ML20140A804
| ML20140A804 | |
| Person / Time | |
|---|---|
| Site: | Armed Forces Radiobiology Research Institute |
| Issue date: | 02/06/1986 |
| From: | Dudley N, Keller R, Kister H NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20140A796 | List: |
| References | |
| 50-170-86-01, 50-170-86-1, NUDOCS 8603210231 | |
| Download: ML20140A804 (37) | |
See also: IR 05000170/1986001
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U. S. NUCLEAR REGULATORY COMMISSION REGION I
OPERATOR LICENSING EXAMINATION REPORT
EXAMINATION REPORT NO. 86-01
FACI!ITY DOCKET NO. 50-170
FACILITY LICENSE NO.
LICENSEE: Defense Nuclear Agency
Bethesda, Maryland 20014
FACILITY: Armed Forces Radiobiology Research Institute
EXAMINATION DATES: January 7 and 8, 1986
CHIEF EXAMINER: /46 Ctp /~b Ib
N. Dudley, Lead R " tor Engineer Date
REVIEWED BY: If 2-[3[k
Rotiert M. Keller, Chief, Projects Section 1C Date
APPROVED BY: d
HarfyB.Kittyr, Chief, D6te I /
Projects Branch No. 1
SUMMARY: Examinations were administered to two Senior Reactor Operator Can-
didates and two licenses were issued. Problems were identified with house-
keeping and maintenance control for areas outside the reactor area.
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REPORT DETAILS
TYPE OF EXAMS: Replacement
EXAM RESULTS:
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l Written Examl 2/0 l
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l Oral Exam l 2/0 l
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l Overall l 2/0 l
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1. CHIEF EXAMINER AT SITE: N. Dudley, NRC
1. Summary of generic strengths or deficiencies noted on oral examinations:
Although candidates were knowledgeable' of reactor systems and operations
they did not display a strong working knowledge of the electrical distri-
bution system, the radiological waste disposal system, or the ventilation
system. Neither candidate was able to correctly determine whether the
discharge pressure of the supply fan to the reactor room was sufficient to
lift the building overpressure relief valve if the exhaust damper was
shut, and whether a release through the relief system would be unmoni-
tored. Neither candidate was able to locate up-to-date, as-built, draw-
ings to evaluate the consequences of the hypothesized malfunctions.
Candidates were unable to identify out of service equipment connected
with auxiliary and support systems not directly addressed by the Technt-
cal Specifications. Candidates stated that there is no management system
available to the operators to track out of service equipment which is not
directly under the cognizance of the operations department.
Housekeeping outside the reactor building is inadequate. In the Reactor
Control Area Room there was a hose which the operator was forced to step
on and over during completion of the startup check-list. There were
rusting cans and buckets on the floor, a fan belt hung from a valve stem,
and an overflowing trash barrel was in the middle of the room. In the
second floor ventilation room valve bodies and diaphragms were laying
loose on top of ventilation equipment.
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'2. . Personnel Present at Exit. Interview:
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NRC Personnel
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'N. Dudley
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-Facility Personnel
M. Moore,-React'or Facility Director
3. Summary of NRC Comments made at exit interview: i
A. discussion was. held concerning the details of facility operations to
clarify questions which. arose during the oral examinations. Also,'a
discussion of-facility comments on the written examination was conducted.
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The examiner ques'tioned why f!re extinguishers had been checked monthly
i until August of 1985 and.had not been checked for five months. The'Reac- ~!
. tor Facility Director explained that the fire department had lengthened
the surveillance periodicity on the fire extinguishers to six months.
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- . The examiner noted that housekeeping outside the reactor area was unsatis-
, factory. The. Reactor Facility ' Director agreed but sta.ted he had no con-
trol over the cleanliness of those areas since they had been turned over l
to contractors'for facility modifications.
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The examiner noted that there was an apparent' lack of management control
for facility maintenance and modifications. Indications of the lack of
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management. control included unavailability of.as-built prints and the lack
- of an out of service equipment' tracking system. .The Reactor Facility
[, . Director stated 'that the operations department-does not track "non-re-
. quired systems" because there is no requirements and that it is too dif-
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ficult to obtain information from the other. departments. He continued,-
that there is' no integrated control system at the facility to monitor and ;
track maintenance being conducted by each department.
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4. Unresolved Items:
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-The status of housekeeping outside the reactor area will be evaluated i
during future inspections. (50-170-86-01-01) F
The apparent lack of management controls for facility maintenance and i
modifications may. result in the inability to identify the effects of
planned maintenance on the safety of the reactor area. This is an
unresol'v ed item pending further discussions between the licensee and NRC
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Region I. (50-170/86-01-02)
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'5. Changes made to written exam during examination review:
Consideration was made of facility comments. However, not all comments
resulted in change to the answer key.
