in parentheses after the question. The passing grade requires at least 70% in each category and a final grade of at least 70%. Examination papers will be picked up six (6) hours af ter the examination starts.
Category % of Applicant's % of Value Total Score Cat. Value Category i 20 20 H. Reactor Theory 20 20 I. Radioactive Materials Handling Disposal and Hazards ,
20 20 J. Specific Operating Characteristics 20 20 K. Fuel Handling and Core Parameters 20 20 L. Administrative Procedures, Conditions and Limitations 100 100 Totals Final Grade %
All work done on this exam is my own. I have neither given nor received aid.
l P
Candidate's Signature I
9
" EQUATION SHEET N f = ma v = s/t 2 Cycle efficiency = "*E "}
w = mg s = v,t + hat E = mC a = (vf - v 9)/t KE = mv v =v + at A = AN A=Ae g E o PE = mgh e = 0/t A = In 2/tg = 0.693/tg W = vaP ~
(to)(tu)
AE = 931am h (tg+t) b Ix Q = mCpaT 7 7 Q = UAAT 7 7 ,-UX Pwr = Wf $ I=I 10"*!
o P=P 10 SUR(t) TVL = 1.3/p P=P et /T HVL = 0.693/p o
SUR = 26.06/T T = 1.44 DT SCR = S/(1 - Keff)
SUR = 26
/A*fr )
o CR = S/(1 - K,ff )
g, T = (1*/p ) + 1( eff)1 =CR(1-K,ff)f 2
[(6 -=' p) / A p}
T = 1*/ (p - T) M = 1/(1 - K,gg) = CR /CR0 g
"( ~ 0)! eff P M = (1 - K,ff)0!II Keff)1
- " ( eff-1)/K,ff = AKdf /Keff SDM = (1 - K,fg)/K,ff
-5 p= [L*/TK,ff,] + [E/(1 + A,ffT )] t* = 1 x 10 seconds
-l P = I4V/(3 x 1010) A,ff = 0.1 seconds I = No Idgy =Id 22 WATER PARAMETERS Idg
=I0 22 1 gal. = 8.345 lbm R/hr = (0.5 CE)/d (meters)
I gal. = 3.78 liters R/hr = 6 CE/d (feet)
I ft = 7.48 gal. MISCELLANEOUS CONVERSIONS ,
10 Density = 62.4 lbm/ft 3 1 Curie = 3.7 x 10 dpc Density = 1 gm/cm 1 kg = 2.21 lbm Heat of vaporization = 970 Btu /lbm I hp = 2.54 x 10 3BTU /hr 6
Feat of fusion = 144 Btu /lbm 1 Mw = 3.41 x 10 Stu/hr 1 Atm = 14.7 psi = 29.9 in. Hg. 1 Btu = 778 f t-lbf I ft. H O2
= 0.4335 lbf/in 1 inch - 2.54 cm F = 9/5 C + 32-f C = 5/9 ( F - 32)
o CATEGORY H REACTOR THEORY H-1 (2.0)
Refer to Figure H-1 which shows an instantaneous positive at reactivity insertion into an already critical reactor core time T = 0. Af ter a stable period is reached an instantaneous removal of this positive reactivity occurs at time T = 1. areRespond not to the following questions, assuming source neutrons significant.
(1.0)
(a) Sketch the reactor power level as a function of time on Figure H-1 for these reactivity changes.
Sketch the resulting reactor period as a function (1.0)
(b) of time on Figure H-1 for these reactivity changes.
H-1 Answers (a & B) see attached drawing (1.0 each)
Reference:
Glasstone & Sesonski, Nuclear Reactor Engineering UCI Triga Instruction Manual, Section 3.2.5 1
9 e
g W*Cl > I .O i
lO I l I 60 77xg . +sl
- m. -
L k+
%; = .
b R
X m.
gy t-)
JL 3 7 D3 -
v 3
e tso t=1 7,g g F1 Cr. H-1 ;
Kn -
A Kew >l.0 I I
/.0 ho TIME - > d'l M-k oa v
M n.- '\
i ~ u wr j . is_ .- v..e
! I feri od. : N
[ too el / '
I/
% l/
p t-) I c
m,se W.! '
- N s_. &
,,e -
v v>n l e p / -
- 1) /
3 ?.
'h$r D? Sf a
3
. e t=o 7,g g t=1
. i -
- H-2 (3.0)
The reactor is shutdown with a count rate of 20 CPS on the count-rate channel. K(eff) has been determined to be 0.96. ,
is necessary to increase the count (1.0)
(a) What K(eff) rate to 80 CPS with the same source neutrons ?
