ML20244B877
| ML20244B877 | |
| Person / Time | |
|---|---|
| Site: | Neely Research Reactor |
| Issue date: | 06/01/1989 |
| From: | Brockman K, Morgan M NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20244B873 | List: |
| References | |
| 50-160-OL-89-01, 50-160-OL-89-1, NUDOCS 8906140019 | |
| Download: ML20244B877 (129) | |
Text
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I prer UNITED STATES
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NUCLEAR REGULATORY COMMISSION p -
REGION 81 l
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101 MARIETTA STREET.N.W.
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ATLANT A, GEORGI A 30323
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i ENCLOSURE 1 EXAMINATION REPORT 160/0L-89-01 Facility Licensee:
Georgia Institute of Technology Neely Nuclear Research Center 900 Atlantic Drive, N. W.
Atlanta, Georgia 30332-0425 Facility Name:
Georgia Tech Research Reactor (GTRR)
Facility Docket No.:
50-160 Written examinations and operating tests were administered at the Neely Nuclear Research Center, Georgia Tech Research Reactor (GTRR), located within the Georgia Institute of Technology campus, Atlanta, Georgia.
Chief Examiner:
hlf. )4mbwn-i June 1969 s
Michael J. Morgan Date Signed Operator Licensing Section 1 Division of Reactor Safety 2_/ Anbsnd
/ 30% 1969 Approved By:
o Kph E. Brockman, Chief Date Signed Aperator Licensing Section 2 Division of Reactor Safety Summary:
Examinations were held on April 27 - 28, 1989.
Written examinations and operating tests were administered to three Reactor Operator (RO) candidates, all of whom passed.
L 8906340039 890601 7
PDR ADOCK 05000160, V
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REPORT DETAILS 1.
Facility Employees Contacted:
- R. A. Karam, Director - Neely Nuclear Research Center W. H. Downs, Senior Reactor Operator - GTRR L. D. McDowell, Senior Reactor Operator - GTRR
- Attended Exit Meeting 2.
Examiners:
- M. J. Morgan, License Examiner Division of Reactor Safety (DRS), Region 11 J. A. Arildsen, License Examiner, DRS, Region 11 D. C. Payne, License Examiner, DRS, Region II T. A. Peebles, Chief, Operations Branch, DRS, Region II C. W. Rapp, License Examiner. DRS, Region 11 R. D. Starkey, License Examiner, DRS, Region 11
- Chief Examiner 3.
Examination Review Meeting At the conclusion of' the written examination, the examiners provided R. A. Karam with a copy of the written examination and answer key for review.
The NRC resolutions to the facility comments (Enclosure 2) are listed below, a.
R0 Exam (1) Question A.08 NRC Resolution:
Comment not accepted.
The supposition that
" natural" sources of neutrons in a highly enriched core is not enough to start the reactor is contrary to information provided in the facility's nuclear theory training manual - Pacific Gas
& Electric Company; INTRODUCTION TO NUCLEAR POWER, Chapter 10, Pages 10-27 through 10-30; J. D. Shiffer, 1971.
Further, according to Professors Glasstone & Sesonske - NUCLEAR REACTOR ENGINEERING, Sections 5.257 through 5.264, Von Nostrand Publishing,1967 - the primary purpose for the use of installed sources is " base level" detection which, in turn, provides " safe" and " consistent" levels of "readily detectable" neutrons during any approach to criticality.
They also mention that the use of installed sources in Deuterium 0xide type reactors - for the purpose of starting the fission process - is unnecessary since D20 reactors readily retain high flux levels long after shutdown.
E-
2 (2). Question B.12 NRC Resolution:
Comment not accepted. The contention that the term " overflow return pumps" refers to ths. " main circulating pumps" MD1 and MD2 and that the SAR is " wrong and ambiguous" is not supported.
Figure 4.24 specifically identifies pumps MD3 and 4 as the " purification & reactor RETURN" pumps. It is logical to infer that pumps MD3 & MD4 are component parts of the "D20 j
OVERFLOW RETURN SYSTEM".
This " system" includes the overflow line and tank T-DI.
If one notes the relative placement of the
" overflow return system" to the purification system, it is apparent that the head developed by the " return pumps" (MD3 and MD4) does in fact provide a driving force for the purification system flow.
However, since this information was not specifically elicited by the question, it will not be required for full credit.,
(3) Question C.05 NRC Resolution:
Comment partially accepted.
The facility indicated that it is possible for the instruments to fail in such a way that the difference between the set point and the indicated position could be within the 10% deviation band. The system would not return to manual and the rods would move out.
The answer key has been modified to allow for this answer; however, the candidate must state that the above situation /
possibility exists as part of their answer in order to receive full credit.
(4) Question D.01 NRC Resolution:
Comment accepted. The answer key has been modified to allow for the sole response of " entry to the pipe tunnel via the process equipment room".
(5) Question E.03 NRC Resolution:
Comment partially accepted.
Answer key has been modified so that answer "c" is the correct answer and answer "a" is now incorrect.
Since current modes of GTRR operation are of " low" & " intermittent" levels AND since the facility SAR states system thermocouple should display "significant" temperature changes, it is recognized that answer "a" is, at best, speculative and thus, not necessarily " correct".
Answer "c" does, in fact, address ALARA and " common sense" radiation protection concerns, and therefore, would be the most correct answer to the question.
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'(6)-.QuestionF.06!
NRC Resolution:
Comment.not accepted. The contention that' E-Plan notification. requirements are not' among the duties of:the GTRR reactor operator (RO) is not. supported by procedural 7
requirements of GTRR Procedure 6100- (i.e.; that the Emergency Director is the only person who may " initiate" notifications).
The Code 'of. Federal Regulations, Part 55.45, states that an' operator. candidate should' be able to " demonstrate a. knowledge of the plant's E-Plan, including, an operator.'s responsibility to decide whether the plan should be executed and the operator's duties under the plan".
Apparently, NNRC/GTRR management' has recognized that events such as fires,' tornados, hot cell window leaks, etc.. could occur during " unattended' hours" and, in light of this, the following provision is noted in-Section 7.0 of the facility's plan - EMERGENCY PREPAREDNESS PLAN, Revision #11 (November 30, 1988):
"If an emergency. is detected at the NNRC during unattended hours, the. emergency organization will be activated by contacting 'the~ first available NNRC staff member' on the emergency notification roster."
This "first available NNRC staff member" may very well be a staff reactor operator and as such he/she will, by virtue of 1
being contacted, set the E-Plan notification process into motion.
b.
Review of the answer key by Commiss' ion examiner resulted in the ~
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following additional changes:
(1) Question B.03 The answer has been expanded to include "Provides set-up area for jobs to be performed in the hot cell area" as one of the recognized purposes of the facility's " isolation room".
(2) Question B.10 Point value of the question was reduced in order to be more consistent with " expected R0 knowledge" criteria.
i 4.-
Exit Meeting i
At the conclusion of the operating exams, the examiners met with GTRR/NNRC management to discuss overall results of the examination.
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4 The training material, specifically, Pacific Gas & Electric Company's INTRODUCTION TO NUCLEAR POWER, contains material which is misleading and/or inappropriate for Deuterium 0xide moderated reactor design.
It is suggested that the facility conduct a reevaluation of this material prior.
to presentation to future reactor operator candidates.
The facility's SAFETY ANALYSIS REPORT (SAR) for the 5 Mw Georgia Tech Research Reactor (December 1967) contains material which is misleading and inaccurate for present plant design / operation.
Throughout the preparation, pre-review and post-review phases of the examination, the examination team identified, SAR material which was incorrect and, many times, in direct conflict with information contained in present plant (i.e., 1974 and 1988/89) documentation.
These inconsistencies are due, in part, to modifications in plant design which have occurred since 1967 and changes in plant operating philosophy that has occurred since the original document was published.
It was recommended that a reevaluation and updating of this material be made as soon as possible.
Dr. Karam stated that plans are being formulated to change the SAR as soon as new fuel design changes are implemented.
He stated that such changes are scheduled to occur in approximately 1994.
The examination team suggests that such SAR changes be made prior to next exam.
The following generic weaknesses were noted during the oral examination and presented to GTRR/NNRC management:
a.
Only one operator / candidate demonstrated a " working knowledge" of the Emergency Generator's maintenance and operation, b.
Even though all candidates were able to perform required activities in a manner prescribed by the facility's procedures (e.g., reactor startup & shutdown) procedures were not open and "at hand" during these activities.
l The following industrial safety concerns were noted by the exam team and presented to GTRR/NNRC management:
a.
Propped open Fire Doors were found in the Emergency Generator and downstairs office areas.
Additionally, there was a broken door l
closure mechanism on the double door leading to the facility's
" Mechanical Equipment Room".
b.
High noise areas (e.g., in the " Process Equipment Room") were not identified as such & no signs highlighting " hearing protection required" were noted.
c.
No hearing protection devices were provided for staff personnel working in high noise areas.
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5 d
0ne Scott Air Pack unit was disassembled and would not have been immediately available if required for an actual emergency.
.e.
The tool room / shop equipment (e.g., grinders, lathes, drills and saws) should be checked to see if such equipment can be safely operated. Poor / unsafe electrical wiring and machine tool bracings (e.g., wedge & vise set-ups) were evident on many machines.
f.
Communications equipment has recently been updated to push-button
' phone stations; however, some areas formerly covered by phone stations no longer have phones.
Areas, such as the airlock leading
'to the containment structure, should have phone stations.
The following facility housekeeping concerns were noted by the exam team and presented to GTRR/NhRC management:
a.
A hydraulic oil drum in the Mechanical Equipment Area had oil spilled on the top and sides of the drum and caked oil / dirt was noted in the immediate vicinity of the drum.
b.
Old, and apparently, disused / obsolete equipment is evident throughout the plant.
Examples include old air filters and an obviously "no longer used" city gas meter.
It appears that such equipment is removed from a system and then placed in the nearest "out of the way" location, c.
The facility's tool room was not clean. Metal shavings / chips and cutting oil / coolant spills were widespread.
Cutting / calibration tools / attachments are scattered throughout the shop area.
d.
The Emergency Generator's batteries were not clean indicating a lack of proper maintenance.
Acid spills, fill cap damage, and questionable terminal contact / hookup were noted.
The cooperation given to the examiners and the effort to ensure an atmosphere in the control room conducive to oral examinations was noted and appreciated by the examination team.