Answer No. Change Reason
K.6 Change to "2, 4, 3,1" In practice, calibration of
the transient rod is
performed after a full core
load.
K.10 Add " Presently one Statement of present plant
top and one center configuration is required
thermocouple are for full credit.
selected."
K.14 Add "for worth per rod; Allows answer for highest
D - most reactive ring". rod worth or highest ring
worth.
L.2 Add "4. Do not lock Corresponds to newly
reactor door". revised procedures.
L.7 Change "15 Watts" to Corresponds to newly
"above source level". revised procedures.
1. Written Examination and Answer Key (SRO)
2. Facility Comments on Written Examinations made af ter Exam Review
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U. S. NUCLEAR REGULATORY COMISSION
SENIOR REACTOR OPERATOR LICENSE EXAMINATION
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, Facility: AFRRI
Reactor Type:' TRIGA
Date Administered:
Examiner: ~ NOEL DUOLEY
Candidate:
INSTRUCTIONS TO CANDIDATE:
Use separate paper for the answers. Write 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. Examination papers will be picked up six (6) hours after the
examination starts. ~
Category % of Candidate's _ % of-
Value Total Score Cat. Value Category -m - - -
20 20 H.. Reactor Theory
20 20 I. Radioactive Materials
Handling,. Disposal, and
Hazards
20 20 J. Specific Operating
Characteristics
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20 20 K. Fuel Handling and
Core Parameters
20 20 L. Administrative Procedures,
Conditions, and-
Limitations
100 TOTALS
Final Grade %
All work done on this examination is my own; I have neither given nor received
. aid.
Candidate's8 gnature
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H.0 REACTOR THEORY'(20 POINTS)
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H.1 Assume the reactor is critical at I watt. . What effect, if any, ;
will be observed if the source is removed at this point?
Explain.
(1.5) j
H.2 Calculate how long it will take to increase the reactor period *
from 15 W to l' MW on a stable 5 second period. (1.5)
H.3 Estimate the shutdown margin of a fully loaded AFRRI core using
given data. (1.5) !
Rod worth
Trans $3.63 - -
Safe $1.88
Shim $1.90
Reg $1.87 _;
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Normal excess infinite H 2O = $4.25 i
H.4 Natural convection of the water in the reactor tank cools the
reactor core. Explain how natural convection takes place,
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including how a doubling of power would affect the flow past the
elements and the change in temperature between the bottom.and ,
top of the core. (3.0)
H.5 A K excess is measured on Honday morning (no weekend
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operations). The reactor is then operated at full power for 5
hrs, shut down, and K excess is measured 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> -later. ~ Would
you expect the K excess to be greater or less than that measured t
in the morning? WA? (2.0)
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H.6 Explain where the large negative temperature coefficient of
reactivity comes from, give all three (3) components, and
briefly describe each one. List in order of importance. (4.0)
H.7 The following statements are concerned with subcritical
multiplication. Choose the one underlined word that will make
the sentence correct. ,
a. As K ff approaches unity, a larger / smaller change in neutron
'aveiresultsfromagivenchangeinK eff. (0.5)
b. As K ff approaches unity, a shorter / longer period of time is
required to reach the equilibrium neutron level for a given
change in Keff. (0.5)
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- H.8 Answer the following True or False: d
a. A week after a reactor shutdown,- a Xe-135-free core is also
. an I-135-free core. (0.5)
b. . The equilibrium Xe-135 reactivity at 70% power is less than
twice the equilibrium Xe-135 reactivity-at 35% power. (0.5)
H.9 The reactor is shut down by 6% delta K/K with a source range
neutron count rate indication of 50 CPS. How much reactivity
will have to be added through rod withdrawal to raise the source
range count rate indication to 300 CPS 7 (2.0)
H.10 J oes
Wh d Xenon peak later following a shutdown from high power
than it does when.following a shutdown from a low power level?- (2.0) (
H.11 According to Fuch's Pulse Model Equations, which parameter given
.below is the pulse power proportional to: Select one.
a. The initial temperature T
b. Thesquarerootofreact10ityinserted
c. The reactivity inserted
d. The square of reactivity inserted
e. Beta-effective (0.5)
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I.0 0
RADI0 ACTIVE MATERIALS HANDLING DISPOSAL AND HAZARDS (20 POINTS)
1.1 If the reactor was operating at 1 MW and a fuel element
developed a~ crack in the cladding, how would the operator first
receive an indication of the failure? As the senior reactor
operator on duty, what would be your immediate actions upon
suspecting the cladding had failed? (3.0) .