(b) How much reactivity change would this require ? (1.0)
(c) How would you convert this reactivity to $s ? (1.0)
H-2 Answers (1.0)
(a) CR1(1 - Keff1) = CR2(1 - Keff2) 2O(1 - 0.96) = 80(1 - Keff2 Keff2 = 0.99 reactivity = (Keff - 1)/Keff (1.0)
(b) 0.04/O.96 = 0.042 0.01/O.99 = 0.010
-0.042 to -0.010 requires +0.032
$ 1.00 = delta K/K of 0.0070 and reactivity = (1.0)
(c) delta K/K so $ 1.00 = reactivity of 0.0070 OR r eacti vi ty / O. OO70 (bet a ) = $s.
OR O.032/O.0070 = $ 4.57
Reference:
UCI Triga Instruction Manual, sections 3.2.7 and 3.2.1 2
- H-3 (2.0)
Regarding a source of neutrons for the reactor core:
(a) Why is an installed neutron source needed to (1.0) conduct a reactor startup ?
UCI (1.0)
(b) What type of neutron source is used for the TRIGA reactor ?
H-3 Answers (a) The neutron source provides a sufficient number of (1.0) neutrons to give accurate instrument readings and therby permit controlled startups.
Americium-beryllium source (1.0)
(b)
B
Reference:
UCI TRIGA Instruction Manual , sections 3.2.7 and 5.4.4 3
- H-4 (3.0)
Significant time dependent reactivity effects occur in reactors as a result of the isotope xenon-135.
(a) What are the two sources of xenon in the UCI (1.0)
(b) What are the two ways xenon is removed from the (1.0) reactor while it is operating ?
(c) After shutdown from full power how long will it (1.0) take for xenon to peak (maximum negative reactivity) ?
H-4 Answers (a) From fission products and decay of iodine-135 (1.0)
(b) By radioactive decay and burnout of xenon-135 (1.0)
(c) 5 to 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> (1.0)
Reference:
UCI TRIGA Instruction Manual, Section 3.3.7 1
4
[
l 4
- H-5 (2.0)
Refer to Figure H-2 which graphs heat flux as a function of delta temperature. Label T between the fuel cladding and the coolant heat transfer the four regions shown according to the type of which is expected to occur.
H-5 Answer See attached drawing (2.0)
Reference:
UCI TRIGA Instruction Manual, Section 3.1.13 e
i 1
5 I . __. _ _ _ _
i l b 4 I l l is I l l j l i i I I I I i I i 3sTo's i 440A l l 1 l 1 l
go' - l l l
1 i I I
- l
- l l l
! l I I l id- l l l i i I
, I I l I I I I I I I
J I l I .
idce i
1600
- l'o g j AT between the cladding and the coolant 1
Fig. H-a. Variation of heat flux with surface liquid temp. differences.in a boiling system 4
4
V
- 5. ,.: g- f .; ":', . _
I SINGLE PHASE I
I H I m I g l Fit M 10 6
cow L~TIOM ( O . 5) l usm( blunc, g , c,)
'PARnAL_.
l ,c09uHG W I
g gyg I ( o. sj i co.s) 1 l l I wo's l I Qsr{0f) l l l
l l
'
- l lo' - .- l l
~.
l ,
! , l l l l l I I I
- I I I i io' - l l l 1 .
- I I l l 1 I l l l 1 1 l I j eS l l . !
I l'o g 10 0 1600 AT between the cladding and the coolant i
Fig. H-2. Variation of heat flux with surface liquid temp. differences.in a boiling system f { \/ .
+-w, -- .> .wa+ 9mge.- - - - . -.e g # p -.,., "
- H-6 (2.0) b (beta) denotes the total fracton of delayed The symbol neutrons.
the difference between delayed neutrons (1.0)
(a) What is and prompt neutrons 7 What is b(eff) (beta-effective) and how (larger (1.0)
(b) or smaller) is it different from b 7 H-6 Answers (a) Prompt neutrons are emitted at or during the (1.0) fission process, delayed neutrons are emitted by an excited nucleus (f ormed during beta-diintregation) an appreciable time after the fission.
(b) b(eff) denotes the effective delayed neutron (1.0) fracton and is larger than b since tbs agerage delayed neutron energy is lower than the prompt neutrons.