The licensee did not identify as proprietary any of the material provided to or reviewed by the examiners.
(NRC-[0fficial'UseOnly.
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l Nuclear Regulatory Commission Operator Licensing Examination This document is removed from Official Use Only category on date of examination.
NRC Official Use Only
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l U. S.
NUCLEAR REGULATORY COMMISSION REACTOR OPERATOR LICENSE EXAMINATION GEORGIA INSTITUTE OF TECHNOLOGY
. FACILITY.
NEELY NUCLEAR RESEARCH CENTER REACTOR TYPE:
TEST - GEORGIA TECH RESEARCH REACTOR DATE ADMINISTERED:
89/04/27 INSTRUCTIONS TO CANDIDATE:
Use separate paper for the answers.
Write 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.
Examination papers will be picked up six (6) hours after the examination. starts.
% OF CATEGORY
% OF CANDIDATE'S CATEGORY VALUE TOTAL SCORE VALUE CATEGORY 16.00 15.31 A.
PRINCIPLES OF REACTOR OPERATION
[
13.88 B.
FEATURES OF FACILITY. DESIGN 15.00 14.35 C.
GENERAL OPERATING CHARACTERISTICS 14.50 13.88 D.
INSTRUMENTS AND CONTROLS
. J.A 13.40 E.
SAFETY AND EMERGENCY SYSTEMS 71.6 15.50 14.83 F.
STANDARD AND EMERGENCY OPERATING PROCEDURES 15.00 14.35 G.
RADIATION CONTROL AND SAFETY J04 TOTALS
/ 0 'L. 3 FINAL GRADE All work done on this examination is my own.
I have neither given nor received aid.
Candidate's Signature
NRC RULES AND GUIDELINES FOR LICENSE EXAMINATIONS Buring the' administration of this examination the following rules apply:
li. Cheating 1 on the examination means an automatic denial of your application and could resalt in more severe penalties.
L.
'Restroom trips are to be limited and only one candidate at a time may leave. 'You must avoid all contacts with anyone outside the examination room to avoid even the appearance or possibility of cheating.
D.
Use black ink or dark pencil only to facilitate legible reproductions.
L Print-your name in the blank provided on the cover sheet of the examination.
5.
Fill in the date.on the cover sheet of the examination (if necessary).
B.
Use only the paper provided for answers.
P.
Print your name in the upper right-hand corner of the first page of each section of the answer sheet.
B.
Consecutively number each answer sheet, write "End of Category __" as appropriate, start each category on a new page, write only on one side of the paper, and write "Last Page" on the last answer sheet.
D.
Number each answer as to category and number, for example, 1.4, 6.3.
LO. Skip at least three lines between each answer.
L1. Separate answer sheets from pad and place finished answer sheets face down on your desk or table.
L2. Use abbreviations only if they are commonly used in facility literature.
L3. The point value for each question is indicated in parentheses after the question and can be used as a guide for the depth of answer required.
L4. Show all calculations, methods, or assumptions used to obtain an answer to-mathematical problems whether indicated in the question or not.
LS-Partial credit may be given.
Therefore, ANSWER ALL PARTS OF THE QUESTION AND DO NOT LEAVE ANY ANSWER BLANK.
L6. If parts of the examination are not clear as to intent, ask questions of the examiner only.
l7. You must sign the statement on the cover sheet that indicates that the work is your own and you have not received or been given assistance in completing the examination.
This must be done after the examination has been completed.
[18. When.you. complete your examination, you shall:
a.
~ Assemble ~your examination as follows:
(1)
Exam questions on top.
(2)
Exam aids - figures, tables, etc.
(3)
Answer pages including figures.which are part of the answer.
~
b.
Turn in your copy of the examination and all pages used to answer the examination questions, c.
Turn in all scrap paper and the balance ~of the paper that you did not use for answering the questions'.
d.
Leave the examination area, as defined by the examiner.
If after leaving, you are found in this area while the examination is still in progress, your license may be denied or revoked.
n.
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PRINCIPLES'OF REACTOR OPERATION Page 4
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QUESTION A.01 (1.00)
]
Which one of the following correctly describes a reactor's state if I
I one dollars ($1.00) worth of positive reactivity is inserted into a-critical reactor?
1 a.
Supercritical' i
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b.
~ Prompt Critical l
1 c.
Prompt'Supercritical
-)
i d.
Critical i
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CATEGORY A CONTINUED ON NEXT PAGE *****-)
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PRINCIPLES O'F REACTOR OPERATION Page: 5 QUESTION A.02 (1.00)
Which on'e-of the following correctly describes the reason for the shape of the: attached 1/M plot?
a.
Detector too'close to source b.
Detector too far from source c.
Detector voltage is too low
-d.
Detector voltage is too high
(***** CATEGORY A CONTINUED ON NEXT PAGE *****)
QUESTION A.02 y
, - N 1
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O N
m 0
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4 4
4 Q
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LLJ E
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La o4 O
M La 10 00 2o 2.
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D.
A.
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" PRINCIPLES OF REACTOR OPERATION.
Page 6
j FLQUESTIONL A.03
-(1.00)
'Which.one of the following Critical' Heat Flux Ratios will:
" produce:the MAXIMUM heat. transfer?
j 1
a.
> 1.0
.j b.
< 1.0
- c..' 1. 0 l
d.
.- 0. 0 l..
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(***'**
CATEGORY A CONTINUED ON NEXT PAGE *****)
.Al PRINCIPLES OF REACTOR OPERATIOR Page-7
> QUESTION
~A.04 l(1.00)
(Which1one of the following is NOT a reason for loading excess fuel?
ai. Produce higher power levels
.b.
Overcome. fission product poisons c.
Compensate for fuel depletion d,
Overcome temperature effects as power is increased.
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CATEGORY A CONTINUED ON NEXT PAGE *****)
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Al PRINCIPLES OF REAfgDR OPER4XIDN
.Page 8
. UESTION A.05
'(1.00)
Q Which one of the following is NOT a characteristic of subcritical multiplication?
a.
.The suberitical neutron level is directly proportional to'the
-neutron source. strength, b.
Doabling the. indicated. count rate by reactivity addition will reduce the margin to shutdown by approximately one-half.
c.
For equal reactivity additions, it takes longer for the new equilibrium count rate to be reached as Keff approaches one, d.
An equivalent incremental amount of rod withdrawal will' produce an equivalent equilibrium count rate increase independent of the value of.Keff.
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CATEGORY A CONTINUED ON NEXT PAGE *****)
'A.
PRINCIPLES OF REACTOR OPERATlDN Page 9
QUESTION.
-A.06 (1.00).
Which one of the following is the correct amount of reactivity added if.Keff is increased from 0.861 to 0.965?
a.
0.086 b.
O.104i c.
0.125 d.
0.220 l
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CATEGORY A CONTINUED ON NEXT PAGE *****)
..A.
PRINCIPLES OF REACTOR OPERATION' Page 10 QUESTION A.07 (1.00)
Which one of the following is the reason for the -80 sec-period after
'a-reactor trip?
a.
This is equal to the decay constant of the longest-lived group of delayed neutrons.
I b.
The ability of U-235 to fission with source neutrons, c.
The amount of negative reactivity added on a trip ie greater than the shutdown margin.
d.
.The Doppler effect adding positive reactivity as fuel temperature decreases after a reactor trip.
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CATEGORY A CONTINUED ON NEXT PAGE *****)
A.
' PRINCIPLES OF REACTOR OPERATION Page 11
[.
QUESTION; 'A.08
'(1.00)
Which;one of the following is NOT a function of the installed OPERATING neutron ~ source?
a.
Provide an initial neutron population to start the fission
- process, b.
Provide reliable source of neutrons during an approach to critical.
c.
Provide-a visible indication to the operator that the neutron instrumentation is functioning properly, d.
Provide a means-for the operator to see changes in neutron flux as reactor conditions change.
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CATEGORY A CONTINUED ON NEXT PAGE *****)
-A.
~-PRINCIPLES'0F REACTOR OPERATION Page 12
._ QUESTION A.09 (1.00')'
Which one of the following is most affected by reactor size?
a.
LThermal Utilization Factor b '.
Fast Fission Factor c.
Resonance Escape Probability
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d.
Non-Leakage Probability 1
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LPRINCIPLES OF REACTOR OPERATION 1
4 4
Page~13 1
QUESTION.
A.10 (1.00)
~Which"one of the'following terms.is' defined as the energy equivalent of'the: mass defect?
- a '. ' Excitation energy b.
' Binding energy c'
Fission energy
'd.
Critical energy
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LA.
PRINCIPLES OF REACTOR OPERATION Page 14
- QUESTION
'A.11 (1.00)
Which one of the following correctly.describee the effect,of an
-OVERCOMPENSATED detector on indicated count rate?
a.; -HIGHER since more gammas are counted.
b.
HIGHER since more neutrons are counted.
c.
LOWER since less gammas are counted.
d.
' LOWER since less neutrons are counted.
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- A. -PRINCIPLES OF REACTOR OPERATXON Page 15 l
QUESTION A.12 (1.00)
Which one of the following correctly describes why D20 provides better moderation than H207 a.
D20 has a lower epithermal and thermal absorption cross-section than H20.
b.
D20 requires a shorter slowing down length than H20.
c.
Fission neutrons from D20 moderation are born at lower energies than fission neutrons from H2O moderation.
d.
The number of neutrons per fission from D20 moderation is higher than the number of neutrons per fission from H2O moderation.
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CATEGORY A CONTINUED ON NEXT PAGE *****)
- N.PRINCIPLESOFREACTOROPERATION Page 16 r
1[
QUNSTION
-A.13 (1.00)
-Which one of the following is most affected by fission product
-poisons?;-
'a.
Fast Fission Factor
'b..
Thermal Utilization Factor c.
Thermal Non-Leakage Probability d-Fast Non-Leakage Probability c.
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PRINCIPLES'OF REACTOR OPERATION Page 17 QUESTION A.14.
.(1.00)
Which one of.the.following factors.has the LEAST effect on rod worth?
a.
Number and' location of adjacent control rods b.
Temperature of the moderator c.
-Temperature of the fuel' d.
Core age 1
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1
-A.
PRINCIPLES OF BEACTOR OPERATION Page 18 1
LQUESTION
- A.15 -
(1.00)~
l Which.one of the.following correctly describes the behavior of Xe-135 L
if reactor power was increased from.an equilibrium 50% to 75%7 l:
a.
