ML20011F372
| ML20011F372 | |
| Person / Time | |
|---|---|
| Site: | North Carolina State University |
| Issue date: | 01/29/1990 |
| From: | Ernstes M NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20011F357 | List: |
| References | |
| 50-297-OL-89-01, 50-297-OL-89-1, NUDOCS 9003050225 | |
| Download: ML20011F372 (97) | |
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i EXAMINATION REPORT 297/0L-89-01 facility Licensee: ~ North Carolina State University i-
'Raleigh, NC 27695 - 7909
~ Facility Name:
North Carolina State University
[
Facility Docket No.:
50-297 Facility. License No.:
R-120 Examinations were administered at North Carolina State University near Raleigh, North Carolina.
Chief Examiner:
Mi Im/ [ h I[
h29 p Michael E. Ernstes Date Signed
- Approved By:
/
/!3oko 7ohn F. Mbnro Chief Date Signed Operator Licensing Section 1 Division of Reactor Safety
SUMMARY
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Examinations were administered on November 27-28, 1989.-
Written -examinations and operating tests were administered to ' four R0 l
applicants, all of whom passed.
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,li PDR ADOCK 05000297 V
PDC U
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4 REPORT DETAILS i
1.
Facility Employees Contacted:
G. D. Miller, Associate Director S. M. Grady, Chief Reactor Operator T. C. Bray. Reactor Operations Manager 2.
Examiners:
- M. Ernstes, NRC, Region 11 S. Guenther NRC, Headquarters C. Gratton, NRC Heedquarters
- Chief Examiner 3.
Exit Meetina:
At the conclus1on of the site visit, an extminer :et with representatives of the plant staff.to discuss the results of the examinations.
The cooperation given to.the examiners and the effort to ensure an atmosphere in the control room conducive to oral examinations was also noted and appreciated.
The licensee did not identify as proprietary any material provided to or
.)
reviewed by the examiners.
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NRC Official Use Only i
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Nuclear Regulatory Commission Operator Licensing Examination 3
i This document is removed from L
Official Use Only category on date of examination.
NRC Official Use Only
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l' U. S. NUCLEAR REGULATORY COMMISSION REACTOR OPSRATOR LICENSE EXAMINATION-REGION 2 FACILITY:
North Carolina State Univ.
REACT 0!! TYPE:
PULSTAR i
DATE ADMINSTERED:
89/11/27 i
CANDIDATE:
INSTRUCTIONS TO CANDIDATE:
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 three (3) hours after the examination starts.
% OF CATEGORY % OF CANDIDATE'S CATEGORY
. CATEGORY VALUE _ TOTAL SCORE VALUE 21,50 M-M-A.
REACTOR THEORY, THERMODYNAMICS
% SS AND FACILITY OPERATING CMARACTERISTICS
-Mr-ltXT iHHr8 B.
NORMAL AND EMERGENCY OPERATING 23.00
% tol PROCEDURES AND RADIOLOGICAL CONTROLS M.-00 M-04 C.
PLANT AND RADIATION MONITORING 73.co 34.o1 SYSTEMS UT. so JG-50 TOTALS FINAL GRADE
)
All work done on this examination is my own.
I have neither given nor received aid.
Candidate's Signature
I NRC RULES AND CUIDELINES FOR LICENSE EXAMINATIOdS During the administration of this examination the following rules apply:
- 1. Cheating on the examination means an automatic denial of your application and could result in more severe penalties.
- 2. After the examination has been completed, you must sign the statement on the cover sheet indicating that the work is your own and you have not received or given assistance in completing the examination. This must be done after you complete the examination.
- 3. 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.
- 4. Use black ink or dark pencil only to facilitate legible reproductions.
- 5. Print your name in the blank provided in the upper right hand corner of the examination cover sheet.
- 6. Fill in the date on the cover sheet of the examination (if necessary).
- 7. You may write your answers on the examination question page or on a separate sheet of paper. USE ONLY THE PAPER PROVIDED AND DO NOT WRITE ON THE BACK SIDE OF THE PAGE.
- 8. If you write your answers on the examination question page and you need more space ta answer a specific question, use a separate sheet of the paper provided and insert it directly after the specific question.
DO NOT WRITE ON THE BACK SIDE OF THE EXAMINATION QUESTION PAGE.
- 9. Print your name in the upper right-hand corner of the first page of each section ef your answer sheets whether you use the examination question pages or separate sheets of paper.
Initial each page.
- 10. Before you turn in your examination, consecutively number each answer sheet, including any additional pages inserted when writing your answers on the examination question page.
-11, If you are using separate sheets, number each answer as to category and number (i.e. Plant Systems # 04, EPE # 10) and skip at 1 cast 3 lines between answers to allow space for grading.
12.-Write "End of Category
" at the end of your answers to a category.
- 13. Start each category on a new page.
- 14. Write "Last Page" on the last answer sheet.
- 15. Use abbreviations only if they are commonly used in facility literature.
Avoid using symbols such as < or > signs to avoid a simple transposition error resulting in an incorrect answer. Write it out.