Reference:
UCI TRIGA Instruction Manual, Section 3.2.2 6
i
H-7 (3.0) with a large prompt The TRIGA reactors have been designed List the three principle negative fuel temperature coefficient.
effects used to achieve this and briefly explain how nach of these decreases reactivity when fuel temperature increases.
H-7 Answers Inhomogenities. Heating the hydrogen (1.0)
(1) Cell and the circonium hydride increases neutron in temperature. This increases leakage into the cold elements therby increasing water between fuel fuel Also the higher capture in the water.
temperature decreases the fission probability in the fuel.
fuel contains 80 % U-238. An (1.0)
(2) Doppler. I: e in fuel temperature causes capture increase resopnances of the U-238 +o doppler broaden therby decreasing resonance esca r e probability.
idea as the cell concept. (1.0)
(3) Core leakage. Same When the core heats up leakage increases and more captures occur outside the core in the reflector region.
Reference:
UCI TRIGA Instruction Manual, Section 3.3.3 7
. H-8 (1.0)
How will doubling the time a target nuclide is irradiated affect the resultant activity ? (doubl e , more than double, less than double) Briefly explain your answer.
d l H-8 Answer Less than double due to the radioactive decay of the radio-nuclide while the target is being irradiated.
Reference:
CAF i
1 4
8 e
(
l l
H-9 (2.0)
Indicate how the following parameters vary as a function of prompt excess reactivity inserted into the UCI TRIGA reactor. (as the square, directly, not at all, inversly, or explain other)
(0.5 each)
(a) Peak power (b) Energy release (c) Fuel can pressure (d) Initial reactor period H-9 Answers (0,5)
(a) Peak power, as the square (b) Energy release, linearly (0.5)
(0.5)
(_) Fuel can pressure, lineraly (d) Initial reactor period, inversly ~ (0. 5) ,
Reference:
UCI TRIGA Instruction Manual, Section 3.4.1 END OF SECTION H GO ON TO SECTION I 9 ,
l
{
6
' CATEGORY I RADIOACTIVE MATERIALS HANDLING, DISPOSAL AND HAZARDS I-1 (2.0)
Match the " qual,,ty i f actor" with the various radiation types.
RADIATION TYPES (0.5)
(a) Fast neutrons (0.5)
(b) Alpha Particles (0.5)
(c)( Beta Particles (0.5)
/ (d) Gamma rays QUALITY FACTORS
- 1. 1
- 2. 2
- 3. 10 1
- 4. -20 I-1 Answer (0.5 each)
- (a) Fast neutrons, 10 (b) ._ Alpha Particles, 20 (c) Beta Particles, 1
( d )' Gamma rays, 1 If candidate matches 1 per 1 partial credit may be given.
Reference:
UCI TRIGA Instruction Manual, Section 8.1.2 l
1 l
l I
l
- I-2 (3.0)
In accordance with 10 CFR 20 " Standards f or protection Against Radiation" (a) What three limits must be met to comply with (2.0)
Radiation Dose Standards for individuals in restricted areas per calandar quarter ?
What are the quarterly standards for minors (0.5)
(b)
(under 18) ?
What are the weekly standards for members of (0.5)
(c) the public ?
I-2 Answers skin 7.5, 18.75 (2.0)
(a) Whole body 1.25, hands / feet Rem /Otr 1/10 of the above limits (0.5)
(b) 100 Mrem in seven consecutive days (0.5)
(c)
Reference:
UCI TRIGA Instruction Manual, Section 8.2.1 10 CFR 20, 20.104, 20.101, 20.105 2
- I-3 (2.0) protection Against In accordance with 10 CFR 20 " Standards for '
Radiation" i RADIATION (1.0) l (a) Which areas must be marked " CAUTION, -
AREA" ? I (1.0) !
areas must be marked " CAUTION, HIGH (b) Which RADIATION AREA" ?
l I-3 Answer Areas accessable to personnel in which a major (1.0)
(a) radiation portion of the body could receive exceeding 5 Mrem in one hour or 100 Mrem in five consecutive days.
amajor (1.0)
(b) Areas accessable to personnel in which portion of the body could receive radiation exceeding 100 Mrem in one hour.
Reference:
10 CFR 20, 20.202 3
. I-4 (3.0)
Refer to Figure I-1 which shows a typical ionization curve, plotting the number of ion pairs collected per ionizing event versus voltage applied to the gas filled chamber. Name each of the indicated regions.