Initially increase then remain constant at a value greater than l
the 50% power value b.
Initially increase then decrease to a value equal to the 50%
power value.
l c.
Initially decrease then remain constant at a value lower than i.
the 50% power value.
d.
Initially decrease then increase to a value greater than the 50%
power value.
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l 1
A.
PRINCIPLES OF REACTOR OPERATION-Page 19 QUESTION-A.16 (1.00)
Which one of the following is the correct reason delayed neutrons allow control of the reactor?
a.
There are more delayed neutrons than prompt neutrons, b.
Delayed neutrons are born at higher energies than prompt neutrons and take longer to thermalize, c.
Delayed neutrons decrease the average neutron generation time.
d.
Delayed neutrons increase the average neutron generation time.
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END OF CATEGORY A *****)
L________________
L.
2BL : FEATURES OF FACILITY DESIQH
Page 20 l
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B.
FEATURES OF FACILITY DES 78di Page 21 QUESTION B.01
' ( 1. 00 ) '
Which one of the following is used to maintain the atmosphere above
.the moderator free of-water vapor?
a.
Nitrogen b.
Helium c.
Hydrogen d.
Argon l
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'B.
' FEATURES OF 'FACGJTY DESIGH Page-22 l
1 QUESTION B.02 (1.00)
Which one of the following is NOT used for shielding around the graphite reflector?
a.
Lead b.
Bismuth-c.
Steel.
d.
Boral-
{
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B.
FEATURES OF FACILITY DESIGN Page.23 i
. QUESTION B.03.
(1.50)
State three purposes of the isolation room immediately behind the larger hot cell.
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FEATURES OF FACILITY DESIGN Page 24 l
L. QUESTION B.04 (1.00)
. Which one of the following is the correct depth of the storage and handling pool?
as-25 feet b.
16 feet c.
18 feet d.
22 feet
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-Q
. B.
FEATURES OF FACILITY DESIGN Page 25-QUESTION B.05 (1.00) iState the design feature that assures the hot celle will be maintained
- at a minimum of 1/4 inch of water below room precsure.
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E'B; FEATURES OF FACILITY DESIGN Page 26 L
1 QUESTION B.06 (1.00)
Wh.ich one of the following liquid waste handling systems accepts all
. drain flow from the high bay area?
a.
Conventional-b.
, Suspect c.
Low level d.
D20 collection 1
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B.
FEATURES-OF FACILITY DESIGN Page 27' p
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' QUESTION'
-B.07 (1.00)
LState the purpose for each of the two volumes cast into the containment
- building basement floor.
1
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l B.
FEATURES OF FACILIU DESIGN Page 28' QUESTION.
B.08
'(2.00)
State the status for each of the following after a power failure.
1)
Safety-shim blades-2)
Stack outside air inlet damper 3)' Top D20 reflector
'4)
Emergency cooling valves I
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..-B.
FEATURES OF FACILITY DESIqd.
o Page 29 QUESTION-B.09 (1.00) a)- State the reactor safety signal that'will cause the reactor to scram during continuous regulating control rod withdrawal if the over-power and period trip circuits fail.
b)
State the mechanism that will terminate the power increase during continuous regulating control rod withdrawal if all scram signals fail.
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-Bi FEATURES OF'FACU,ITY DESIGN Page 30 QUESTION ~
B,10 (2.00)
State,four horizontal experimental facilities that are close to the fluel elements.
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B'.
FEATURES OF FACILfTY DESIGN Page 31
)
i QUESTION B.11 (1.00)
. State.the two fail-safe features of the biomedical facility if a power or equipment failure occurs.
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B'; ' FEATURES ' OF FACILITY ' DESIGN Page.32 QUESTION' B.12 (1.00)
-State the reason the D20 purification system is connected to the D20
. overflow return system.
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C.
GENERAL OPERATING CHARACTERISTICS Page 33 1
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'C.
GENERAL OPERATING CHARACTERISTICS Page 34 QUESTION
.C.01 (1 50)
Answer each of'the following regarding the daily radiation instrument response check conducted prior to reactor operation during daily checkouts.
-a)
What item / piece of equipment is used to perform this check?
b)
Where is this piece of equipment placed in order to perform the check?
c)
How long (time) is this piece of equipment used to validate the check?
d)
What indication should be seen in order to have a satisfactory check?
e);
On which equipment should this indication be observed?
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E C.
GENERAL OPERATING CHARACTERISTICS' Page 35 QUESTION.
C.02 (2.00) c Answer each of the following in regard to the Pneumatic Tube Transport System ~. Consider each independently.
' a)-
(During normal system operation, what amount of regulating rod movement to maintain criticality would require the reactor to be shutdown?
b)
Once the rabbit ~begins its automatic return to the selected station, and it.is heard passing through the rabbit room, what is the maximum time that may elapse, if the rabbit does not show up.
at the receiving station, before the receiving personnel should clear personnel from the cold equipment room?
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C.
GENERAL OPERATING CHARACTERISTICS Page 36
'LQUESTION-C 03 (1;00)
In-. regard to spent' fuel handling, select.the required minimum waiting
. period following a reactor. shutdown which must pass before any fuel element'is discharged from the reactor, a '.
18 hours2.083333e-4 days <br />0.005 hours <br />2.97619e-5 weeks <br />6.849e-6 months <br /> b.
12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> c.
24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />s-d.-
72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />
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C.~
GENERAL OPERATING CHARACTERISTICS Page 37
. QUESTION.
C.04
'(2.50)
'Two tests, Visual Inspection and Temperature Monitoring, are used to verify that Emergency Coolant Water is actually.being supplied to each fuel element when it would be required.
Briefly describe each of the above tests and include:
a)-
Its~ testing. frequency.
'b)
The specific instruments used for each test c)
The expected indication of proper flow 1
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'C.
' GENERAL OPERATING CHARAqIEFISTICS' Page 38
-QUESTION C,05 (3.00).
For each of the.following independent conditions in which the reactor
-hasLbeen operating in automatic control, state the response of the
. regulating rod (move in, move out, or not move), and provide the reason for the stated response.
a)
Reactor' operation is set at 2 MW two hours after a-cold startup.
b)-
Reactor operation'is set at 2 MW with equilibrium conditionc
, established when the instrument supplying the reference power to the automatic control system fails low.
c)
Reactor operation ie. set at 2 MW with equilibrium conditions established when a decrease in the H2O inlet temperature occurs for'the D20/H2O heat exchanger, l
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C.
GENERAI, OPERATING CHARACTERISTIfd Page139 r_
QUESTION-C.06 (1.00)
Indicate which one of the follow'ing statements concerning the small D20 circulating pump is most correct, a.
It must be run in parallel with the main D20 pump in order to increase power to 5 MW.
b.
It.is'used for reduced power operations in the event of the failure of the main D20 pump.
c.
It is to be used only below 50 KW to minimize pump heat added to the moderator.
i d.
.It is an emergency system, powered from an independent power supply, which allows forced flow during a loss of normal power.
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C.
GENERAL-OPERATING CHARACTERISTICS Page 40 l
l:-
l= QUESTION C.07-(2.00)
.a)-
State three indications in the. control room that a loss of substation B has occurred. (1.50) b ),
State the control room indication (if any) available for indication of a loss of substation A.
(0.50)
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P' C.
. GENERAL OPERATING CHARACTERTA'TYCS Page 41 l
I 1
.j QUESTION.
C.08 (1.00)
-l Indicate which one of the following best represents the MINIMUM
,. achievable recovery range for the Pneumatic Transport System's samples l
recovered at the containment building basement station?
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- a. 0.5.to 1 seconds i
b.
1 to 2 seconds c
20 to 30 ceconds
- d. 60 to 120 seconds l
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LC.
GENERAL-OPERATTNG CHARACTERISTICS Page-42.
1.
1'
-QUESTION:
C.09 (1.00)
State the minimum allowable reactor period during a no~rmal reactor
~
-startup.
Aesume there are no specially written and approved test l
. procedures in effect.
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.D.
INS E)MENTS AND CONTROLS Page :43
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D.
INSTRUMENTS AND CONTROLS Page 44 QUESTION D.01 (1.50.)
i Concerning access to'the pipe tunnel:
a)
State how entry is made into the pipe tunnel.
b) ' State the status of each of these accesses during reactor operation.
c)
State the indications available for determining access status.
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'.D.
INSTRUMENTS'AND CONTROLS Page 46 l
QUESTION D.02 (1.00)
Select'the most correct phrase to complete the following' statement.
The GTRR instrumentation and reactor safety circuit design provides operational safety-by. requiring the failure of circuit functions in order to block an automatic scram action.
- a. 2 or more
- b. 3 or more
- c. 4 or more
- d. 5 or.more
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D.
INSTRUMENTS AND CONTROLS Page 46 QUESTION D.03 (1.00)
Indicate the normal method by which the cooling tower's cooling
, capacity is varied to accommodate seasonal temperature changes.
- a. Use of the water bypass loop
- b. Use of-the air flow bypass butterfly valve
- c. Use of the standby circulating pump
- d. By changing of the speed (slow / fast) of the fan in each of the cooling tower sections l
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INSTRUMENTS AND' CONTROLS Page.47 QUEST 1ON D,04-(1.00)
.a)
State the speed of operation of the regulating (fine control) element.
-b)
State the maximum rate of reactivity addition obtainable with
.this rod (in % per second).
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- D':
INSTRUMENTS AND 90NTROLS-Page 48
- QUESTION D.05 (l'.00) i,
.. State the two signal sources for the ECCS alarm.
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D.
INSTRUMENTS AND COUROLS Page 49
- QUESTION D.06 (1.00)
. Indicate the statement that.best describee a major difference between
.a GM detector and an ion chamber, a.
The.GM detector has a photomultiplier tube to increase it's sensitivity, while an ion chamber does not, b.
The ion chamber operates at a much lower voltage resulting in a significant number of. ion pairs lost by recombination therefore decreasing it's sensitivity.
c.
The GM detector operates at a much higher voltage causing-
. gas multiplication to increase the charge collected to a value~ independent of the type of particle initiating it.
d.
The GM detector operates under a vacuum, and the ion chamber is pressurized.with a gas.
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-D.
INSTRUMENTS AND-CONTROLS.