I.2 You are the SRO on duty. -You learn that an experimenter has
made the following changes in his experiment ~ after it had been
approved for irradiation in the Core Experiment Tube. (CET).
1. He will use an aluminum rabbit instead of plastic.
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2. He will clean the experiment with acetone.(CH3)2C0 rather
than alcohol C 25 H 0H.
3. He will place the experiment in a gold-silver capsule with a
sodium chloride solution instead of a quartz ~ glass with a
distilled water solution.
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4. The run will be reduced from 1 MW hr to 55 min at 1 MW.
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a. Will you permit the experimenter to place this experiment in
the Core Experiment Tube (CET)? Briefly explain your
answer. (1.0)
b. For the changes 1-4 explain how and why each would affect
the radiological hazards associated with the experiment
(i.e., no significant change, or increase or decrease hazard
and reason for change). (3.0)
c. If the experiment as changed is eventually performed, what
precautions would you suggest for handling the rabbit after
exposure? (1.0)
1.3 Explain the operation of the N-16 Diffuser System and wA the
system is rarely used. (2.0)
I.4 True or False: The Remote Area Monitor (RAM) System consists of
detectors to measure neutron radiation levels in various areas
of the plant where radiation hazards may exist. (0.5)
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~ I.5 List the three (3) principal nuclides potentially present in the
gaseous effluent measured by the stack gas monitoring system.
Also state the primary source for each. (2.5)
I.6 Why are all six (6) surfaces of the exposure room lined with a
P oot thick wood lining? (2.0)
1.7 What prevents upward streaming of radiation from the Core
Experiment Tube (CET)? (1.0)
I.8 Two identical samples are irradiated in the same flux; one for
20 minutes, and the other for 10 minutes. What will determine
the ratio of activities .of the two samples T6TTowing
irradiation? Explain. (2.0) ,
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I.9 The radiation level in a planned maintenance work area is 150
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mrem /hr. Work in that area is expected to take three (3) people
. working 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> apiece. For each of the following options,
calculate the ex ected total man-rem exposure (including
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a. Temporary shielding is installed by two (2) worker d ho stay '
one hour in the 150 mrem /hr area, then the maintenance work
begins. A tenth thickness of shielding M installed. (1.0)
b. The radiation source is found to be a point source, where
the 150 mrem /hr is the exposure at four (4) feet. By using
extender tools, half the work is done at four (4) feet and
half the work is done at eight (8) feet. (1.0)
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J.0 SPECIFIC OPERATING CHARACTERISTICS (20 POINTS)
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J.1 Given the following rod configurations: safe-up, shim 60%,
reg-up, trans servoing at steady 800 KW - what changes, if any,
will occur if the shim rod up switch is depressed? If the safe
down switch is depressed? Explain. (2.0)
J.2 Explain the " isolation" capabilities of the air system in the
reactor room. (2.0)
J.3 List five (5) conditions that will cause a RWP (Rod Withdrawal
Permit) for one or all rods. (2.5)
J.4 What design feature minimizes the bottoming impact of a control
rod drive piston? ~
(1.0)
J.5 Explain the difference between Safety Channel 1 and Safety '
Channel 2. (1.5)
J.6 a. What is the range of the wide range log channel in the
nuclear instrumentation system? (1.0) ,
b. What two (2) techniques are used for covering the upper and
lower ranges? (1.0)
J.7 For the electrical loads listed below, indicate whether power
comes from Transformer 42A or 428.
a. Reactor Console
b. Cooling tower fan motors
c. Radiation Monitor Power Panel
d. Lighting. (2.0)
J.8 Briefly describe the differences in physical operation between
the regulating rod drive mechanism and that of the shim and
safety rod drives. (1.5)
J.9 Why is air pressure at 9 psi supplied to the shield door
bearings? (1.0)
J.10 On a loss of air pressure, what will happen to the supply
dampers (S1, S2, and S3) and to the exhaust damper (E1) located
in the heating and ventilating ducts of the Reactor Room? (1.0)
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J.11 What are the three (3) basic functions of'the water purification C
. system? (1.5)
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J.12 Two 1tems, frequently associated _with in-tank experimental
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devices, are mercury thermometers and dosimetry devices. Why is
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it important to ensure neither of these items are introducW
into the reactor coolant? (1.0)
J.13 What would happen if the rods failed to scram after a pulse?