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- 16. The point value for each question is indicated in parentheses after the question. The amount of blank space on an examination question page is i
NOT an indication of the depth of answer required.
i
- 17. Show all calculations, methods, or assumptions used to obtain an answer.
i
- 18L. Partial credit may be given, Therefore, ANSWER ALL' PARTS OF THE QUESTION AND DO NOT LEAVE ANY ANSWER BLANK. NOTE: partial credit will NOT be given on multiple choice questions.
- 19. Proportional grading will be applied. Any additional wrong information that is provided may count against you.
For example, if a question is worth one point and asks for four responses, each of which is worth 0.25 points, and you give five responses, each of your responses will be worth 0.20 points.
If one of your five responses is incorrect, 0.20 will be deducted and your total credit for that question will be 0.80 instead of 1.00 even though you got the four correct answers.
- 20. If the intent of a question is unclear, ask questions of the examiner only.
- 21. When turning in your examination, assemble the completed examination with examination questions, examination aids and answer sheets.
In addition, turn in all scrap paper.
- 22. To pass the examination, you must achieve at least 70% in each category.
- 23. There is a time limit of (3) hours for completion of the examination.
1 (or some other time if less than the full examination is taken.)
r
- 24. When you are done and have turned in your examination, leave the examin-ation area as defined by the examiner.
If you are found in this area while the examination is still in progress, your license may be denied or revoked.
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RX THEORY, THERMO 6 FAC OP CHARS Page 4 QUESTION A.01
-(1.00)
Which one of the following is the correct reason that delayed neutrons-enhance control of the reactor?
a.
More delayed neutrons are produced than prompt neutrons, b.
Delayed neutrons increase the average neutron generation time, c.
Delayed neutrons take longer to thermalize than prompt neutrons, d.
Delayed neutrons are born at higher energies than prompt neutrons.
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(***** CATEGORY A CONTINUED ON NEXT PAGE *****)
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RX THEORY, -THERMO & FAC OP CHARS Page 5 QUESi' ION ' :A.02
_(2.00)
-Match each' term listed below with its corresponding definition.
TERMS:
~1.
Fast Fission Factor 2.
Resonance Escape Probability 3.
Reproduction Factor 4.
Thermal Utilization Factor DEFINITIONS:
j A.
The number of neutrons born from fission by thermal neutrons The number of thermal neutrons absorbed in fuel i
B.
The number of thermal neutrons absorbed in fuel
.i The number of thermal neutrons absorbed in all materials
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The number of neutrons that do not leak out while thermal The number of neutrons that escape resonance capture while slowing down I
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The number of neutrons that escane resonance caoture while slowine down j
The number of neutrons that do not leak while fast
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The number of neutrons-that do not leek out while fast
-l Net number of neutrons born from fission by neutrons of all energies
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The net number of neutrons born from fission by neutrons of all energigg-l The number of neutrons born from fission by thermal neutrons j
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(***** CATEGORY A CONTINUED ON NEXT PAGE *****)
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RX THEORY, THERMO & FAC OP CHARS Page 6 QUESTION A.03 (1.00)
The Doppler effect is significant for the Pulstar reactor because of the a.
pin type fuel that is used b.
low enriched fuel that is used c.
control rod configuration used l
d.
low operating power levels I
b.
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i QUESTION'_- _ A.' 04':.. (l'. 00) -
.Which-one ofLthe follow'ing-factors of the six' factor-formula is most easily'-
-varied by.the reactor operator?
w thermal utilization factor a.-
- b.. reproduction factor c.
fast: fission factor
-d.-
ifast non-leakage factor
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RX TilEORY, THERMO & FAC OP CilARS page 8 4-QUESTION A 05 (1.00) k'hich one of the following is NOT a function of the installed neutron source?
a, provide a reliable source of neutrons to initiate the approach to criticality b.
provide a source of neutrons to initiate a chain reaction c.
provide an indication to the operator that the reactor nuclear instrumentation is functioning properly d.
provide a means for the operator to see changes in neutron flux as conditions in the reactor change h
(***** CATEGORY A CONTINUED ON NEXT PAGE *****)
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RX THEORY. THERMO & FAC OP CHARS Page 9 QUESTICN A,06 (1.00)
Enough reactivity is added to a shutdown reactor to double the count rate.
If this same amount of reactivity is again added to the reactor, then the reactor will be a.
suberitical b.
critical c,
super critical d,
prompt critical
(***** CATEGORY A CONTINUED ON NEXT PAGE *****)
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c.-add excesa. reactivity
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RX THEORY,-THERMO & FAC OP CilARS Page 11
..i QUESTION A.08 (1.00)
Which one of the following statements concerning the rcactivity values of equilibrium.(at power) Menon and peak (after shutdown) Xenon is correct?
(assume shutdown occurs from equilibrium conditions) a.
Equilibrium Xenon is INDEPENDENT of power level; peak Xenon is INDEPENDENT of power level, b.
Equilibrium Xenon is INDEPENDENT of power level; peak Xenon is DEPENDENT on power level.
l c.
Equilibrium Xenon is DEPENDENT on power level; peak Xenon is INDEPENDENT of power-level.
d.
Equilibrium Xenon is DEPENDENT on power level; peak Xenon is DEPENDENT on power level.
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RX THEORY, THERMO & FAC OP CHARS.
Page'13 V.