Page 50 t
- )
L:
- . QUESTION
.D.07 (1.50)
L
~ What emergency ~ power sources are available and what do they supply?
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ID.'-INSTRUMENTS AND CONTROLS Page 51 i
QUESTION
'D.08 (2.50)
List the five different conditions (" parameters"):that will cause a
' DELAYED scram.
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D:
INSTRJ)MENTS AND ' CONTROLS -
Page.52.
QUESTION.
D.09 (3.00) i Match ONE primary sensing-element description to EACH of the GTRR safety interlock circuits listed below.
A particular primary. sensing
-element description may be used more than.once.
CIRCUIT DESIGNATION PRIMARY SENSING ELEMENT DESCRIPTION a) Power' Trip 1, Compensated Ion Chamber b)' Period Trip
- 2. BF3 Detector
.c)-Reflector Drain Valves
- 3. Uncompensated Ion Chamber Open
- 4. Mechanically operated switch
'd). Low Nitrogen Level
- 5. Pneumatically operated switch e) Containment Doors Open
- 6. Pneumatically and mechanically f) Control Air Low Pressure operated switches a) High H2O Temperature 7.
In-line thermocouple h) Low H2O Flow
- 8. Resistance thermometer
- 1) Low Shield Coolant Flow
- 9. Variable area type flow tube
'j) Low Nitrogen Flow
- 10. Venturi type flow tube l
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'D.
-INSTRUMENTS AND CONTROLS Page 53 QUESTION D.10 (1.00)
Which one of the following conditions is interlocked to prevent a reactor
.startup?
a.
Emergency Cooling Tank Low b.
Regulating Rod Low Limit c.-
Outside Automatic Controller Servo Range
.d.
D20 Leak-I t
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SAFETY AND EMERGENpY SYSTEMS-Page 54 1 :.
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i-E.
SAFETY AND EMERGENCY' SYSTEMS.
Page 55 l:
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QUESTION-E.01 (2.50)
During safety analysis of 5 MW operating conditions for the GTRR,
< conceivable situations leading to fuel plate burnout were analyzed.
.This study-led to the creation of five reactor safety signals which could detect / prevent plate burnout.
LIST these five safety signals (" monitored parameters").
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- E.
SAFETY AND EMERGENCY SYSTEMS Page 56
' QUESTION-
.E.02 (2.00)
. FILL.IN THE BLANKS For operationsat power levels greater than MW, GTRR's Emergency Cooling System is capable of providing GPM total flow to'the fuel elements for a period of at least minutes.
This total flow is equally divided / dispersed among fuel element positions."
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E'.
SAFETY AMD' EMERGENCY SYSTEME Page'57'
-QUESTZON)
E.03 (1.00)
.Which one of'the following practices IS NOT one of the accepte6
. methods of monitoring for proper Emergency Cooling System flow 7 I
- a.. Observation of a slight temperature difference - approxitiately 2 to 3 degrees - between coolant exit area thermocout,,les and ambient coolant. temperatures after system actuation.
- b. Flow from the system's distribution manifold to a fuel element's emergency. coolant port is observed through a borascope after system actuation,
'c.
Flow to each fuel element port is observed after removing the fuel element, looking directly into the open port and upon actuation of the system.
.d.
Flow to each fuel element port is observed after removing the fuel element, positioning an angled mirror over the open port and upon actuation of the system.
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E.
SAFETY AND' EMERGENCY SYSTEMS Page 58 i
QUESTION E.04 (1 50) d After. depressing the scram and shutdown pushbuttons - in order to-commence an emergency shutdown of the reactor - the operator is to check'that flux levels are decreasing AND - if these flux levels ARE NOT decreasing - the operator must open the " drain valves" and individually open the clutch magnet circuits.
In.what system are these " drain valves" found, AND how might flux levels be, lowered by the opening of these valves?
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E.'
SAFETY AND EMERGENCY SYSTEMS Page'59 l:
1.
QDESTION E.05 (1.00) l Concerning-the Gas Recombiner System, which1one of the following statements is TRUE7 a, High Deuterium Oxide dissociation rates ARE NOT expected, however, the Recombiner System is available as Deuterium
-concentration' levels near minimum explosive concentrations.
L b.-10-15 Cu ft/ min of blanket gas (Nitrogen)- which carries Deuterium & 0xygen - is withdrawn, heated, then passed over a catalyst bed as part of the recombination process.
- c. The chosen velocity-(~30 Cu ft/ min) of Nitrogen /D2/02 mix, passed over the' catalyst, virtually eliminates the amount of D2 gas returned - i.e.; ppm D2 gas is undetectable,
- d. If the Nitrogen gas flow rate is too high - i.e.; above the preset value - circuit interlocks, associated-with the Recombiner System, cause alarm / annunciator actuation.
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-SAFETY AND'EMERGEt4CY SYSTEMS' Page 60
/
.L-
[Q ESTION
'E.06 (2.00)
'How is.the-GTRR automatically protected from excessive internal pressurization caused by the formation of;eteam voids within the coolant channels of the fuel assemblies?
'HOTE:
In-your response, BRIEFLY DESCRIBE both the system and/or components involved and the basic mechanics of
' system / component operation.
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L E.
' SAFETY'AND EMERGENCY SYSTEMS
'Page161 l
QUESTION
.E.07 (1.00)
.'Concerning the-Reactor Ventilation System, which one of the following
- statements is TRUE7-
.The Reactor Ventilation System maintains a negative pressure on the ventilation connection at the reactor face, the biomedical facility ~
- and "most" of the reactor experimental openings.
This design:
- a. Allows for a " sweep ventilation flow" design which, in turn, aids in the cooling of the outer reactor vessel shroud by removal of higher temperature ambient air.
- b. Prevents buildup of radioactive gases, such as Argon-41, in air pockets around the reactor and experimental facility areas.
- c. Prevents contamination of the air by nonrepresentative sources l
of facility - incidental, "non-GTRR" produced radioisotopes. This further. enhances radiological monitoring of only "GTRR-produced" isotopes.
- d. Allows for an initial air flow of a higher " purity" and thus, as the air is sampled, a more representative sample is presented.
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'E ;
SAFETY ANQ_SMERGENCY SYSTEMS Page 62 i
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)
' QUESTION E.08 (1.00)
Concerning the Fuel Handling Transfer Coffin, which one of the following statements is TRUE7 i
The. transfer coffin:
-j
- a. Has at least'one foot of' lead (Pb) shielding positioned radial'ly about the " fuel-bearing" area of a spent fuel assembly.
This l
provides adequate' radiological protection.
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- b. Has a shielded cable external to the " grapple hook" end of the coffin.
This allows for attachment of a " chain fall" which, in turn, pulls fuel-upward into the coffin shroud.
- c. Has two shielded holes, each ~3/4 inches in diameter.
This allows for viewing of the " pulled" fuel assembly and for noting proper fuel " seating" within the coffin prior to coffin movement.
- d. Has an externally mounted, and " valved" drain port'
~1/2 inches in. diameter.
This allows for adequate Deuterium Oxide drainage prior to any coffin movement, i
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[E.
SAFETY'AND EMERGENCY SYSTEMS Page 63-N UESTION; E.09 (1.00)
Q
.Concerning:the Emergency Co'oling System & "Other" Additional-Long-term Sources ~of Core Cooling,-which one of the following statements le LTRUE7:
The Emergency Cooling System has been designed to provide:
- a. A "more-than-adequate" amount of time.to hookup to "other" water sources.
Therefore, the maximum credible accident at the GTRR, is a PARTIAL loss of coolant.
- b. An " adequate" amount of time to hookup to "other" water sources.
Therefore, the maximum' credible accident at the GTRR, is a COMPLETE loss of coolant.
- c. A "more-than-adequate" amount of time to hookup to "other" water sources.
HOWEVER, hookup may be prevented or interrupted; therefore, the maximum credible accident at the GTRR, is a PARTIAL core meltdown.
- d. An " adequate" amount of time to hookup to "other" water sources.
HOWEVER, this hookup may be prevented or interrupted; therefore, the maximum credible accident at the GTRR, is a COMPLETE core meltdown.
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.. STANDARD AND EMERGENCY' OPERATING PROCEDURES Page 64
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l F.
-STANDARD AND EMERGENCY OPERATING PRQCEDURES Page 65-t..
l-QUESTION' F.01 (2.50)
List the immediate operator actions for performing Code BAKER.
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1-E.
STANDARD AND' EMERGENCY OPERATING PROCEDURES Page 66 1
QUESTION F.02-(1. 0)
FILL;IN.THE BLANKS TO COMPLETE EACH OF THE FOLLOWING:
In accordance with GTRR Procedure 5000, after initiation of ECCS the
- operator must decide if Emergency Core Cooling is'neceosary.
a.
Under normal conditions of TD-2 "at overflow", TD-2 is designed to provide cooling for.approximately minutes.
This provides sufficient time to decide if emergency core cooling is actually needed-.
b.
Check reactor tank Deuterium Oxide level and if the level is LESS THAN inches install jumper hose.
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F.
STANDARD - AND EMERGENCY ~ OPERATING RROCEDURES Page 67
. QUESTION F.03 (1 00)
Which one of the following statemente is TRUE7 IfLat anytime during reactor operation a condition or event occurs.which, in the opinion of the reactor operator, is not thoroughly understood or explained,.the. operator will:
a.
Immediately contact a Senior-Reactor Operator.
b.
Immediately notify reactor supervision and Health Physics.
c.
Immediately commence a shutdown of the reactor, d.
Immediately notify a member of HNRC management.
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STANDARD AND EMERGENCY OPERATING-PROCEDURES Page 68 QUESTION F.04
-(1.00) 1 Which one of theJfo11owing statements is TRUE7 During the removal of an irradiated fuel element, the element,
- due to a' mechanical failure of the transfer coffin, falls out L of the coffin onto the containment building floor.
In accordance with GTRR/NNRC rules / guidelines, the operator (s)
. conducting the fuel handling operations, should now:
a.
Immediately run away from the exposed fuel element.
Immediately evacuate the containment area & request others to do the same.
Promptly notify NNRC management.
- b. Immediately proceed to an area within containment which L
affords the greatest amount of shielding.
Immediately request l
othere in the area to do the same.
Promptly notify NNRC management,
- c. Immediately lie down if atop the reactor (this will afford the greatest amount of shielding).
Attempt to retrieve the element (minimize exposure time).
Move the element to an area which would provide sufficient shielding.