Draw or describe'in detail the power response. (1.0)
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K.0 FUEL HANDLING AND CORE PARAMETERS (20 POINTS)
K.1 Briefly describe the procedure to be used in detemining a
steady state power coefficient. of re~ activity? (3.0)
K.2 True or False: In-core experimer.ts shall not be placed in
- adjacent fuel positions of the B-ring and/or C-ring. (0.5)
- K.3 a. What is the minimum number of nuclear instrument channels
! (with capability to detect' source neutrons) needed for fuel
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movement during core loading? (0,5)
b. During unloading? (0.5)
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! K4 a. In what order are the rings ~ loaded? (1.0)
b. How many elements are loaded per step until critical loading
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1s achieved? (0.5)
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K.5 What three (3) inspections and measurements must be conducted on
a new fuel element received at AFRRI prior to it being loaded
into the core?
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(1.5)
K.6 The following steps are taken ff6m' the AFRRI operating procedure
for reactor core loading. Rearrange in the order that they will
- be performed.
l 1. Calibrate the transient rod
j' 2. Load elements until critical loading is achieved
3. Load core to full operational load
l 4. Load core to $2.00 excess reactivity. (2.0)
K.7 How does the operator ensure that the fuel element is properly
l seated in the lower grid plate during the loading of F28 during
Core Experiment Tube (CET) removal from the core? (1.0)
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K.8 According to the AFRRI Reactor Core Loading and Unloading
Procedure (VII), who are the minimum personnel that must be
present for the core loading operation? (2.0)
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K.9 What is the purpose of the. graphite slugs at each end of the U
TueT-moderator rods? (1.0)
K.10 Which fuel temperature thermocouple readings are fed to fuel
safety ~ channels one and two? .(2.0)
K.11 What would happen if while operating at 1 MW the CET came loose
,
and popped out of the core? 37 W (2.0)
K.12 What is the maximum allowable K excess with a fully loaded
core? (0,5)
K.13 W
M is samarium included in each fuel element? (1.0)
K.14 Which fuel element ring has the. highest worth? (1.0) '
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L.0 ADMINISTRATIVE PROCEDURES, CONDITIONS AND LIMITATIONS (20 P0lNTS)
L.1 List five (5) items that require daily checks for operation by (2.5)
the Technical Specifications.
L.2 List three (3) things an operator must do upon hearing a fire (1.5)
alarm.
L.3 What conditions must be met for the reactor to be considered (3.5)
$ECURED?
L.4 Who is allowed unescorted access to the reactor Controlled (1,0)
Access Area (CAA)?
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L.5 What actions must an operator take on an AFRRI Complex Emergency
Evacuation according to Procedure VI (Emergency Procedures)? (2.0)
Include what actions are taken with reactor area doors.
L.6 Entries to the Reactor Operations Logbook are occasionally made
Give two (2) examples for each color '
in Red or Green colors.
(red, green) of an entries that might be designated by that (3.0)
color indication.
What is the maximum power limit for square wave operation? (0.5)
L.7 a.
b. What is the maximum power allowable before pulse (Mode III)
(1.0)
operation? What is the minimum power?
L.8 According to the AFRRI Emergency Plan, define _both Emergency (2.5)
Action levels (EAL's) and Emergency Classes?
L.9 What is the order of succession for.the Emergency Command Post (1.5) .
(ECP) Commander?
L.10 AccordingtoTechnicalSpectfications,whatarettEeminimum
number of fuel elements that are required in a closely packed
array to achieve criticality? Select one.
a. 12 elements
b. 33 elements
c. 67 elements (1.0)
d. 87 elements.
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EQUATION SHEET -
.____..._________________________________........__...______ ....... __....
. . +
l - Where mi = m2
(density)1(velocity)i(area)1 = (density)2(velocity)2(area)2
,
____.......____________________________.............____ ........._____ __
l ~ KE = mv2 PE = mgh PEi +KEi +Pi Yi = PE +KE where Y = specific
! - li 2 +P
2 Y22
volume
P = Pressure
.. ______...... _______...... __...______...__ ......._____..__....____ ..
( Q = ic p(Tou t-Tin) Q = UA (Tave-Tstm) Q = m(hi -h2 ) *
____________ .______.. _______________..______ ..__ ..........___..__..... _
,,
P = P e10(.SUR)(t) p p et/T SUR = 26.06 T = (B-p)t
I p
...__.u_. __.....___________.. ___.__..__._..___.......____.. .....____...
.- -
delta K = (Ke f f-1) CR1 (1-Keffi) =.CR 2 II-Keff2)
CR = S/(1-Keff) e r -
, M = (1-Keffi) SDM = (1.Keff) x 100%
!