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[1 QUESTION A.10 (1.00)
Fill in the blanks Xenon 135 is removed from the core by and l--
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(***** CATEGORY A CONTINUED ON NEXT PAGE *****)
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RX THEORY. THERMO & FAC OP CHARS Page 14' QUESTION A.11 (1.00) k'hich one of the following describes the feature of the moderator temperature coefficient which leads to a self regulating reactor as modera or temperature increases?-
a.
Its negative value adds positive reactivity, b.
Its negative value adds negative reactivity, c.
Its positive value adds positive reactivity, d.
Its positive value adds negative reactivity.
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(***** CATEGORY A CONTINUED ON NEXT PAGE *****)
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RX THEORY. < THEPJto & FAC OP CHARS Page 15 a
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QUESTION A.12 (1.00).
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Which~one of the following conditions is most appropriate for announcing 1
that the reactor is critical during a reactor startup?
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No control. rod motion, stable zero SUR, stable source range count p
rate.
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No control rod motion, stable zero SUR, increasing source range count rate.
d.
Control rod motion, stable positive SUR, increasing source range count' rate.
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'RX' THEORY. THERMO-& FAC OP CHARS
- Page 16-R L
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A.13!
(1.00)
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During a: power escalation on the log N channel it takes 35' seconds for' reactor power to. double. Which one of.the following is the stable reactor.
r period that would cause this rate of change?
g, a.
17 seconds' i
b.
35 seconds' i
c.-.50 seconds.
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70~ seconds i
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RX THEORY. THERMO & FAC OP CHARS Page 17 QUESTION A.14 (1.00)
During a normal reactor startup (after a two week shutdown) the rod withdrawal is stopped at the 200 pcm position and power level' stabilizes.
Which one of the following statements correctly describes how power level will respond in the next hour if no other action is taken?
4 a.
'it will remain essentially constant b.
it will slowly decrease to one third of its maximum level-c.
it will rapidly decrease to the initial pre startup level d.
it will slowly increase due to the effect of long lived delayed neutrons t
(***** CATEGORY A CONTINUED ON NEXT PAGE *****)
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- QUESTION
A.15:
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CWhich'one'of the following rods has'.the highest worth?J 4
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lg-,
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- c. ' Regulating :
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RX THEORY, THERMO & FAC OP CHARS Page 19 QUESTION A.16 (1.00)
The Shutdown Margin Benchmark is best described by which one of the following?
a, the value of shutdown margin below which the reactor must be scrammed b.
the value of. shutdown margin below which the DSRO's permission is required for continued operation c,
the critical rod position above which a shutdown margin greater than the Technical Specification limit is ensured d.
the critical rod position above which a shutdown margin greater than 800 pcm is ensured k
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(***** CATEGORY A CONTINUED ON NEXT PAGE *****)
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RX THEORY, THERMO 6 FAC OP CHARS Page 20 QUESTION A.17 (1.00)
The automatic return to a low power level following a reactor pulse is primarily caused _by which one of the following?
- a. doppler coefficient I
- b. moderator temperature coefficient c, pulse rod falling back into the core d.. void coefficient due to the void formed when pulse rod is ejected j
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RX THEORY, THERMO & FAC OP CHARS Page 21 QUESTION A.18 (1.00)
(
Which one of the following ebanges adds positive reactivity to the reactor?
a, the pool temperature increases by 5 degrees F b,
an empty pneumatic sample tube is inserted into the reactor c,
the startup source is removed d.
the neutron radiography facility is installed o
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(***** CATEGORY A CONTINUED ON NEXT PAGE *****)
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RX THEORY. THERMO & FAC OP CHARS Page 22 i
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_ QUESTION A.19 (1.50)
Match each parameter listed below with its Technical Specification Limit.
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. a.
0.1 % delta k/k
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0.3 % delta k/h.
i c.
0.4 % delta k/k K
2.-
reactivity. worth of pneumatic d.
0.6 % delta k/k~
L rabbit experiments
- e.. 1.7 % delta k/k i
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2.0 % delta k/h L
3.
total reactivity worth g.
3.0 % delta k/k p
of all experiments h.
4.0 % delta k/k j
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RX THEORY. THERMO_6 FAC OP CHARS Page 23 QUESTION A.20 (1.00) k'hich one of the following parameters is abnormal for steady state operations at 1.0 MW7 i
a.
primary flow :
500 gpm b,
pool temperature :
105 degrees T c.
pool level :
20 feet above core d.
Primary heat exchanger delta T :
15 degrees T h
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(***** END OF CATEGORY A *****)
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NORMAL /EMERG PROCEDURES 6 RAD CON Page 24 QUESTION B.01 (2.00)
Match each administrative responsibility listed below with the title of the individual responsible for its accomplishment.
(responses may be used more than once) f ADMINISTRATIVE RESPONSIBILITY 1.
approve reactor operations with the pulse rod in the core 2.
approve routine experiments 3.
approve design, facility, and procedure changes 4.
approve bypass of interlocks and insure removal of bypasses and jumpers TITLE OF INDIVIDUAL a.
reactor operator b,
designated senior reactor operator c.
associate director d.
reactor supervisor e,
reactor health physicist f.
chief of reactor maintenance
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(***** CATEGORY B CONTINUED ON NEXT PACS *****)
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NORMA 1/EMERG PROCEDURES 6 RAD CON Page 25 QUESTION B.02 (1.00)
Which one of the following individuals may close out red tagouts?
a, the person who completes the maintenance action b.
the reactor operator c.
the designated senior reactor operator d.
the reactor supervisor h
(***** CATEGORY B CONTINUED ON NEXT PAGE *****)
B.