Promptly notify NNRC management.
- d. Immediately cover at least the active fuel portion of the assembly with blanketing,. blocks, etc...
Immediately evacuate
.the containment area & request others to do the same.
Promptly notify senior NNRC management personnel.
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L F.
STANDARD AND EMERGENCY OPERATJNG PROCEDURES Page 69 l'
QUESTION F.05 (1.00)'
Which one of the following statements is TEUE?
During reactor operations, at ~10:00 AM, a large fire is noted in the containment building.
As the reactor operator you l
conduct a code ABLE, turn "off" all switches to pumps / control drives, leave the scene of the-fire and isolate containment.
Once others have-been notified of this fire, the proper response of NNRC personnel is to:
a.
Immediately evacuate the NNRC.
A minimum _of six (6) NNRC personnel will re-enter the building and-proceed to make a general survey of the building.
- b. Immediately evacuate the NNRC.
The ED, and only the ED, shall attempt to re-enter the building and make a determination about the best way to recovery, c.
Immediately evacuate the NNRC.
The ED & TWO (2) "other" personnel will re-enter the building, then go to the Emergency Command Center (ECC) and proceed to make a general survey of the building.
d.
Immediately evacuate the NNRC.
ONE (1) HP and the Hot-Cell operator will re-enter the building and go to the ECC.
They will proceed to make a specific survey of containment.
Once survey is complete the ED shall note recovery options.
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1 F:
STANDARD AND EMERGENCY OPERATING PROCEDURES Page 70
' QUESTION F.06 (2.50)-
LFor each of~the events' listed in the left-hand column, select and list l
the appropriate actions from those given in the right-hand column:
l EXAMPLE:
" Explosion which is Non-specific to l
the-Reactor or Its Control Systems"
- 1. Call GA Tech Police (GTP) after assessment
- 2. Call Fire Department if needed EVENTS ACTIONS a) "An-individual is found to be
- Call GT Police contaminated" after assessment (AA) 1.
- Call GT Police if needed (IN)
.b) "NNRC has received a bomb threat -
- Call GT Police immediately (I) with possible radiological release implications (during off-hours)"
- Call for Fire Assistance-(AA) l 1.
- Call for Fire Assistance (IN) l 2.
- Call for Fire Assistance (I) c)- "An experiment has failed and a
- Call NNRC Staff (AA) l minor release of radioactivity L
has occurred - MAP-1 & Kanne
- Call NNRC Staff (IN) readings are high"
- Call NNRC Staff (I) 1.
- Call HP (IN) 3.
- Call HP (I)
- d) " Received report that a tornado will strike the NNRC and reactor
- Call NRC (AA) safety systems could be affected"
- Call NRC (IN) 1.
- Call NRC (I) 2.
- Call GA Dept. Nat.
3.
Res. (GDNR) (AA) 4.
- Call GDNR (IN)
- Call GDNR (I)
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F.
' STANDARD AND EMERGENCY OPERATING PROCEDURES Page 72 i
QUESTION F.07 (1.00)
Which one of the following sequence of events is TRUE7 During reactor operations, at ~11:00 AM, a " Process Room Doors Open". alarm is received in the control room.
The proper response of'the GTRR operator is to:
a.
Immediately dispatch a field operator to the process equipment room to determine if anyone has made an unauthorized entry.
Reduce power,or shutdown Rx IF entry to room is required.
- b. Immediately shutdown (Scram) the reactor.
Dispatch a field operator after shutdown of the reactor.
Determine if'anyone has made an unauthorized entry, c.
Immediate1y' shutdown (Scram) the reactor.
Immediately dispatch a field operator to enter the process equipment room, after shutdown of the reactor.
d.
Immediately dispatch a field operator to enter the process
. equipment. room to determine if anyone has made an unauthorized entry.
Notify-NNEC management of the problem.
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F.
STANDARD AND EMERGENCY OPERATING PROCEDURES Page 73 l QUESTION F.08 (1.00)
Concerning Operator Licenses and GTRR staffing, which one of the
.following statements is TRUE?
- a An operator who willfully violates any provision of his license,.
including stated conditions, may be guilty of a crime & upon conviction, the individual - not necessarily the facility.- may be' punished by fine and/or imprisonment.
b..Whenever the reactor is secured, the MINIMUM crew complement at the facility shall be TWO persons, including at least ONE RO and at least ONE SRO, licensed pursuant to 10 CFR 55.
- c. A reactor operator or senior reactor operator licensed pursuant to 10 CFR 55 shall be present at the controls - at all times - as defined by GTRR's Technical Specifications.
- d. As defined by GTRR's Technical Specifications, the Reactor Supervisor.shall hold either a reactor operator's or senior reactor operator's license.
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Y F: -S'TANDARD AND~ EMERGENCY OPERATING PROCEDURES Page 74-
, QUESTION F.091 (1.00)
Concerning Personnel Survey Frequency and Personal Frisking, which one of;the following statements.is TRUE?
a When performing a personal frisk, initially set - or ensure that the frisker unit is set - on its highest scale and' fastest response setting.
'11.
If an increase in " click rate" is heard, return the probe to the area of increased click rate & hold the probe over the' suspected area for ~4 to 5 seconds for confirmation.
-c. If increased " click rate" is confirmed and/or increased over
-previous background levels - greater than 1000 cpm over normal' bkgd - immediately leave the reactor control zone, proceed to a clean area and promptly notify HP.
- d. When exiting a-potentially contaminated area, personnel shall frisk to a level which is specified on an applicable RWP. If not specified on.the RWP, at a minimum, frisk head, hands, feet, arms, legs,-back and torso.
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l E.~
STANDARD AND' EMERGENCY OPERATING PROCEDURES' Page 75 F
fQUESTI N F.10-(2.00).
MATCH ~the1 areas below with their applicable definition - NOTE:
Only ONE. definition is applicable to each area.
AREAL DEFINITIONS-a) ~ ' EXCLUSION AREA
- 1. An outer boundary formed by a 400 meter radium centered on b)
REACTOR. CONTROL ZONE the reactor.
c)
RADIATION AREA
- 2. An area to which access is controlled for purposes of~
d)
LOW POPULATION ZONE (LPZ) protection of individuals from exposure to radiation / rad matl.
- 3. An area inside the circle formed by a 100 meter radium centered at the reactor.
- 4. An area NOT controlled for purposes of radiation. Limits personnel exposure to <2 mR in any one hour, or 100 mR in 7 consecutive days.
- 5. Area inside the facility at-whien radiation levels may range from 5 mR/hr up to but not inclusive of 100 mR/hr.
- 6. An established area'at a radium of 523 meters from the containment building.
- 7. Any area in which potential exists to expose individuals to radiation / rad material in excess of 100 mR/hr at 18 inches from the source.
(*****
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F.
-STANDARD AND EMERGENCY OPERATING PROCEDURES Page 76 l;
QUESTION-F.11
.(1.50)
In accordance with 6020, the first three action steps upon noting "a
. Deuterium Oxide leak at a' power level of 1 Mw or less" are the same as the first three steps to be taken if the leak was to occur at a. power of greater than 1 Mw.
LIST these steps.
(***** END OF CATEGORY F *****)
QI
- G.
RADIATION CONTROL'AND SAFETY-Page 77
- THIS PAGE INTENTIONALLY BLANK -
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l..
jG.
RA'DIATION dONTROL AND SAFETY-PageL70 l
1 ls l LQUESTION, G.01 (2.00) 1 I
Given - that' the " Exposure Rate Constant" for Cobalt-60 is equal tx>
l
~13.2 Roentgens-sq. cm per hr-mC1, CALCULATE the MINIMUM distance an individual would need to' stand from a 2 Curie point source such that
.the-individual's' exposure rate would be held to less than 50 mr/hr?
Assume that the point source is exclusively Cobalt-68.
I STATE ALL ASSUMPTIONS - SHOW CALCULATIONS i
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G((
~~~
G.
' RADIATION CONTROL AND' SAFETY Page'79-
- " QUESTION
- G.02' (1.75) a)
LIST the locations of the continuous monitoring external' gamma area radiation monitors including the areas which they monitor.
~
(0.75).
b)-
LI'ST the-locations of the criticality monitors.
(1.0)
(***** CATEGORY G CONTINUED ON NEXT PAGE *****)
t l G.
RADIATION CONTROL AND SAFETY Page 80.
' QUESTION G.03
- (1.50).
A " Cutie Pie" and a Geiger-Mueller instrument are used to survey a
< beta-gamma radiation field.
The following. readings are recorded:
" Cutie ~ Pie" (Closed Window)
~2.5 Roentgens per hour
" Cutie Pie" (Open Window)
~3.1 Roentgens per hour Geiger-Mueller Instrument
- ~ZERO (0) CPS'(Range " set" to lowest scale) a). What is the " beta-gamma" dose rate in'the area?
b)
What is the " beta" dose rate in the area?
.c).
Why would the Geiger-Mueller instrument - even though properly
" checked out" prior to operation - be reading'ZERO (0) "counte"?
(*****
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G.
RADIATION CONTROL AND SAFETY Page 81 QUESTION G.04 (2.00)
A point source of. gamma radiation has been surveyed and causes a dose rate of 1000 mr/hr at one meter.
j a)'
It has been determined that it would.take one person 45 minutes to install and 15 minutes to remove a tenth thickness of lead shielding at one meter from the source.
ASSUME no shielding effects from the lead during the performance of this job.
CALCULATE the exposure the person would receive while doing this job.
(0.5) b)
-A' job has'been proposed which would take two people 1.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> to perform at 10 meters from the source.
CALCULATE the total exposure the TEAM would receive including that calculated in part a). (1.0) c)
CALCULATE the total exposure-received for the same job in b) above.except WITHOUT the shielding installed. (0.5)
I.
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L___________________________________________-
G.
' RADIATION CONTROL'AND SAFETY Page.82 QUESTION
'G;05 (1.00)
' STATE the maximum 10 CFR~20 limits of radiation dose permissible per
- quarter for the whole body; the forearms; and the skin of the-whole
- body.-
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l
G.
RADIATION CONTROL AND SAFETY Page 83 QUESTION-G.06'~
(1.00)
~
'From the following list of types of radiation, SELECT which ones a)
.are " ionizing" radiation.
1.
. alpha 2.
beta 3.
gamma 4.
microwave 5.
laser 6.
ultraviolet 7.
x-ray.