(1-Keff2) K
eff
__...___ ......____..______._____...__......._......._______........ __...
l decay constant =
in (2) = 0.693 A 1 = Ag e-(decay constant)x(t)-
-, t t
1/2 1/2
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L Water Parameters Miscellaneous Conversions #
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l 1 gallon = 8.345 lbs 1 Curie = 3.7 x 1010 dps
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1 gallon = 3.78 liters 1 kg = 2.21 lbs
1 ft3 = 7.48 gallons 1 hp = 2.54 x 103Btu /hr
! 3
' Density =62.4lbg/ft 1 MW = 3.41 x 106 Btu /hr
Density = 1 gm/cm 1 Btu = 778 f t-lbf
Heat of Vaporization = 970 Dtu/lbm Degrees F = (1.8 x Degrees C) + 32
- Heat of Fusion = 144 Btu /lbm 1 inch = 2.54 centimeters -
1 Atm = 14.7' psia = 29.9 in Hg g = 32.174 f t-lbm/lbf-sec2
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U. S. NUCLEAR REGULATORY C0ftt!SS10N
SENIOR REACTOR OPERATOR LICENSE EXAMirMTI(N
4
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Facility: AFRRI
Reactor Type TRIGA
.
Da te Administered:
Examiner: NOEL DVDLEY
Candidates ANSWER KEY
- INSTRUCTIONS TO CANDIDATE:
Use separate paper for'the answers. Write 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. Examination papers will be picked up six (6) hours after the
examination starts.
Category % of Candidate's % of
Value Total Score Cat. Value Cateocry
20 20 H. Reactor Theory
20 20 1. Radioactive Materlaks .
Handling, Disposal,'and **
, . , Hazards
20 20 J. Specific Operating
Ch ar ac ter i st ics
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20 20 K. Fue1 Handling and
. . . , g Core Parameters
20 20 L. Administrative Procedures,
Conditions, and ,.
Limitations '
100 TOTALS
Final Grade %
All. work done on this examination is my own! I have neither given nor received
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Candidate's Signature
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H.0 REACTOR THEORY (20 POINTS)
H.1 If source is removed when critical at 1 W, a slight positive period will
result due to the source having a negative reactivity (about 5 cents)
worth at this power level (source absorbs more neutrons than
producing) .
Referenc2: AFRRI Question Bank A.16
H.2
P = Poet /T
10' .5 sec = 55.5 sec
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in . E
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Reference: AFRRI Question Bank A.14
w
H.3 Total rod worth $9.28
K excess -4.25
Shutdown $5.03
Reference: AFRRI Question Bank K.8
H.4 Natural convection is caused by the principle that as water is heated it
becomes lighter and rises causing flow past the elements - 1.5 pts. The
heat removed is equal to mCp (Tto -Tc .75 pts. Therefore, as
the power is doubled, the heat reSovedttTi-)l
w .be doubled.
^ (Ttop-T '
will nearly double and m will increase, but not quite double 73ps.
.b tt{m)
Reference: Basic Fluid Theory / Equation Sheet
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H.S K excess less (1 pt) due to:
1. heat up of core (because of increase in H O temp) .5 pts.
2. slight buildup of xenon .5 pts. 2
Reference: AFRRI Question Bank H.7
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-H.6 7tH disadvantage factor. The heatup of the zirconium hydride prevents a
neutrons from scattering down to reach thermal energy.
Doppler broadening. T apparent increase in wW of de resonance
capture integrals of. Ugg8causes the loss of neutrons thru resonance
capture.
Density. The thermal expansion causes a loss of moderator effectiveness
.thereby decreasing the neutrons reaching thermal energy.
I pt each description
1 pt order
t
Reference: AFRRI Question Bank J.9
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H.7 a. larger
b... longer -
Reference: Basic Reactor Theory
m.
H.8 a. True - - - -
b. True
Reference: Basic Reactor Theory
H.9 Given (delta K) = - 6%, Cf = 50 cps,'Cf = 300 cps
6.=
.943 / Assumption- (del ta K) = K-1
K = 1-(de ta K)- 1
C 1-K '
1 2* 50 * 1-K2 -
{*1-K
~
3
300 1 .943 /
1
50 057) , y,g *
- K,2 = .9905 -
2
'(delta K) = ~I =* ~
g- 5
= .00959 or about 1% S/D /
Reference: AFRRI Reference Package, p. 1
Formula Sheet-
. 6
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3
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H.10 Equilibrium todine is proportional to power, while equilibrium xenon is g
not.- Therefore, you have a higher ratio of.I to Xe at higher power
levels. The greater the I-to Xe ratio, the longer it takes for
sufficient .I to decay to Xe such that an equilibrium production and
decay of Xe is occurring (i.e., the peak).
Reference: Basic Reactor Theory
i
.H.11 d. The square of the reactivity inserted.