(a) Region I (0.5)
(b) Region II (0.5)
(c) Region III (0.5)
(d) Region IV (0.5)
(e) Region V (0.5)
(f) Region VI (0.5)
I-4 Answers (0.5 each)
(a) Recombination (b) Ionization (c) Proportional (d) Limited Proportional (e) Geiger - Mueller (f) Continuous discharge
Reference:
UCI TRIGA Instruction Manual, Section 7.2 l
F3. I .
I f 8 8
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Curve 2,: Radiation event of higher specific lonization. !
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e.--,,.--.---,-,----v-- ,-----,,---,-e,,- rn,,--, ,m e , - - , - --,r-- , - -
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. I-5 (3.0)
A radio-isotope is known to emit a single 2.0 Mev gamma ray for An unshielded sample of the material is each disintigration.
observed to cause a radiation level of 0.5 R/hr at a distance of one foot.
(a) How many curies of the radio-isotope are (1.0) present ?
(b) What would the radiation from the same sample (1.0) be at a distance of 4 feet 7 (c) What thickness of lead shielding will be (1.0) required to reduce the radiation level from the sample to 50 Mrem /hr at a distance of one foot 7 (Assume the 1/2 thickness for lead is 1/2 inch.)
I-5 Answers (a) R/hr at one foot =6x Ci xnx E (1.0) 0.5 = 6 x Ci x 1.0 x 2.0 Ci = 1/24 QtQ42 curies (b) D2 = Di(d1/d2)*2 (1.0)
D2 = 500 Mrem /hr (1/16)
Il Mtemfbt (c) I = Io x 2(exp-n(number of half thicknesses)) (1.0) 50/500 = 2(exp-n) 10 = 2(exp n) n = 3.32 3.32 x 1/2 = izZ Laches Ref erersce: UCI TRIGA Instruction Manual, Section B.2.4 I
t 5
P
- . .- . , . - + .m _, ,..,m_ , . - . + . , , _ . _ . - . _
- I-6 (3.0)
Complete the following table to match the kindradiation of detectordetection and the
- radiation normally detected with the proper (0.5 for each t instrument, as used at the UCI TRIGA facility. l-correct response) !
DEVICES TYPE OF DETECTOR RADIATION DETECTED j (A)
Universal Portable Monitor PUG-1A(Technical Associates I
(b)
Personnel Radiation Monitor PRM-2 " Chirper" (c)
Civil Defense Monitor 710-4(Jordan)
CHOICES l
TYPES: Proportional Counter, G-M Tube, Ion Chamber, Scintillation Counter, Thermoluminescent Device Beta, Gamma, Neutrons, Peta-Gamma, RADIATION CHOICES: Alpha, Alpha-Beta-Gamma, all --_ ------------------------_ __
1-6 Answers TYPE OF DETECTOR RADIATION DETECTED DEVICES (A) Alpha-Beta-Gamma Universal Portable Monitor G-M Tube (0.5) (0,5)
PUG-1A(Technical Associates (b)
G-M Tube Gamma Personnel Radiation Monitor (0.5) (0.5)
PRM-2 " Chirper" (c) Gamma Civil Defense Monitor Ion Chamber (0.5) (0.5) 710-4(Jordan)
Reference:
UCI TRIGA, Instruction Manual, Section 9.2 6
I-7 (2.0)
Which decay mode listed below is closest to that of:
[ note: select 1,2,3, or 4 for (a) and 1,2,3, or 4 f or (b)]
(1.0)
(a) Argon-41 (1) T(1/2) = 3.81 hr/ beta- decay /no gamma
= 1.83 hr/ beta- decay /1-2 Nev gamma (2) T(1/2)
(3) T (1/2) = 7.35 Sec/ beta + decay /6-8 Mev gamma (4) T(1/2) = 21.7 Min / beta + decay /no gamma (1.0)
(b) Nitrogen-16 (1) T(1/2) = 1.83 Hr/ alpha decay /no gamma (2) T(1/2) = 35.7 Sec/ beta- decay /1-2 Nev gamma (3) T(1/2) = 7.35 Sec/ beta- decay /6-8 Mev gamma (4) T(1/2) = 21.7 Min / beta + decay /no gamma J I-7 Answers (1.0)
(a) 2 (1.0)
(b) 3
Reference:
UCI TRIGA, Instruction Manual, Section 8.3.7 1
l I
I l
7
I-8 (2.0)
In core experiments constitute both a radiation and a contamination hazzard. What is the difference between radiation and contamination ?
I-8 Answer Radiation is the emanations (particles or rays) which are emitted by radioactive material. Contamination is the presence of radioactive material (usually as dust) where it is not desired.