8.
neutron
- b):
DEFINE a curie.
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Y
'G.
' RA1)IATION CONTROL AND SAFETY Page 84 QUESTION G.07
('O.50)
An~ operator is working with a co111 mated gamma ray beam.
The
~
radiation level.(contact) on the shielded side of a thin shield, one
' foot from the'collimator,.is 1000 mrad /hr.
. NOTE:' ASSUME NO SCATTERING' EFFECTS
-STATE / CALCULATE the expected radiation level ten feet past the shield..
I.
(***** CATEGORY G CONTINUED ON NEXT PAGE *****)
^l G.
RADIATION CONTROL AND SAFETY Page 85 QUESTION-G.08
-(1.00)
.l a)
STATE which university department is responsible for-radioactive shipments: received by Georgia Tech.
. b)'-
STATE who is responsible for decontaminating an accidentally contaminated area-
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Y 'G.
' RADIATION CONTROL AND SAFETY Page 86 lQUESTION-G.09 (1.00)
Which one of-the following would be the do.ee received in mrem after 45 minutes-in a. gamma field of 80 MRAD / hr.
a.
20 MREM b.
40 MREM c.
60 MREM
'd.
90 MREM
(*****
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i
_.__._..__________-_____________________m___.
Gl RADIATION CONTROL'AND SAFETY Page:87 b
il
[ QUESTION-G.10 (1l00)
Which one of the following' isotopes is considered to be a significant internal radiation hazard since it easily penetrates the skin?.
a.
Iodine 131~
'bi Thitium
~c.
Argon 41 t _.e,
~
d.
Uranium 238-(*****
CATEGORY G CONTINUED ON NEXT PAGE *****)
J G.'
RADIATION CONTROL AND SAFETY.
Page 88-
.r..
QlTESTION G.11
-(1 00)
' STATE which isotope is formed in the graphite region of the reactor-and:is a significant gamma emitting radiation hazard.
j-.
1
(*****
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- G.
' RADIATION CONTROL'AND SAFEll Page 89 l
L OQUESTION G.12
( 1. 2 5 )..
.For each~of the.following statements, FILL-IN THE' BLANK with one of
- the choices given below.
l. NOTE:
Each choice may be used more than once.
Use of the number L
'beside:the' choice is sufficient.
a) working under a RWP shall comply with the requirements of
. that: RWP.
Ib) is responsible for notifying HP that a job is completed.
jc) must sign the RWP form.
d) shall maintain RWP surveys and other documents.
e)
RWPs shall: be maintained until their disposal is authorized by CHOICES 1.
all' personnel 12.
Health Physics 3.
the RWP requestor 4.
.the NRC,
(*****
END OF CATEGORY G *****)
(********** END OF EXAMINATION **********)
A'.
PRINCIPLES QE REACTOR' OPERATION Page 90 L
L l.
ANSWER A'.01
-(1.00) b.
REFERENCE GTRR: Nuclear. Reactor Theory, Lamarsh 12-8 ANSWER A.02 (1.00) a.
, REFERENCE GTRR: Reactor Operator Training Chap 12
~~ ANSWER A.03 (1.00)-
CANSWER c.
REFERENCE
'* REFERENCE GTRR: Reactor Operator Training Chap 11
! ANSWER.
A.04 (1.00) a..
REFERENCE GTRR: Reactor Operator Training Chap 9
(*****
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- k...
[ X l RINCIPLES_0F REACTOR OPERATION
,Page 91
{,:
L
':' ANSWER A.05.
(1.00)
OANSWER-d.
' REFERENCE t
- REFERENCE LGTRR: Reactor Operator Training Chap 10
' ANSWER-A 06 (1.00)
CANSWER c.
REFERENCE
- REFERENCE GTRR: Reactor Operator Training Chap 10 ANSWER' A.07 (1.00)
- ANSWER a.
2 REFERENCE.
oREFERENCE GTRR: Reactor Operator Training Chap 10 ANSWER
- A.08 -
.(1.00) 0 ANSWER a.
REFERENCE
- REFERENCE
'GTRR: Reactor Operator Training Chap 10
(*****
CATEGORY A CONTINUED ON NEXT PAGE *****)
- .A.
PRINCIPLES OF' REACTOR OPERATION Page 92 i-
-ANSWER A.09 (1.00)
CANSWER d.
REFERENCE L* REFERENCE GTRR: Reactor Operator Training Chap 10 JANSWER A 10 (1.00) b.
a-REFERENCE GTRR: Reactor Operator Training Chap 5
' ANSWER A.11 (1.00)
CANSWER d.
REFERENCE'
- REFERENCE GTRR: Reactor Operator Training Chap 14 ANSWER A.12 (1.00)
- ANSWER a.
LREFERENCE
-CREFERENCE GTRR: Nuclear Reactor Theory Lamarsh, Chapter 8, pgs 260 - 264.
(*****
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J
- Al PRINCIPLES OF REACTOR OPERATION' Page 93 L
' ANSWER'-
'A.13 (l'.'00)
- ANSWER-
-b.
REFERENCE REFERENCE
- GTRR: Reactor Operator Training Chap 10
~ ANSWER A.14
-(1.00)-
i C..
- REFERENCE
.GTRR; Reactor Operator Training Chap 10
~
ANSWER A.15 (1.00) j CANSWER
- d.
' REFERENCE OREFERENCE GTRR: Reactor Operator Training Chap 12 ANSWER A.16 (1.00) i d.
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i
! REFERENCE I
GTRR: Reactor Operator Training Chap 10 l:
(***** END OF CATEGORY A *****)
B; FEATURES OF FACILTTY DESIGM Page 94
.. ANSWER B.01 (1.00)
- ANSWER a.
REFERENCE CREFERENCE GTRR: SAR ANSWER B 02 (1.00) b.
REFERENCE GTRR: SAR ANSWER B.03 (1.50)
CANSWER 0.50 each:
- 1) Buffer zone (air lock)
NOTE: Also accept the follow-
.2) Reduce spread of contamination (from the hot cell) ing:
3)' Permit temporary storage of contaminated equipment "Provides set-up area for jobs to be perform-REFERENCE ed in the hot cell area'
- REFERENCE GTRR: SAR Pg. 25 ANSWER B.04 (1.00)
- ANSWER c.
I
(*****
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?..
. FEATURES OF FACILITY' DESIGN Page 95
(- B';
l i' REFERENCE r
- REFERENCE-
'GTRR: SAR i
-ANSWER B.05 (1.00)
The second blower will auto start (if pressure in either cell' rises above about 0.1 inch of water below atmospheric pressure). (1.00)
REFERENCE
.GTRR: SAR
. ANSWER
-B.06 (1.00)
CANSWER C.
.. REFERENCE
- REFERENCE
~GTRR: SAR ANSWER B.07 (1.00)
CANSWER O.50 each:
1). holdup volume (for exhaust)
- 2) expansion volume for N2 REFERENCE
- REFERENCE
~GTRR: SAR
(*****
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s:1 FEATURES-OF FACILITY DESMli Page 96 L
1.
I NNSWER'..
B.08 (2.00) 0.50 Leach:
1).-inserted (scrammed) 2). closed
<3)' drained (to-the storage tank)
L'4) opened
~ REFERENCE GTRR: SAR 8.2.1 ANSWER B.09 (1.00)
CANSWER 0.50 each:
a)' D20 high temperature b) void or. temperature coefficients REFERENCE
- REFERENCE
'GTRR: SAR 8.2.5 ANSWER B.10
. G.-00-)- (1.00)
CANSWER 0.25 Any four at 0.40-each:
- 1) H1
- 2) H3
- 3) H4
- 4) H7
- 5) H8
- 6) H10
-REFERENCE
- REFERENCE GTRR: SAR 4.4.6.2 i
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___m__________
_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - -Q
t'
-B.
FEATURES OF FACILITY DFjilfdl Page 97-
.AN.SWER-B.11 (1.00)-
- ANSWER 0.50 each:
.1)'
shutter closes 2): entrance-door-is-kept in place.
REFERENCE
-CREFERENCE-GTRR: SAR 4.4,6.2 l
4
' ANSWER B.12 (1.00)
Uses,the developed head of-the overflow return pumps (as the driving i
force for.the purification system flow).
' REFERENCE GTRR: SAR 4.4.9.2 l
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-)
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(*****
END OF CATEGORY B *****)
l
_. _______-_____ x___- -_ - -
a
-C.
' GENERAL OPERATING CHARACTERISTICS
.Page 98
- p. >
4 ANSWER-C.01 (1.50)
CANSWER
.a)
A Co-60 wand (57 uCi sealed source)-(0.-25) n b)
Is placed at the' connector end of the detector (0.25) c):
For 30 seconds (0.25) d)-
Increased counts should be seen (by the control room operator) e)... -(0.25)
On the-rate' meter'(0.25) and the stripchart recorder (0.25). (The L
values should be recorded )
-REFERENCE 0 REFERENCE
'GTRR Procedure.9012, p.3.
' ANSWER C.02 (2.00)
CANSWER a)
Greater than 2 inches movement (exact distance for 1.0 point) b)
-15 seconds
(+ or - 2 seconds for 1.0 point)
REFERENCE CREFERENCE GTRR Procedure 3104, p.1-2.
ANSWER C.03 (1.00)
.b.
(1.0)
REFERENCE GTRR SAR, p.128.
(*****
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l C.
GENERAL OPERATING CHARACTERISTICS Page 99 L
l
' ANSWER C.04 (2.50)
- ANSWER 1.
Visual Inspection It is conducted at approximately 6 month intervals (0.25).
Using a borascope (0.5) beneath the lower top shield permits actual
. observation of Emergency Coolant Water entering all fuel elements (or fuel element mock-ups) (0.5) 2.
Temperature Monitoring It is conducted at monthly intervals (0.25).
Following a reactor shutdown and after allowing sufficient time for decay heat removal, the top reflector is drained to the storage tank (0.5).
This exposes the fuel element thermocouple to the nitrogen gas blanket at 90-100 degrees F Emergency Coolant Water (approx. 75 degrees F) is initiated, and a sharp temperature decrease on all functioning thermocouple should be noted (0.5). )
REFERENCE
- REFERENCE GTRR SAR, p.133.