Reference: AFRRI Reference Package, p. 1
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I.0 RADIOACTIVE MATERIALS WV4DLING DISPOSAL AND HAZARDS (20 POINTS)
1.1 Reactor room CAM. Fission product gasses decay to particulate and
collect on the CAM filter. R1 would probably not alarm (unless levels
are greater than 500 mR/hr). Criticality monitor also would not alarm
(unless levels at room are greater than 10 mR/hr) -1pt.
Scram the reactor. Activate emergency plan. Isolate area. Insure CAM
alarm triggered close of dampers. Assess and evaluate situation - 2
pts.
Reference: AFRR1 Question Bank 1.8
I.2 a. No. It is not the same experiment. There will have to be a new
RUR.
b. 1. Significant change, Al will activate but short lived so not a
large problem if decay.is allowed.
'
2. No significant' change as both will evaporate but they are very'
similan chemically.
3. The capsule will be a very significant change as the gold and
silver will activate. Although the gold is practically opaque
to neutrons, if the solution is exposed to any flux at all, it
will activate. Gold wil1~ ac tivate wi th a high cross sect ion.
4. No significant change.-
c. Leave experiment in CET for short lived isotopes to decay off.
Af terwards use Time / Distance / Shielding when~ working wi th rabbi t.
Have a lead rask nearby as necessary.
t
Reference: AFRRI Question Bank I.5
, ta '
I.3 'The diffuser system is a pump mounted on the carriage above the reactor
~
tank. The piping of the diffuser system, located on the inside of the
core-support structure, passes pool water through an opening in the side
approximately 4 feet from the top of the support cylinder. The wa ter,
discharged inside the support structure in a tangential direction,
causes the water.above the core to swirl. This action breaks up the
vapor formations, thereby increasing bubble rise time and reducing the
radiation level at the top'of the reactor poei. This system-does not
reduce the levels by more than about 25% and it is therefore rarely
used.
1.5 pts - description of system
0.5 pts - why not used.
.
Reference: AFRR1 Hanual 82-1, p. 48
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I.4 False - measure gamma ,
Reference: AFRRI Manual 81-1, p. 111
I.5 AR-41 - Reactor
0 -15 LINAC.
N -13 LINAC
0.5 for each gas; 1/3 point for each source.
Reference: AFRRI Manual-82-1, p. 139
I.6 'It is there to prevent activation of the-12-foot thick concrete
biological shield by4hermalizing the fast neutrons and thereby reducing #
the secondary gamma ra91ation emitted from the concrete.-
.
Reference: AFRRI Manual 82-1, p. 157
I.7 The tube has a large "S" bend in it. ~
-
i
Reference:~ AFRRI Manual 82-1, p. 188
-I.8 Activity is proportional to lambda, the ' decay constant for the material.
1 = lambda.
A = Ag e-AE +~(flux)'N (cross section) (1-e' )
(,
If you double the time a material is irradiated, you will not double the
activation. Because it is a LN function. The' lower the lambda (higher
the half life), the closer you will come to. almost having a doubling. ,
~
Reference: AFRRI R'eference Package, p.1 '
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I.9 a. EXP = (2 men)x(150 mrem /hr)x(1 hr)
.+ (.1)x(3 men)x(5 hrs)x(150 mrem /hr)
. = 300 mrem + 225 mrem I
= 525 mrem ~or .525 Man-Rem
b. EXP = (3 men)x(2.5 hrs)x(150 mrem /hr)
+ (.25)x(3 men)x(2.5 hrs)x(150 mrem /hr)'
= 1125 mrem + 281.25 mrem
= 1406.25 mrem or 1.40625 Man-Rem ~
Reference ALARA and Shielding / Attenuation Basic Theory
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J.0 ~ SPECIFIC OPERATING CHARACTERISTICS (20 POINTS)
J.1 If shim up switch is depressed, no change will. occur (in square wave the
trans rod will servo, all other rods up, movement' is prevented).
If safe down is depressed, trans will servo out further to compensate
since downward movement is allowed.
Reference: AFRRI Question Bank-A.17
J.2 During any alarm from the primary reactor room CAM, the. positive sealing
dampers of the reactor air system will close. .The dampers can also be
closed manually. The doors and hatch to the reactor room are sealed
with gaskets to prevent air leakage from the reactor room.
Reference: AFRRI Question Bank B.21
J.3 . HV-loss on fission chamber
. fast period 3 sec
. pool water temp 50 C
.. source level (RWP unless operational channel sees source level
neutrons)
. IKW interlock - no air to trans rod
. operational calibrate - if operational channel is in any mode-except
operate. . .
Reference: AFRRI Manual 82-1, pp. - 92-23
AFRRI Question Bank J.18
J.4 The upper portion of.the barrel is well ventilated by slotted vents, so
the piston moves freely in this range. However, when the- piston is
within 2 inches of the bottom of its travel', its movement is restrained
Hby a dashpot action of the graded vents in the lower end of the barrel.