NOPMA1.[EMERG PROCEDUR_ES 6 RAD CCN Page 26 4
QUESTION B.03 (1.00) k'hich one of the following it.dividuals is authorized to release irradiated materials to off campus userst
- a. associate director
- b. reactor supervisor
- c. designated senior reactor operator
- d. reactor health physicist h
(***** CATECORY B CONTINUED ON NEXT PACE *****)
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NORMAL /EMERC PROCEDURES & RAD CON Page 2 r QUESTION B.04 (1.00)
Fill in the blanks with the title of the appropriate person.
A radiation work permit shall be initiated by _
and must be signed by before the work can begin.
i h
(***** CATEGORY B CONTINUED ON NEXT PAGE *****)
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B.
NORMAL /EMERG PROCEDURES 6 RAD CON Page 28 i
QUESTION B,05 (1.50)
What three conditions must be met in order to perform a short form startup checklist in lieu of a lone, fonn ?
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(***** CATEGORY B CONTINUED ON NEXT PAGE *****)
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Page 29
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. QUESTION B.06-(l'. 00)
Till in the blanks, i
I' A key on startup may be performed if the reactor keyswitch has been off for less than six hoursLfo11owing a successful operation, no i
+has been performed and a long form or short form startup checklist has been completed within
?
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NORMA 1./EMERG PROCEDURES 6 RAD CON Page 30 QUESTION B.07 (1.00)
An EC1' is required to be calculated in which one f the following cases?
a.
prior to all reactor startups b,
only prior to the first startup of t1 day onlypriortonormalreactorstartgs c.
d.
only prior to startups which requ te a long form startup checklist
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(***** CATEGORY B CONTINUED ON NEXT PAGE *****)
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NORMAL /EMERG PROCEDURES 6 P.AD CON Page 31 l
QUESTION B.08 (1.00)
Till in the blanks.
During a.1ormal reactor startup, if criticality occurs before the __
limit of the ECP or if the reactor is not critical by the limit the reactor should be shutdown.
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(***** CATEGORY B CONTINUED ON NEXT PAGE *****)
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B '. NORMAL /EMERG PROCEDURES 6 RAD CON Page'32 l
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QUESTION B.09 (1.00)
L, If the calculated SDM on a reactor startup is 500 pcm then t
a.
operations may proceed normally.
- 1..
b.
the DSRO's permission is required to continue operation c.
the reactor supervisor's permission is required to continue operation =
P d.
the reactor should be scrammed and the DSRO notified i-f.
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(***** CATEGORY B CONTINUED ON NEXT PAGE *****)
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B.
NORMAI./EMERG PROCEDURES 6 RAD CON Page 33 QUESTION B 10 (2,2$)
l List all the Reactor Operator's immediate actions for a reactor scram.
Include immediate actions if the expected response is not obtained, i,-
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(***** CATEGORY B CONTINUED ON NEXT PAGE *****)
i B.
NORMAL /EMERG PROCEDURES 6 RAD CON Page 34 l
f QUESTION B.11 (1.00)
The reactor startup immediately following an unscheduled reactor scram is classified as a a normal startup
- b. key on startup
- c. high residual startup
- d. scram recovery startup t
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(***** CATEGORY B CONTINUED ON NEXT PAGE *****)
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NORMAL /EMERG PROCEDURES T RAD CON Page 35 m
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. primary coolant leak.
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B.
NORMAL /EMERG PROCEDURES 6 RAD CON Page 36 i
QUESTION B.13 (1.00) 4 The 10 CFR part 20 permissible limit for whole body dose to a radiation worker during a calendar quarter is Rem.
a.
1.25 b.
7.5 c.
12.s d.
18.75 r
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(***** CATEGORY B CONTINUED ON NEXT PAGE *****)
l
B.
NORMAL /EMERC PROCEDURES & RAD CON Page 37 i
QUESTION B.14 (1.00)
A point source measuring 80 mr/hr of gamma radiation at one meter has been detected. Assume 100% detector efficiency for gamma radiation.
At what distanc( from the source will your oxposure be reduced to 20 nr/hr?
a.
2 meters b.
3 meters c.
4 meters d.
8 meters t
1 I
( ** * ** CA'I EGORY B CONTINUED ON NE.XT PAGE *****)
B.
NORMAL /EMERG PROCEDURES & RAD CON' Page 38 QUESTION B.15 (1.00)
An accessible area with a radiation level of 150 inr/hr would be classified as which one of the following?
a.
restricted area b.
radiation area c.
exclusion area M
(***** CATEGORY B CONTINUED ON NEXT PAGE *****)
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NORMAL /EMERG PROCEDURES & RAD CON Page 39 QUESTION B.16 (1.25) p List the four accident classes, as defined by the Emergency Plan, in order of severity from least severe to most severe, i
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(***** CATEGORY B CONTINUED ON NEXT PAGE *****)
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NORMAL /EMERG PROCEDURES 6 RAD CON Page 40 QUESTION B.17 (1.50)
Fill in the blanks.