Reference:
CAF END OF SECTION I GO ON TO SECTION J B
' CATEGORY J SPECIFIC OPERATING CHARACTERISTICS J-1 (4.0) the UCI For the control board power channels listed belowofat radiation TRIGA, complete the table by indicating the type (SCRAMS detector used and automatic reactor protection features and interlocks associated with each channel. (0.8 each)
CHANNEL DETECTOR & REACTOR PROTECTION FEATURE Count rate channel Linear power channel Log-n channel Period channel Percent power channel J-1 Answer (0.8 for each correct channel)
CHANNEL DETECTOR & REACTOR PROTECTION FEATURE Count rate channel fission counter, rod block if count rate too low (0.8)
Linear power channel compensated ion chamber, 110% SCRAM (0.8)
Log-n channel compensated ion chamber, <1 Kw interlock for pulsing operations (0.8)
Period channel compensated ion chamber (same as log-n), <3 Sec. period SCRAM (0.8)
Percent power channel uncompensated ion chamber, 110% SCRAM (0.8)
Reference:
UCI TRIGA, Instruction Manual, Scetions 6.2.4 through 6.2.8, and 6.3.2 1
J-2 (3.0)
Regarding " pulse" operation, briefly explain or describe:
power levels (0.5)
(a) Why are pulses initiated from low (below 1 Kw) ?
(1.0)
(b) What two indications are available to monitor fuel temperature ?
allowed (0.5)
(c) What is the maximum reactivity insertion during a pulse ?
How is pulse peak power sensed and where is peak (1.0)
(d) power displayed ?
J-2 Answers To avoid over heating the fuel. (0.5)
(a)
(b) The log power recorder in the pulse mode and the (1.0) water / fuel temperature meter.
(0.5)
(c) $ 3.00 uncompensated ion chamber feeds the linear (1.0)
(d) The power amplifier through the n-v circuit. The linear recorder displays the signal.
Reference:
UCI TRIGA, Instruction Manual, Sections 3.4, 6.2.11, 6.2.10 and Technical Specification 3.2 i
2
J-3 (3.0)
The reactor is in the " automatic" mode of operation attime. 100 watts.
State Consider each of the following situations one at a and how the what immediate indication the operator will see reactor servo-amplifier will respond.
(a) The negative voltage to the compensated ion (1.0) chamber is lost.
(1.0)
(b) The output signal from the compensated ion chamber is lost.
to a higher (1.0)
(c) The range switch is switched scale. (ie; from 100 to 250 w)
J-3 Answers will (1.0)
(a) Indicated power on the linear channel and the servo amplifier will insert the increase (Candidate may indicate that at regulating rod.
no effect will be seen, then no rod 100 watts motion will occur) will (1.0)
(b) Indicated power on the linear channel to zero and the serva-amplifier will decrease withdraw the regulating rod.
from full (1.0)
(c) The linear recorder trace decreases scale to less than half scale and the servo-amplifier withdraws the regulating rod.
Sections 6.2.9, 7.4.1,
Reference:
UCI TRIGA Instruction Manual, and 6.2.5 i
l l
l_-_ _____-__________-________
J-4 (3.0) pechbuttons The control rod drive system uses three illuminated for the shim and regulating rods.
the During a training start-up a student inadvertently presses been fully
" CONT /DN" switch of the shim rod after the rod has withdradwn. What indications (light and color & on/of "CDNT/DN" f) do youand pushbuttons expect what to see for the "DOWN", 'UP",
do these indications signify 7 (1.0 for each pushbutton)
J-4 Answer DOWN White, off, rod and rod drive not at lower limit (1.0) rod dri ve at top of travel (1.0)
UP Fad, on, CONT /ON Bl ue t< yell ow , "on" li ght on t< " CONT" light off, (1.0) l magnet energized but rod not attached
Reference:
UCI TRIGA Instruction Manual, Section 6.2.1 and Table 6.1 1
1 l
l l
4 l
l J-5 (2.0)
The UCI TRIGA f acility uses a continuous air monitor.
(0.5)
(a) Where is the CAM located ?
locating the (0.5)
(b) Why is this a better location than CAM in the exhaust duct ? .
by (0.5)
(c) What general automatic actions are initiated the CAM ? '
(0.5)
(d) What is the principal accident the CAM is intended to detect ?
J-5 Answers (0.5)
(a) Alongside the reactor.
(0.5)
(b) Tests show that detection is faster.
emergency purge system as well as (0.5)
(c) Actuate the the i sol ate inlets and shut off exhaust fans for reactor / counting / laboratory rooms.