This action reduces the bottoming impact. ,
,
Reference: AFRRI Manual 82-1, p. 27
J.5 Safety channel two operates exactly like safety channel one in the -
steady-state modes. In pulse mode, however, the safety channel input is
changed so that a separate ion chamber or other detector is placed on
'
the. channel input. This channel reads the peak output on the console
recorder blue pen and the energy produced during the pulse on the NVT
meter in the right drawer, and supplies the scram signal based on a 110%
current signal from the detector.
' Reference: AFRRI Manual 82-1, p. 89
~
. ed
. ._ .. - ._ -. - - . - _ . . . _
- -
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cJ.6 a. 10~3 watt to 1 MW (ten decades)
~
b. The lower six decades uses a pulse log-count technique; the upper
four decades uses a log campbelling technique.
Reference: AFRRI Manual 82-1, p. 83
J.7 a. 42A
b. 428
c '. 428
d. 42A-
Reference: AFRRI Manual 82-1, p. 70 + 74
J.8 The regulating rod has a unique drive motor and drive control circuitry.
A. tachometer feedback drive motor moves the regulating rod. This system
interacts with the servo controller circuit in the control console. The
tachometer feedback drive motor is actuated by a variable signal from
the output of the servo controller. The tachometer in turn feeds back -
information on its rate and direction of travel to the servo controller
circuit.
Reference: AFRRI Manual 82-1, p. 28
J.9 To minimize the likelihood of water leaking into the housing if the seal
should rupture.
Reference: AFRRI Manual 82-1, p. 68
.
a
J.10 'The~ air dampers are spring-loaded with pneumatic solenoids. Air
pressure is required to hold them'open; when the air pressure is
removed, the dampers spring closed.
Reference: AFRRI Manual 82-1, p. 68
J.11 . It maintains. low electrical conductivity of the reactor coolant to
minimize the corrosion of all reactor components.
. It reduces radioactivity in the water by removing particulates and
soluble. impurities. ,
. It helps to maintain the optical clarity of the water.
Reference: AFRRI Manual 82-1, p. 41
, 6
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J.12 Both are highly' corrosive agents on the ~ aluminum tank and components
.(dosimeterscontainsalt).
Reference: AFRRI Question Bank, A.19
~J.13 The pulse'would terminate and convert to a steady state condition the .
'-
_ power of which would be detenmined by the amount inserted to cause the
pulse. For example, a $3.40 pulse would convert to 1 MW steady state
run after a few seconds.
Reference: AFRRI Question Bank, J.13
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K.0 FUEL HANDLING AND CORE PARAMETERS (20 POINTS)
K.1 The procedure to-determine a steady state power coefficient of
reactivity is as follows:
.
1. Bring the reactor to a cold critical condition.
2. Bring reactor- critical at desired higher power, measure' and record
the worth of control rod used to achieve this level or
2a. Using current control rod worth curves, insert a set amoun t of
reactivity (by withdrawing a rod to the appropriate ~ position).
3. Plot these values on a curve _ of power vs. reactivity in dollars.
Reference: AFRRI Exam Bank A.3
K.2' True
Reference: AFRRI SP 84-2, p. 27
K.3 a. 2
b. 1
Reference: AFRRI Operating Proced'sres VII, p. 1
.
K.4 a. B--------)5 ~~
!
b. '2 i
___.
_
Reference: AFRRI Operating Procedure VII, p. 2
K.5 o
1. ' visual defects (af ter cleaning)
2. length measurement
3. bow measurement.
..
Reference: AFRRI Operating Procedures, Procedure VII
K.6- 2, 4, 4 T-9-t
3,: 1
Reference: AFRRI Operating Procedures, Procedure VII
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K.7 There should be an audible " double click." -
d
Reference: AFRRI Operating' Procedure, TAB B-
~
K.8 ~ a' . The-Reactor Facility Director- or the Reactor Operations Supervisor,
b. One other licensed SRO or R0.
Reference: AFRRI Operating Procedure, VII
K.9- They are reflectors.
Reference: AFRRI Operations Manual, p. 20 i
K.10 Instrumented fuel elements, with three thermocouples each, are located
at selected positions in the B and C rings. Generally, the center
thermocouple (the one physically located in the center of the fuel
section), of the hottest reading element from one B ring and one C ring,
is' fed to fuel safety channels one and two, respectively. I'4f5fva r ur
icp t.vc car cwice rnewc:ett Mr Snczrto, ,
Reference: AFRRI Manual 82-1,,p. 89
K.11 Especially if experiment was in CET (usually neg) a pos insertion is
made. The position of the CET occupied is then replaced with water.
which is a reflector which is also positive worth. Therefore the power ' -*
would increase unless in servo whereby the reg rod would lower.