ANSWER C.05 (3.00) a)
Regulating rod will move out. (0,5)
Compensation for Xenon buildup. (0.5) b)
Regulating rod will not move. (0.5)
Automatic switch of the power control system to manual due to
>10% setpoint to reactor power deviation. (0.5) c)
Regulating, rod will move in. (0.5)
Compensation for the power increase due to the MTC response from the increased cooling. (0.5)
NOTE: For "b" above:
If candidate expresses that the " fault" occurs within the 10% deviation band, the reguldting rod could move out since there would NOT be a switch to manual therefore the candidate should receive full credit for such an answer.
(***** CATEGORY C CONTINUED ON NEXT PAGE *****)
'th ' GENERAL' OPERATING CHARACTERISTICS Page100 v
i-
' REFERENCE-
- 5GTRR SAR, p.69.
ANSWER C.06 (1.00)
'b.
(1.0)
REFERENCE--
GTRR SAR, p.75 ANSWER C.07 (2.00) a)
(any 3 of the following at 0.5 each)
- 1. Scram
- 2. Loss of I&C power
- 3. Loss of mercury lamps 4.
Emergency lights illuminate b)
There is no indication.
(0.5)
REFERENCE GTRR OP 5105, p'.1.
' ANSWER C.08 (1.00) b.
(1.0)
(*****
CATEGORY C CONTINUED ON NEXT PAGE *****)
- C. ' GENERAL OPERATING CHARACTERISTICS Page101 REFERENCE
'GTRR'SAR, p.117.
ANSWER-C.09 (1.00)
- 20 seconde (Exact time required for 1.0 point.)
REFERENCE GTRR' Operating Procedure 2000, Ch. 4.
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(***** END OF CATEGORY C **r<**)
r 1
D.
= INSTRUMENTS AND CONTROLS Page102 ANSWER D.01 (1.50)
- ANSWER
'a) There are 2 doors from the process equipment room (0.5) NOTE:
" Entry from the b) Locked shut (0.5)
E s eq $.
c) Opening either door activates an alarm (0.5) po j an REFERENCE acceptable answer since the question DOESNOTelici{2 0 REFERENCE the answer of rs".
GTRR SAR, p.56.
. ANSWER D.02 (1.00)
- ANSWER c.
(1.0)
REFERENCE
- REFERENCE GTRR SAR, p.139.
. ANSWER D.03 (1.00)
- ANSWER a.
(1.0)
REFERENCE
- REFERENCE GTRR SAR, p.79.
(*****
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I
"D.
INSTRUMENTS ANILEDNTROId Page103 f
ANSWER D.04 (1.00)
~a )'-
0.2.in/second (accept + or - 0.02)
(0.5) b)-
'O.01 % per second (accept + or - 0.001) -(0.5)
= REFERENCE GTRR SAR, p.140.
ANSWER
.D.05~
(1.00).
- 1'.
Mechanical limit switch on.the spray' block valve handle (valve not fully open). (0.5)
'2.
TD-2 level indicator. (0.5)
REFERENCE
.GTRR E0P.5059, p.2 ANSWER D 06 (1.00) c.
(1.0)
' REFERENCE Nuclear Rad. Det., Price, p_42.
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pm77 3
E D.
-INSTRUMENTS AND CONTROLS Page104 j
L L
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LANSWER D.07 (1.50) 0 ANSWER a) Battery (0.5) supplies' lighting and PA system (0.25) b) (43.8.KVA nat gas) engine generator set (0.5) supplies house loads (0.25)
~ REFERENCE GREFERENCE GTRR SAR, p.70.
ANSWER D.08 (2.50)
- ANSWER (Any 5 @ 0.5 each)
- 1. Low H2O ilow
- 2. Control air low pressure l.
- 3. Low shield coolant-flow
- 4. High shield coolant temperature
- 5. High bismuth coolant temperature
'6.
Low bismuth coolant flow REFERENCE
- REFERENCE
'GTRR SAR, p.
72.
(*****
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l. DI INSTRUMENTS AND CONTROLS Page105 i,
l ANSWER D.09 (3.00)
- ANSWER
!.a) 3 f) 5 b)
.1 g) 8 c) 4-h) 10 d)' 4 i) 9-e) 6 j) 9 (0.3 each)
REFERENCE
.0 REFERENCE GTRR SAR, p.71-73.
i J
ANSWER D.10 (1.00)
CANSWER a.
i REFERENCE
- REFERENCE.
i GTRR: SAR pp 72-73 J
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(*****
END OF CATEGORY D *****)
f-E.
SAFETY'AND' EMERGENCY SYSTEMS.
Page106 I
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- ANSWER:
E.01 (2.50)
- AN'SWER-
- 1. Reactor Power Circuitry (0.5)
- 2. Reactor Period Circuitry
( 0. 5 ')
-3.
Deuterium Oxide (0,1) - " heavy water" - Temp Circuit (0.4) 4 Deuterium Oxide Q.1).- " heavy water" - Flow Circuit (0.4) l 5'.
Deuterium oxide (0.1) - " heavy water" - Level Circuit (0.4) l NOTE: The terms " circuitry" or " circuit" IS NOT required for full credit, j
REFERENCE
- REFERENCE GTRR SAR; Pages 67 through 69.AND Figure 4.23, Page 68 ANSWER E.02 (2.00)
- ANSWER ONE-(1) MW (0.5) 1 EIGHT-(8) GPM (0.5)
)
THIRTY (30) to thirty seven (37) mins (0.5)
NINETEEN (19) fuel element positions (0.5) i REFERENCE
]
- REFERENCE
.GTRR SAR; Pages 79 through 81 ANSWER E.03 (1.00) av'C. (1.0)
NOTE: Answer "c" is the most correct answer. Answer "a" is an acceptable means of core spray verification if the plant has been operating at low or intermittent power levels. Answer "c" IS NOT an acceptable REFERENCE means of verification - ALARA and overall HP " common sense" concerns.
I GTRR SAR; Page 81 AND GTRR Procedure 7211 i
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1 s
i E,
SAFETY'AND' EMERGENCY SYSTEMS Page107 L
1 i
! 5NSWER E.04
-(1.50)
LThefvalves-are part of the " Top. Reflector Control System".(0.5)
-NOTE: " Primary Coolant Supply and Return System" is acceptable.
By: opening valves SA & 5B the upper volume (mass)
~28 inches of
~1evel -'of Deuterium Oxide (" heavy water") is. removed. (0,5)
By! draining this mass of water, the operator has, in effect, removed
'the upper neutron reflector and, in turn, caused a reduction in core reactivity.and'overall flux level.
(0.5)
LNOTES: 'Similar explanations are acceptable for full credit.
TheLterms " heavy water", " Deuterium Oxide", "SA & SB"
"~28 inches of level" IS NOT required'in the candidate's
-response.
REFERENCE
-GTERLSAR; Pages 83'& 84 AND GTRR Procedures 2000, 5000 and 8100 ANSWER E.05 (1.00)
- ANSWER b.
(l' 0)
" REFERENCE
- REFERENCE iGTRR SAR; Page 84 AND GTRR Procedures 2400 & 8400
(***** CATEGORY E CONTINUED ON NEXT PAGE *****)
?. E.
SAFETY AND' EMERGENCY SYSTEMS Page108 L ANSWER E.06 (2.00)
L
~The Overpressure Relief System (0.5)
- System consists of a' pipe which connects the gas volume in the upper l
part of the reactor tank to an expansion chamber (provided beneath the basement floor in the containment building).
(0.5)
Pipe is closed at its lower end with a graphite diaphragm which will rupture at ~1 PSIG.
(0.5)
Rupture of the diaphragm will permit the steam to expand into the chamber, thus relieving pressure within the vessel.
(0.5)
-NOTES 5 Similar explanations'are acceptable for full credit.
The terms " graphite diaphragm", & "1 PSIG" ARE NOT required in the candidate's response.
The location of the expansion chamber IS NOT required in the candidate's response.
~
REFERENCE GTRR SAR; Page 86 ANSWER E.07 (1.00) b.
{1.0)
REFERENCE GTRR SAR; Pages 84 & 85 AND GTRR Procedures 3000 & 8500 ANSWER E.08 (1.00) a.
(1.0) 1
(*****
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i l
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l 3 E., : SAFETY AND EMERGENCY SYSTEMS Page109
- REFERENCE GTRR SAR; Pages 128'&f129 AND GTRR Procedure 1500
, ANSWER.
E.09-(l'.00) l. '.~ d.
( 1. 0 ) -
- REFERENCE GTRR SAR;.Pages 141 &.142 l
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(**:*** END OF CATEGORY E *****)
F.
STANDARD AND EMERGENCY OPERATING PROCEDURES Page110
. ANSWER F.01 (2.50) i 1.
Press manual ECCS initiation button.
(0.5) 2.
Verify Rx isolation valves close & LID-1 stabilizes. (0,5) 3.
Verify ECCS spray valves open.
(0.5) 4.
Dispatch operator to process room to look for large l
Deuterium Oxide leak.
(0.5) 5.
Observe Kanne Chamber for up-scale reading.
(0,5)
NOTE: Also accept for F.01:
"If emerg is real:
REFERENCE
- a. Verify Emerg. Coolant Spray is initiated GTRR Procedure 5000
- 1. Obs TD-2 lvl dropping
- 2. @ dump lvl obs fuel element 1
temperature on TR-1
- b. Provide additional supply of cooling water from:
ANSWER F.02 (1. 0)
- 1. City Water
- 2. Spent Fuel Basin Water
- ANSWER "0t r"
a.
30 to 37 minutes (0.5)
"Ifebe
- a. Close ball valve to stop b.
"LESS THAN" ECCS spray FIFTY (50) inches (0.5)
- b. Restore normal primary coolant flow as soon as possible."
' REFERENCE 0 REFERENCE GTRR Procedure 5000 ANSWER F.03 (1.00) c.
(1.0)
' REFERENCE GTRR Procedure 5000 e
ANSWER F.04 (1.00) oANSWER a.