(0.5)
(d) Leakage of fission products from a fuel element.
Reference:
UCI TRIGA Instruction Manual, Section 4.7.1 5
J-6 (2.0)
Regarding the UCI TRIGA area radiation monitors:
List the locations of four of the five area monitors. For each monitor listed, where are alarms and readouts provided 7 (0.5 for each monitor)
J-6 Answers (0.5 each for any four of the f ollowing)
(1) Ceiling over the Reactor core Central control (2) Ceiling over fuel storage pit Central Control (3) (East) wall of reactor room Central control and Local also window wall or corridor wall (4) (South) wall of laboratory Central control and local (5) In pool next to L-S unload tube Central control and local
Reference:
UCI TRIGA Instruction Manual, Section 4.7.2 6
i 1
i J-7 (1.0)
During normal operation the reactor core is cooled mostly by
_.__. (multiple choice, select the best answer listed below)
(a) Natural convection (b) Radiation (c) Natural conduction l (d) Forced convection J-7 Answer (1.0)
(a)
Reference:
UCI TRIGA Instruction Manual, page 5-6 bottom i
i 7
J-B (1.0)
How would the following mistakes or errors affect the calculated (calorimetric) 7 power for a reactor power calibration (calculated power too high, too low, or no effect)
(0.33)
(a) Secondary cooling water not completely turned off (0.33)
(b) The digital thermometer has a constant error of
+10 C (0.33)
(c) Measured pool depth lower than actual depth.
J-8 Answers (0.33)
(a) Calculated power too low (0.33)
(b) No effect (0.33)
(c) Calculated power too high
Reference:
UCI TRIGA Operation Manual, Section 4.3 l
8
J-9 (1.0)
High conductivity, with no level increase, in the UCI TRIGA pool could be caused by: (select the best answer)
(a) Operating at 250 Kw for more than 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> / week (b) An air leak f rom the f ast transf er system into the pool (c) Purification system flow decreased due to filter plugging (d) Heat exchanger leak J-9 Answer s
(1.0)
(c) or (d)
Reference:
UCI TRIGA Instruction Manual, page 5-34 and Operating Manual, page 4-7-9 i
END OF SECTION J GO ON TO SECTION K 9
i
u CATEGORY K FUEL HANDLING AND CORE PARAMETERS K-1 (1.0)
A maximum flux position is provided in the UCI TRIGA core at:
(select one of the following)
(a) The in-core terminus of the high speed pneumatic transfer system (b) The dry thimble at the center of the core (c) The lazy-susan device (d) The pneumatic-transfer (rabbit) system terminus .
i K-1 Answer (b)
(1.0) l
Reference:
UCI TRIGA Instruction Manual, page 5-6 1
e f
f 1
- K-2 (3.0)
The loading required for criticality is determined by observing the multiplication of source neutrons as fuel is added to the core. Using the data below answer the following questions.
NUMBER OF ELEMENTS COUNT RATE MULTIPLICATION 40 4000 2.0 50 8000 4.0 will be required for (1.0)
(a) How many elements criticality ?
many elements would you add for the next (1.0)
(b) How loading step (beyond 50 elements) ?
(1.0)
(c) With the reactor were subcritical and at a count rate of 20000 CPM, how would count rate be affected (increase , decrease, or stay the same) if the neutron source were removed. Briefly explain your answer.
l K-2 Answer (1.0)
(a) 10 to 11 (1.0)
(b) 4 would decrease because the neutron population (1.0)
(c) It is caused by subcritical multiplication. Without the neutron source there is nothing to multiply (count rate will decrease with a -80 Sec period)
Reference:
UC1 Instruction Manual, Section 3.5.2 2
l
K-3 (2.0)
Regarding the TRIGA core:
(a) What provides neutron reflection in the radial (1.0) direction 7 (b) In the vertical (top and bottom) direction 7 (1.0)
K-3 Answers (a) Graphite (in an aluminum can) in a ring around (1.0) the core.
(b) Fuel element graphite end sections. (1.0)
Reference:
UCI TRIGA Instruction Manual, Section 5.1 & 5.4.1 a
3 i
. K-4 (4.0) adjustable Draw a cross sectional sketch of the shim rod, the transient rod, a fuel element, and the non-adjustable transient Show the location of fuel, reflector, voids, and poison.
rod.
Approximate dimensions (+/- 20 %) should also be shown. (1.0 for each)
K-4 Answer See attached sketch Reference UCI TRIGA Instruction Manual,Section 5.3.1 4
K-9 AMSu) ER 5 ~$ 3lE h (o.O b
h (0 2)
N (o.O
) .