The maximum whole body dose permitted at this facility during the following emergency actions is:
j a.
rescue of personnel (lifesaving) b.
performing assessment actions t-'
c.
providing first aid i
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(***** CATEGORY B CONTINUED ON NEXT PAGE *****)
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j 11. NORMAL /EMERG PROCEDURES 6 RAD CON Page 41 i
QUESTION B.18 (1,00)
Pill in the blanks, When rabbit experiments are to be inserted in the reactor, power shall be reduced at least 54 from the 1 MW 1evel to prevent from being exceeded due to 1
l
(***** CATEGORY B CONTINUED ON N12T PAGE *****)
s B.
NORMAL /DIERC PROCEDURES 6 RAD CON Page 42 QUESTION B.19 (1.00)
Fill in the blanks with the title of the appropriate person.
When irradiating samples with unknown or questionable renetivity values the must supervise the loading of the sample and the must be present in the control room during the approach to criticality.
(***** CATECORY B CONTINUED ON NEXT PACE *****)
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NORMAL /EMERG PROCEDURES 6 RAD CON ~
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B.20-
' (l'. 50)
List the three methods employed'to prevent inadvertant ejection of the-pulse _ rod when it is necessary.to operate with it in the core during fl?,
steady state operations, y
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- PIANT-AND RAD MONITORING SYSTEMS Page 44 f
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The ficaw rate of the primary system is varied by which one of the.
following methodr.?
- a.. adjusting the speed of the primary pump q_
b.
adjusting the orifice downstream of the flow straightenin6 tubes c.
adjusting the control signal from the flow transmitter d.
adjusting the position of the primary pump discharge valve
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PLANT AND RAD MONITORING SYSTEMS Page 45 QUESTION C.02 (1.00) k' hen switching from the forced convection mode to the natural convection mode the flapper valve is opened by which one of the following methods?
a, by an electro mechanical interlock activated when the primary pump is secured
- b. manually by raeans of a reach rod from the reactor bridge area
- c. manually using a switch on the reactor control console
- d. by gravity when the d/p across the flapper valve is lost i
I
(***** CATEGORY C CONTINUED ON NEXT PAGE *****)
m.
7 C.
PLANT AND RAD MONITORING SYSTEMS Page 46 7
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QUESTION C.03 (1.00)
Fill in the blanks.
The delay tank is designed to provide approximately of delay time for approximately nine half lives decay of N 16 generated by the neutron activation of in the primary coolant water as it flows through the reactor core,
(***** CATEGORY C CONTINUED ON NEXT PAGE *****)
C.
PIANT AND RAD MONITORING SYSTEMS Page 47 QUESTION C.04 (1.00)
Which one of the following automatic actions wilf occur if the secondary i
pump suction header temperature is low?
a.
The cooling tower blowers will secure b.
The three way mixing valve will repop ition.
c.
The cooling tower basin heaters will energize.
d.
The cooling tower spray control va'Ive will shut.
/
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(***** CATECORY C CONTINUED ON NEXT PACE *****)
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PLANT AND RAD MONITORING SYSTEMS
.Page 48 t
QUESTION
.C.05 (1.00)
Fill in the blanks.
-In the event of a tube leak _in the primary to secondary heat exchanger with both systems operating, the higher pressure in the system will leak in to the '
system.
i.
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(***** CATECORY C CONTINUED ON NEXT PAGE *****)
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C.
PLANT AND RAD MONITORING SYSTEMS Page 49 QUESTION C.06 (1.00) k'hich one of the following methods is used for adding nitric acid or ammonia to adjust primary pH?
a.
the chemical tank and pump b.
adding it directly to the pool water c.
the sampling connection in the purification system d.
adding it directly to the make up water in the balance tank h
(***** CATECORY C CONTINUED ON NEXT PAGE *****)
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On a;1ossiof commercial power the reactor control console power 1
s.
is automatica11y' supplied by battery systems.
b.7 is automatically supplied by the auxiliary generator' after it: automatically starts c.
is automatically supplied by the auxiliary. generator after the operator-starts it 1
e is capable of being powered from the. auxiliary generator if 1
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it is manually-selected l
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PLANT AND RAD MONITORING SYSTEMS Page $1 QUESTION C.08 (2.00)-
Match the radiation monitors in column A with the detector type in column B. (Column B responses may be used more than once)
L
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B 1,
control room
- a. ion chamber
- b. proportional counter 2.
hand and foot c, gamma scintillator
- d. beta scintillator 3.
stack particulate
- e. G.M. tube
- f. compensated ion chamber 4.
primary demineralizer W
(***** CATEGORY C CONTINUED ON NEXT PAGE *****)
m C.
PLANT AND RAD MONITORING SYSTEMS Page 52 QUESTION C.09 (1.00)
Which one of the following methods is used to remove the gamma signal from the neutron signal in the Log N Channel?
a.
The outer chamber prevents gammas from ionizing the inner
- chamber, b.
Inner chamber current cancels out gamma current in the outer i
- chamber, c.
A pulse height discriminator does not allow the gamma signals to be counted.
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Squaring the combined signal makes the gamma contribution insignificant.