Reference: AFRRI Question ~ Bank, J.10
K.12 -$5.00 g 4
Reference: AFRRI Operating Procedures, VII
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K.13 As a burnable poison to minimize reactivity changes resulting'from
6
i
fission-product buildup and fuel burnup.
Reference: AFRRI Manual 82-1,'p. 20.
-
K.14 8 - all worths' decrea~se going from B to F. Fca weerre Nt /?ct,
D - Nsr Rentt<K Dn
Reference: AFRRI Reference Package. -Reactor Parameters
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L .'O ' ADMINISTRATIVE PROCEDURES. CONDITIONS AND LIMITATIONS (20 ' P01NTS)
d
L.1 1. Functional performance check of the transient rod system
~
2. Measurement of core excess reactivi ty
3. Check of-the scram function of the high-flux safety channels
4. Check of the fuel temperature scrams
5. Pool water. temperature measured at inlet to the purification system
6.. Channel check of RAMS and CANS.
Reference: AFRRI Question Bank L.14
L.2- 1. Scram the reactor (if operating)
. 2. Secure any exposure facilities open or in use
3. Remove the: log book, keys, AFRRI Fire and Emergency Evacuation
Information Guide. Carry _them to the Emergency Action Station and g
4,
prepare
Oc to M
gar L M support
AcTCAemergency
acch actions as required.
Reference: .AFRRI Question Bank L.18
--
% __.
L.3 a. The reactor is shut down - 1 pt.
m
b. The console key switch is in the "off" position, and the key is
removed from the console and is under the control'of a licensed
operator, or is stored in a locked storage area - 1 pt.
c. No work is in progress involving in-core fuel handling or refueling
operations, maintenance of the reactor or its control mechanisms, or
insertion or withdrawal of in-cor(' experiments, unless sufficient
fuel is removed to insure a $0.50 (or greater) shutdown margin with
the most reactive control rod removed - 1.5 pts.
Reference: AFRRI Question Bank L.1
AFRRI SP84-2, p. 3
9 &
L.4 Reactor staff'and any~other person who is designated on the Reactor
Access Roster.
'
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Reference: AFRRI Operating Procedure V
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, 14
L.5 1. Scram reactor. 4
2. Secure any. exposure facilities which are in use.
~
3.
\
Remove logbook, emergency guide and keys: 'and report to- EAS.
.
4. Do NOT lock reactor area doors.
Reference: AFRRI Operating Procedures VI
L.6 ' RED
.1. K-excess measurements, to include experiment worth determinations.
.i
2. Actions which affect reactivity:
a. Core movement.
b. Fuel movement.
--c Control r,od physical removal for maintenance.
'd. Experiment' loading and removal from the CET, PTS, Pool, or
Core. ,
GREEN
1. Reactor malfunction, to include the reactor systems and support
. equipment taken out of service for maintenance and returned to
service. .
2. Additional items entered at the discretion of the operator such as
addition of makeup water to the reactor pool, etc.
Reference: AFRRI Ope, rating Procedures, TAB A, p. 2,
o
L.7 a. ~900 KW
b. 1 KW / 15-Matts a cca . sc nc u s%
Reference: AFRRI Operating Procedure, TAB D (b). *
TAB E (a)
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, 15
L.8 Emergency Action ' Levels (EAL's). "EAL's" are specific. reactor-related i
instrument readings, or observations; radiological dose or dose. rates;
or specific contamination levels of airborne, waterborne, or
surface-deposited radioactive materials, which relate to the AFRRI
Reactor Facility, that are used as thresholds for establishing and
achieving emergency classes and initiating appropriate emergency.
measures or procedures under this Emergency Plan - 1 pt.
Emergency Classes. " Emergency classes" are generally accepted
classification labels for accident situations. grouped by severity level
for which predetermined emergency measures or procedures have been
addressed, considered, or provided .5 pts. The four emergency 'classes
are: (1) Notification of Unusual Event;.(2) Alert; '(3) Site Area
Emergency; and (4) General Emergency - 1 pt.
Reference: AFRRI Emergency Plan, p. 9 + 35
.
L.9 1. Director, AFRRI
2. Deputy Director, AFRRI
3. Senior Military Officer present in the AFRRI chain-of command.
s
Reference: AFRRI Emergency Plan, p. 22
s
L.10 c. 67 - other answers obviously wrong.
Reference: AFRRI Tech Specs, p. 28
, ..,_ -END of KEY-
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