=
e N b N s (0 5)
(oJ) 1o N (0 Y)
D D N
- 4. E h b5 (o.4 "n (o5) D
% Q
\
(0.'f) &
N 1 e k 5
% (o.4)
O (o.1)
Fv&L /S + ll/L" a jg . (o.1) }
q Rob 5 Al2E V 1 %" On9. ( o . lea.)
A C L ADD /A) &- 0.030 s.s. F0/C FVGL E SHIM O ALUMwvM PcR ffR s SHIM ROD A bdosTA6L E FUE t. N OK)- A M OSTA8LE l TRANsisor (100 Eterneur renmaar R.co .
K-5 (2.0)
Regarding the structure of the TRIGA reactor cor e:
(a) What precludes the possibility of of a control rod (1.0) dropping out of the core ?
(b) How is the weight of the core (f uel elements) (1.0) transmitted to the bottom of the pt:01 7 K-5 An wer e (a) The safety plate under the core (1.0)
(b) The bottom grid plate supports the core. The grid (1.0) plate is welded to the reflector container support which rests on the pool bottom.
Reference:
UCI TRIGA Instruction Manual, Sections 5.4.1 t< 5. 4. 2 5
K-6 (1.0)
The void coefficient of reactivity for the UCI TRIGA ist (select one of the following)
(a) About -1 x 10-5 delta K/K/ 1%
(b) About -1 x 10-4 delta K/K/ 1%
(c) About +1 x 10-5 delta K/K/ 1%
(d) About +1 x 10-4 delta K/K/ 1%
K-6 Answer
! (b) (1.0) l l
Reference:
UCI TRIGA Instruction Manual, Section 3.3.5 1
1 I
.l j
s 4
l i
6
. , . . _ . , . . - ~ --- - - -.- -...-.._-.~.- __,, -- ----.-.-.-. - . . . - . . - - . - - - ,
K-7 (3.0) containers and experiments irradiated in the Regarding sample core:
using plastic sample (1.0)
(a) What is the advantage of containers ?
When must aluminum sample containers be used ? '( 1. 0)
(b)
(c) What four conditions require double encapsulation ? (1.0)
K-7 Answers activated by (1.0)
(a) The plastic container is not easily neutrons.
fissionable (1.0)
(b) Aluminum containers must be used when materials are irradiated or when significant heat will be generated in the sample.
Double encapsulation must be used for samples (1.0)
(c) which are corrosive, highly reactive with water or aluminum, potentially explosive, or liquid fissionable materials.
UCI TRIGA Instruction Manual, Section 8.3.3 and
Reference:
Operating Manual, Section 2.4.1 1
9 7
- K-8 (2.0)
Regarding core reactivity limitations contained in the Technical Specifications:
(a) What is the maximum total incore reactivity of an (1.0) individual experiment ?
(b) What is the minimum calci xenon free shut-down (1.0) margin with any single control rod fully withdrawn 7 K-8 Answers (a) $3.00 (1.0)
(b) $0.50 (1.0)
Reference:
Technical Specification 3.1 1 f f
8 j
. K-9 (1.0) in What is the worth (reactivity in $) of a single fuel element j the center of the core ? (select one of the following)
(a) $ 4 to 3 (b) $ 3 to 2 (c)
- 2 to 1 ,
(d) $ 1 to 0.50 K-9 Answer (c) (1.0)
Reference:
UCI TRIGA Instruction Manual, page 3-34 l
. /
v N V l
l 1
e 9
K-10 (1.0) follower control rode be When must fuel elements and fuel inspected 7 (two conditions)
K-10 Answer of less than 12 months and whenever 500 pulses At intervals (greater than $1.00) have occured. (1.0)
UCI TRIGA Operations Manual Technical Specification
Reference:
4.1 j
i 4
I s
W 9
END DF SECTION K
"' 00 DN TO SECTION L 10 y .
O CATEGORY L ADMINISTRATIVE PROCEDURES, CONDITIONS AND LIMITATIONS L-1 (4.0)
Regarding the Reactor Operations Committee (ROC):
What constitutes a quorum of the ROC 7 (1.0)
(a)
(b) Who are (by title) the permanent members of the (1.0)
ROC 7 four of the seven Technical (2.0)
(c) Briefly list Specification responsibilities of the ROC.
L-1 Answers At least a majority of the full committe including (1.0)
(a) the chairman or his designee constitute a quorum.