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(***** CATEGORY C CONTINUED ON NEXT PAGE *****)
1.
C, PLANT AND RAD MONITORING SYSTEMS Page 53 QUESTION C.10 (1.00)
Which one of the following reactions is used for neutron detection in the startup channel detector?
a.
Neutron + Boron 10 - > Lithium 7 Ion + Helium 4 Ion b.
Neutron + Nitrogen-16
-> Nitrogen 17 + Camma c.
Neutron + Fluorine 19 - > Nitrogen 15 Ion + Helium 4 Ion d.
Neutron + Uranium 235 ---> 2 Fission Fragment Ions h
(***** CATEGORY C CONTINUED ON NEXT PAGE *****)
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PLANT AND RAD MONITORING SYSTEMS Page 54
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.a QUESTION C.11
-(1.00)
A reading of 25 mr/hr on the control room radiation monitor will cause which one of the following to occur?
a.
" Radiation. Alert" annunciation b,
evacuation but not confinement c.
evacuation and confinement d.
confinement and reactor scram 1
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'C.
PLANT AND' RAD MONITORING SYSTEMS Page.55 d
,4 QUESTION
'O.12 (1.00)
Which one of the following radiation n<onitors is automatically bypassed during reactor pulsing?
a.
over the pool monitor b.
control room area monitor c, ' particulate monitor d.
west wall area monitor 1
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(***** CATEGORY C CONTINUED ON NEXT PAGE *****)
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C.
PIANT AND RAD MONITORING SYSTEMS Page 56 QUESTION C.13 (1,00)
When the initiating condition is cleared, how are evacuation and confinement reset?
a, automatically b,
manually using a key c.
manually by placing the confinement fans in standby do manually by pressing the alarm reset button on the radiation alarm panel
(***** CATEGORY C CONTINUED ON NEXT PAGE *****)
f.'.
C ',
PLANT AND RAD MONITORING SY?TEMS Page 57 QUESTION C,14 (1.00)
Banked control rods refers to which one of the following?
a.
The rod drive motors for safety 1 and safety 2 are electrically coupled and produce simultaneous equal movement of both rods, b.
The rod drive motors for safety 1, safety 2, and the regulating rod are electrically coupled and produce simultaneous equal movement of all three rods, The physical position of safety 1 and safety 2 are identical, c.
d.
The physical position of safety 1, safety 2, and the regulating rod are identical, 7
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. QUESTION' C.16 (1.50)
E List the three conditions which must be met for the magnet power supply to be energized, f
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PLANT AND RAD MONITORING SYSTEMS Page 60 w
QUESTION C.17 (1.00)
List the_.two input channels to the scram logic unit which are automatically
. bypassed during pulsing operations.
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PIANT AND RAD' MONITORING SYSTEMS Page 61 6-
' QUESTION
_C.18 (0,50) e Fill'in the blank.
The absence of the +12 volts ("0" logic level).at any input channel of the scram logic unit is by definition a.
- to the logic, 1
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PLANT AND RAD MONITORING SYSTEMS Page 62 l
QUESTION C.19 (3.00)
Match each condition listed below with the primary signal it provides.
(responses may be used more than once)
CONDITION SIGNAL 1.
startup power level < 2 cps
- a. scram
- b. alarm 2.
linear channel reading 1.2 MW-
- c. ciert
- d. reverse drive 3.
flapper open at 100 KW e.
inhibit
- f. evacuation 4
resistivity reading 400 kohm/cm
- g. no signal provided.
5.
primary flow 450 gpm at 175 KW 6.,
over the pool monitor reading 25 mr/hr
(***** CATEGORY C CONTINUED ON NEXT PAGE *****)
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'Pl. ANT'AND' RAD MONITORING. SYSTEMS Page 63' L4 s;
QUESTION C.20 (1.00) g Tho'most reliable check on power level of the reactor, assuming a constant primary coolant flow, is the.
a.
. Log N channel b.
Linear Power channel c.
Safety Power channel d.
N 16 channel i
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(***** END OF CATEGORY C *****)
(********** END OF EXAMINATION **w*******)
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. ANSWER A.01 (1.00)-
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REFERENCE.
I' DPC' Fund, of Nuc. Eng. (p. 47)
ANSWER A.02 (2.00)
- 1. F 2, D
- 3. A
- 4. B REFERENCE DPC, Fund of Nuc. Eng.
(p.305)
ANSWER A.03 (1.00) b.
a REFERENCE l
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(p.65) q 1
ANSWER A.04 (1.00) i A.
REFERENCE DPC, Fund. of Nuc. Eng.
(p.74)
ANSWER A.05 (1.00) b.
(***** CATEGORY A CONTINUED ON NEXT PACE *****)
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REFERENCE:
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ANSWER A.09 (1.00)
C.
REFERENCE DPC.' Fund, of Nuc. Eng.
(p.121)
ANSWER A.10 (1.00) decay (0,5) burn up (0.5)
(***** CATEGORY A CONTINUED ON NEXT PAGE *****)
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'RX THEORY. THERMO & FAC OP CHARS Pcgo 66 y
REFERENCE gH DPC,' Fund. of Nuc. Eng.'(p.160)
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REFERENCE' I
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ANSWER A.15 (1.00) 7 C.