(1.0)
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F....'EIANDARD:AND EMERGENCY OPERATING PROCEDURES Page111-REFERENCE-
.10 REFERENCE
't-1GTRR/NNRC Procedure 6030
,ANSWERf F.05 (1.00)
'OANSWER c,
(1.0)
REFERENCE
'* REFERENCE-GTRR/NNRC Proc 6040; Sec 5.2.4.1,
" Fire During Working Hours" ANSWER-F.06 (2.50)
- ANSWER a)-1. Call NNRC Staff (0.125)
- Immediately (I)
(0.125)
NOTE:. Contacting "HP Immediately" is also acceptable
'b) 1. Call GT Police (0.125)
- Immediately (I)
(0.125)
- 2. Call the NRC
.(0.125)
- After Assessment (0.125) c)L1. Call GT Police (0.125)
- After Assessment (0.125)
- 2. Call the NBC (0.125)
- After Assessment (0.125)-
- 3. Call HP (0.125)
- Immediately (I)
(0.1251 d) 1. Call HP (0.125)
- Immediately (I)
(0.125) 4
- 2. Call GT Police (0.125)
- Immediately (I)
(0.125)
- 3. Call the NRC (0.125)
- Immediately (I)
(0.125) l
- 4. Call the GDNR (0.125)
- Immediately (I)
(0.125)
-REFERENCE I
- REFERENCE GTRR/NNRC Proc 6100
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CATEGORY F CONTINUED ON NEXT PAGE *****)
1' I
F '.
STANDARD AND-EMERGENCY OPERATING PROCEDURES Page112 ANSWER
~ F.07-(1.00)
G.:(1.0)
' REFERENCE'
.NHRC/GTRR Procedure 5058 ANSWER F.08.
(1.00) ta.
'(1.0)
[
REFERENCE NNRC/GTRR Te.'.nical Specification; Administrative' Controls Section AND id CFR 55 requirements ANSWER F.09 (l'.00) b.
(1.0)
REFERENCE NNR0/GTRR HP Procedure 9280
' ANSWER F.10 (2.00) 0 ANSWER a) 3 (0.5) b) 2 (0,5) c). 5 (0.5) d) 1 (0.5)
(***** CATEGORY F CONTINUED ON NEXT PAGE *****)
1
- F.
STANDARD'AND EMERGENCY OPERATING'PROCEDUlES.
Page113 4' REFERENCE
.* REFERENCE-1NNRC/GTRR HP Procedure 9310 AND GTRR Technical Specifications Site Description Section ANSWER F.11 (1,50) u
- ANSWER-
'1.
. Scram the' Reactor.(0.25) - Make sure building isolated.(0.25) 2.
Announce on PA (0.25)'- Evacuate " Containment".
(0.25)
'3.
Leave by fasteet route (0.25) - Through emergency exit.
(0.25)
REFERENCE
- REFERENCE NNRC/GTRR Procedure 6020 i
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END OF CATEGORY F *****)
G.
RADIATION CONTROL AND SAFETY Page114.
ANSWER G.01 (2.00)
. ANSWER-Given the following formula on the formula sheet:
Activity (C1)
Exposure Rate-(X) = Constant (T) distance (squared)
Ci distance (squared) : T X
2000 mci sq. distance : 13.2 R-sq. cm/hr-mci 50 mR/hr 13200 [2000/50]
= 2640000/5 = 528000 distance = 726.6 cm = 286.1 inches = 23.8 ft.
[ Calculation 1.5 pts - Ans = 0.5 pts]
[All Errors Carried Forward]
NOTE: Allow for C-M-Rem rule calculation REFERENCE CREFERENCE
" Radiation Detection And Measurement" (Knoll); Section A, Chapter ONE (1),: Pgs 74 and 75 ANSWER G.02 (1.75) a)
The containment bldc. (5 main floor ; 5 basement)
(0.5)
Hot laboratory (0.25) l b)
Near the spent fuel storage pool in the high bay area (0.5)
Adjacent to the cold fuel element storage vault (0,5) i 1
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L
LG. ! RADIATION CONTROL AND SAFETY Page115
-REFERENCE
'GT SAR pg;109 ANSWER G.03 (1.50)
- ANSWER a) 3.1 R/hr (0.25)
- b) 3.1-(-) 2.5 = ~0.6 R/hr (0,25) c)
The Geiger-Mueller instrument tube is apparently eaturated therefore it is giving an erroneous downscale reading.
(0.5)
REFERENCE
- REFERENCE
" Radiation Detection and Measurement" (Knoll), Section B, Chapter SEVEN (7), pgs 219 through 235 l
l l
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l l.
(--
e, G2 RADIATION CONTROL'AND SAFETY Page116 i-
. ANSWER.
G.04 (2.00)
'* ANSWER-
.( 80% setup, 20% math) a)
To install and remove shielding (45 min + 15 min)/ 60 min /hr x 1000 mr/hr (0.4)
= 1000 mr (0.1) b)
Exposure at 10 meters = dose rate x 1/10 thickness distance squared
= 1000 mr/hr x 1/10 thickness (0.4)
(10 meters squared)
= 1mr/hr (0.1)
Exposure for the two person shielded job at 10 meters (1.5 hr x 2) x 1 mr/hr (0.3)
= 3 mr (0.1)
Total exposure for this case = 1003 mr (0.1) c)
For unshielded job at 10 meters (1.5 hr x 2) x 1000 mr/hr (0.4)
(10 meters squared)
= 30 mr (0.1)
REFERENCE
- REFERENCE PGaE INTRODUCTION TO NUCLEAR POWER Chapter IV Radioactive Particle Emission
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.~_-
p-
[G2 RADIATION CONTROL'AND' SAFETY-Page117
- ANSWER
~ G.05 (1.00)-
whole body.
1.25 rem / quarter (0.34) forearms' 118.75 rem / quarter (0.33) skin 7.5 rem / quarter (0.33)
REFERENCE 10 CFR~20~
. ANSWER' G.06 (1.00)
OANSWER a) 1,2,3,7 (0.125 each) b ).
A curie is the amount of any radioactive isotope which is
' decaying at the rate.of 3.7 x E10 disintegrations per second.
(0,5)
REFERENCE.
- REFERENCE PG&E INTRODUCTION TO NUCLEAR POWER Chapter IV ANSWER G.07 (0.50)
-1,000 mrad / hr.
(A collimated source with no scattering assumed => there is no attenuation for gamma energy)
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.2 U G '.
RADIATION CONTROL AND SAFETY Page118~
REFERENCE PG&E INTRODUCTION TO NUCLEAR POWER Chapter IV-
)
,.,/.
./
jANSWER G.08 (1~.00)
- I,
"'a).
Office of Radiation Safety (0.5) b)
The individual who created the contamination (for significant contaminations,. health physics should supervise)
(O.5)-
REFERENCE' GT Procedure 9250 pg 1'of 7 ANSWER G.09 (1.00) c.
(1.0)-
REFERENCE
. PG&E INTRODUCTION 11 TO NUCLEAR POWER Chapter IV ANSWER G.10 (1.00)
~* ANSWER b.
(1 0)
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__--_-__ _ -_-____ _ - - _ _ _ _ _ A
tjG.
RADIATION' CONTROL AND SA MIX Page119 iREFERENCE-LOREFERENCE PG&E-INTRODUCTION TO NUCLEAR POWER CHAPTER 13.
Chemical, Radiochemical and Waste Disposal Considerations in Water Reactor Operation r
ANSWER.
-G.11 (1.00)
' Argon'41 (1.0)'
~ REFERENCE
- GT SAR pg 44 l ANSWER G 12' (1.25)
- ANSWER a) '
1 (0.25) b)
3 (0.25)
-c) 3 (0.25) d)
2 (0.25)
~
e) ~
4 (0.25)
REFERENCE-cREFERENCE GT Procedure 9306
' Preparation and Maintenance of RWPS
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END OF CATEGORY G *****-)
(********** END OF EXAMINATION **********-)
if
t l^
' TEST CROSS REFERENCE Page: 1 9dESTION VALUE-BEFEBENCE A.01 1.00 9000044 A.02-1.001 9000045 b
A.03 1.00 9000046 A-.04 1.00-9000047 i
A.05 1.00 9000048
' A.06
'1.00 9000049 A.07 1.00 9000050 A.0S 1.00 9000051
' A.09' 1.00 9000052 A.10 1.00 9000053 A.11-1.00 9000054 A.12 1.00 9000055 A.13 1.00~
9000056
- A.14 1.00 9000057 A.15 1.00 9000058 l
A.16
.1.00-9000059
~{~~6 00
/f
- 31'
.B.01 1.00 9000060
- B.02 1.00 9000061
' B.03 1.50 9000062 B.04 1.00 9000063
- B.05 1.00 9000064-
- B.06
-1.00 9000065 B.07 1.00 9000068 B.08 2.00
-9000067 B.09 1.00 9000068 B.10 2.00 9000069 B.11 1.00 9000070 B,12.
1.00 9000071
]~4]O
/3* Nb C.01 1.50 9000004 C.02 2.00 9000005 C.03
.1.00 9000010 C.04 2.50 9000011 C.05 3.00 9000015 C.06 1.00 9000016 C.07 2.00 9000017 C.08 1.00 9000018 C.09 1.00 9000019
/f' 7 /
15.00 D.01~
1.50 9000001 D.02 1.00 9000002 D.03 1.00 9000003 D.04 1.00 9000006 D.05 1.00 9000008 D.06 1.00 9000009 D.07 1.50 9000012 D.08 2.50 9000013 D.09 3.00 9000014 Q_-____-----_---
TEST CROSS REFERENCE Page 2
QUESTION VALUE REFERENCE D.10' 1.00 9000090
~$[~g fl88 V 5
E 01' 2.50-9000021 E.02 2.00 9000022 E.03 1.00 9000023 E.04 1.50 9000024 E.05 1.00 9000025 E.06 2.00 9000026 E.07 1.00 9000027 E.08 1.00 9000028 E.09 1.00 9000029 i
E.10~
1.00
/3. [j6
~~~~~-
14.00 F.01 2.50 9000032 F.02 1.50 9000033 F.03 1.00 9000034 F.04 1 00 9000035 F.05 1.00 9000036 F.06 2.50 9000037 F.07 1.00 9000038 F.08 1.00 9000039 F.09 1.00 9000040 F.10 2.00 9000041 F.11 1.50 9000042
,s' 14,80 /Ti $$
N'h)
G.01 2.00 9000074 G.02 1.75 9000075 G.03 1.50 9000076 G.04 2.00 9000077 G.05 1.00 9000078 G.06 1.00 9000079 G.07 0.50 9000080 G.08.
1.00 9000081 G.09 1.00 9000082 G.10 1.00 9000083 G.11 1.00 9000084 G.12 1.25 9000085
/ t/. 3 3 - f 15.00 loYf /
- _ _ - --- -