Reactor Administrator and Radiation Safety (1.0)
(b) The Officer are permanent members of the ROC.
(c) (0.5 each for any four of the following)
Review and approval of e>: peri ment s Review and approval of changes to the facility Determinations of unreviewed safety questions and changes to Technical Specifications Annual review of operations
- Review of abnormal performance Review of events reportable under 10 CFR 20 and 50 Approval of operators and supervisors for the reactor
Reference:
UCI TRIGA Operation Mahual, Section 3.5 Technical Specification 6.2 1
)
e L-2 (3.0)
According to Technical Specifications what three conditions must be met for the reactor to be considered secured 7 (1.0 each)
L-2 Answer (1.0)
(a) The reactor is shutdown actuating (1.0)
(b) Power to the control rod magnets and solenoids is of f , and the key is removed work is in progress involving fuel or in-core (1.0)
(c) No structure, e>:periments or maintenance of the core control rods, or control rod drive mechanisms
Reference:
J
O
~
L-3 (2.0)
There are Class I and Class II experiments at the UCI each Describe each class briefly and state who may approve
" class". (1.0 each)
L-3 "tried" experiments which are repeats of (1.0)
(a) Class I, successful experiments and those that are only a minor modification of a previous successful experiment (no additional hazzard involved) can be approved by the Reactor Supervisor.
" untried" experiments are all other (1.0)
(b) Class II, experiments which must be reviewed and approved by the ROC.
Reference:
UCI TRIGA Operations Manual, Section 2.1 3
e L-4 (2.5)
(a) Which facility personnel (by title) must review a (1.0) new experiment to determine whether it is Class I or Class II.
(1.5)
(b) State three of the four reasons an amendment would be required to an experiment.
L-4 Answer (1.0)
(a) The Reactor Supervisor and a radiological safety staff member must review the new experiment.
(b) (0.5 for any three of the following)
New personnel New procedures New types of materials to be irradiated original Quantities to be irradiated outside the limits
Reference:
UCI TRIGA Operations Manual, Section 2.3 4
.i
e 4
L-5 (1.0)
When a large group of visitors not authorized under categories A
- C are given a tour, how many dosimeters must be issued 7 L-5 Answer at least i for every 5 people (1.0)
Reference:
UCI TRIGA Operating Procedures, Section 4.9.3 9
I
. m._. _ .. _. . - , . . ,, ...
e L-6 (1.0)
According to the Operating Procedures, what are the three staffing requirements for operating the UCI TRIGA 7 L-6 Answer reactor is operated by, or under the direct (0.33)
(a) The supervision of a Licensed Operator. (Part (a) and (b) could be considered as one item for the SRO position.}
(b) A Senior Operator must be present or immediately (0.33) on call in the Physical Sciences Building.
(0.33)
(c) A second individual must be present in the facility capable of initiating emergency action.
Reference:
UCI TRIGA Operations Manual, Section 4.1.1
-9 6
L
e O
L-7 (3.0) are At the UCI TRIGA three categories of authorized users is established. List the three categories and state when each allowed access to the facility. (1.0 each category)
L-7 Answer (1.0)
(a) Fully Authorized User, can enter at any time.
can enter when the facility is (1.0)
(b) Authorized User, not Secured.
Authorized Visitor, can enter when the facility is (1.0)
(c) not Secured and for brief and specific times when it is Secured.
Reference:
UCI TRIGA Operation Manual, Section 4.9.1 l
7
o L-B (2.5)
While you are operating the UCI TRIGA a container of flammable liquid catches fire in the hallway adjacent to the control room.
(a) What are your three immediate actions 7 (1.5) what additional (1.0)
(b) If the fire is out of control two actions will you take ?
L-8 Answers evacuate non-operations (1.5)
(a) SCRAM the reactor, personnel, fight the fire.
the building fire alarm, and evacuate the (1.0)
(b) Sound facility.
Reference:
UCI TRIGA Operation Manual, Section 6.5.1.b 8
l l
o O
L-9 (1.0) levels of The UCI TRIGA Emergency plan lists five possible emergency classification. State the two emergency classification levels used at the UCI TRIGA and briefly explain why the others are not used.
L-9 Answers Unusual events and alerts are used. (0.5) routine Events less severe than unusual events are handled with alerts procedures, and events more severe than those requiring are not credible. (0.5)
Reference:
UCI TRIGA Emergency Plan, Chapter 4 1
I l
I END OF CATEGORY L END OF EXAMINATION I 9
1 3