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RX THEORY, THERMO & FAC OP CHARS Page 67 i
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ANSWER-A.16 (1.00) d.
REFERENCE p
ANSWER A.17 (1.00) a.
REFERENCE I
NCSU FOM (p.1-7)
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(p.14)
ANSWER A.20 (1.00) d.
(***** CATEGORY A CONTINUED ON NEXT PAGE *****)
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4 B.- NORMAL /EMERG PROCEDURES & RAD CON Page 69--
ANSWER B 01 (2,00) 1.
b 2.- d or e 3.
c 4.
b REFERENCE NCSU POM table 2 1 ; k,%\\fw Rcube @'4.h
' ANSWER B.02 (1.00) d.
REFERENCE NCSU POM (p.2 18)
ANSWER B.03 (1.00) d.
REFERENCE NCSU POM (p.2-27)
ANSWER B.04 (1.00) reactor health physicist (0,5) reactor supervisor (0,5) 3 or Rom or RW or Pnm i-(kry A IL.je
~A2FERENCE NCSU POM (p.2-22)
ANSWER B.05 (1.50) shutdown less than 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> (0,5) instrumentation performed satisfactorily during last operation (0.5) less than 7 days since last long form checklist was completed (0,5)
(***** CATEGORY B CONTINUED ON NEXT PACE *****)
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NORMAL /EMERC PROCEDURES & RAD CON Page 70 4
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.d NCSU POM:(p.3 2)
ANSWER ~
B 06 (1.00) reactor safety! system maintenance (0.5) i, 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> (0,5)
~
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{
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.+200 pcm (0,5)
REFERENCE.
NCSU POM-(p.3-33)
.i ANSWER.
B.09 (1.00)
~b.
REFERENCE
.tlCSU POM (p.3-36)
(***** CATEGORY B CONTINUED ON NEXT PACE *****)
.c B.
NORMAL /EMERG PROCEDURES & RAD CON Page 71 ANSWER B.10 (2.25) 1.
Verify rods " seated" (0.25) and "off magnet" (0.25) lights are on.
If rods are not seated, initiate manual scram or turn off keyswitch (0.25) 2.
Insure prompt power drop has occurred (0.25) and power level is decreasing (0.25)-
3.
Insure follow on reverse action of rod position indicators (0.25),
if not turned ganged insert switch to on (0.25) 4.
Inform DSRO (0.25) 5.
Make log entries (0.25)
REFERENCE NCSU POM (p.3-51) i Of i) & d ANSWER B.11 (1
C.
REFEREN i
SU POM (p.3 53) l ANSWER B.12 (2.00) i i
1.
secure the reactor (0.5).
2.
stop the primary pump (0,5) 3.
notify the DSRO (0.5) 4.
attempt to locate and isolate the leak while maintaining (0.5) water over the core by any available means 1
i-REFERENCE i
NCSU POM (p.3-52)
ANSWER B.13 (1.00)
I l
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B.
NORMAL /EMERG PROCEDURES & RAD CON
.Pago 72-
^ REFERENCE-10 CFR 20.101 ANSWER B.14 (1.00)
.a.
REFERENCE NCSU Pulstar Health-Physics Procedures HP30 2 (p.2)
ANSWER B.15
-(1.00)
C.
REFERENCE-NCSU.POM (p.2 20)
ANSWER' B.16 (1.25)
'1. Notification of Unusual Events (0.25)
- 2. Alert,(0.25)
- 3. Site-Area' Emergency (0.25)
- 4. General Emergency (0.25)
-(0.25 for correct order)
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REFERENCE NCSU Pulstar Emergency Plan (p.10)
ANSWER B.17 (1.50) a.
25 R b.
3R
- c. 0.5 R REFERENCE'
-NCSU Pulstar Emergency Procedure 1.0 (p.7)
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NORMAL /EMERC PROCEDURES & RAD C0!!
Page 73 o
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P ANSWER B.18 (1.00) i reverce or scram setpoints (0.5)-
[
prompt power increase ~ (0.5) l t
REFERENCE NCSU POM (p.3 43)
ANSWER B.19 (1.00) r il Reactor Supervisor (0.5)
DSRO (0.5)
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REFERENCE R % re. k.) l NCSU'POM (p;9 19) ; rs 3
t ANSWER.
B.20 (1.50)
,1.
inlet, outlet and bypass valves for.the pulse air supply regulator will be closed -(0.5) 2.
'a vent a* the pulse accumulator will be open to prevent any pressurizing of the accumulator (0,5) 3.
a section of the air line between the pulse accumulator and the solenoid valve will be physically removed (0.5)
REFERENCE NCSU POM (p.3 44) i i
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PIANT AND RAD MONITORINu SYSTEMS' Page 74
.jp ANSWER l C 01 (1.00) d.-
REFERENCE NCSU POM-(p.5 2)
ANSWER C.02 (1.00) d.
REFERENCE NCSU POM (p.5 3)
ANSWER-C.03 (1.00) one minute (0.5) oxygen (0.5)
REFERENCE-NCSU POM- (p.5-5)
ANSWER C 04 (1
).
%Md b.
REFERENC U POM (p. 5-16)
ANSWER C.05 (1.00) secondary (0.5) primary (0.5)
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PLANT AND RAD MONITORINC SYSTEMS =
Page 75 REFERENCE 5
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. NCSU POM (p.5 6)
ANSWER C 06 (1.00) b.
REFERENCE NCSU POM (p.5 21)
-ANSWER C 07 (1.00) d.
REFERENCE NCSU POM (p.6 6)
ANSWER C.08 (2.00) 1.
a 2.
e 3.
d 4.
a REFERENCE NCSU POM (p.7-3,7-6)
ANSWER C 09 (1.00) b.
y REFERENCE-NCSU POM (p.4-5)
(***** CATECORY C CONTINUED ON NEXT PACE *****)
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ANSWER C.14 (1.00) d.
-a REFERENCE c
(***** CATECORY C CONTINUED ON NEXT PACE *****)
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PLANT AND RAD MONITORING SYSTEMS-Page 77
' ANSWER 1C.15 (2,00)
- 1. Mode selector in " steady state" position (0.5)
- 2. No manual operation of the ganged drive switch (0,5)
- 3. Servo error (deviation).is less than +/ 0.5%
(0,5)
- 4. The regulating rod is withdrawn beyond the 13.5 inch position (0.5)
REFERENCE NCSU POM (p.4 21)
ANSWER C.16 (1.50) l '.
" reactor on" keyswitch on (0.5) 2.
" power" circuit breaker on the reactor control console is not tripped (0,5) 3.
120 V electrical power is available (0,5)
REFERENCE NCSU Pom (p.4 17)
ANSWER C.17.
(1.00) 1.
safety power channel (0,5) 2.
linear power channel (0,5)
REFERENCE NCSU POM (p.4-18)
ANSVER.
C.18 (0.50) scram demand (0,5) g REFERENCE NCSU POM (p.4 17)
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TEST CROSS REFERENCE Page 1 QUESTION _VALUE REFERENCE A.01 1.00 9000205 I
A.02 2.00 9000206 L
A.03 1.00 9000207 A.04 1.00 9000208 A 05 1.00 9000209 A 06 1.00 9000210 A.07 1.00 9000211 A.08 1.00 9000212 A.09 1.00 9000213 A.10 1.00 9000214 A.11 1.00 9000215 A.12 1.00 9000216 i
A.13 1.09 9000217 A.14 1.00 9000218 A.15 1.00 9000219 A.16 1.00 9000220 A.17 1.00 9000221 A.18 1.00 9000222 A.19 1.50 9000223 A.20 1.00 9000224
+
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- l' ENCLOSURE 3 04 DEC 1989 USNRC MR RICH LAUPER ROOM 10C21 11555 ROCKVILLE PIKE ROCKVILLE, MD. 28052
SUBJECT:
REVIEW OF WRITTEN EXAMINATION FOR REACTOR OPERATORS, NCSU PULSTAR 89/11/27 MR LAUPER:
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ENCLOSED IS OUR " REVIEW OF WRITTEN EXAMINATION" DOCUMENT FOR THE REACTOR OPERATOR EXAM HELD AT THE PULSTAR FACILITY ON 27 NOV 1989.
PLEASE ADVISE IF.THERE ARE ANY QUESTIONS.
SINCERELY, han 0. ]Y GARRY D. MILLER ASSOCIATE DIRECTOR NUCLEAR REACTOR PROGRAM GDM:smg ATTACR(ENTS cc T:C. BRAY S.M. GRADY l
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RX THEORY. THERMO & PAC OP CitARS Page 15 (4,
QUESTION A.12 (1.00)
Which one of the following conditions is most appropriate for announcing that the reactor is critical during a reactor startup?
No control rod notion, stable zero SUR, stable source range count j
a.
rate.
b.
No control rod notion, stable positive SUR, increasing source range count rate.
c.
No control rod notion, stable zero SUR, increasing source range count rate.
d.
Controi rod notion, stable positive SUR, increasing source range count rate, b.
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(***** CATEGORY A CONTINUED ON NEXT PAGE *****)
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i B.
NOPMAL/EMERG_ PROCEDURES & RAD CON Page 24 1
4, QUESTION B.01 (2.00)
Match each administrative respc.nsibility listed below with the title of the individual responsible for its accomplishment.
(responses may be used more than once)
ADMINISTRATIVE RESPONSIBILITY 1.
approve reactor operations with the pulse rod in the core i
2.
approve routine experiments 3.
approve design, facility, and procedure changes 4.
approve bypass of interlocks and insure removal of bypasses and jumpers TITLE OF INDIVIDUAL a.
reactor operator b.
designated senior reactor operator c.
associate director d.
reactor supervisor e,
reactor health physicist f.
chief of reactor maintenance f
1.
b 2.
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NRP OPN 3 Redsion 8. March 19BS REQUEST FOR REACTOR OPERATION The saperimenter should complete allspaces whhin the bar and should indicate NA when not applicable.
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EXPERIMENT DETAILS 1.
Experimenter Name/ Agency:
Phone #:
2.
Requested date of experiment:
Requested time:
3.
Experiment title:
4.
PULSTAR Project #:
5.
Signature of Project approved Faculty / Staff:
TOR EXPERIMENTS INVOLt1NG ONLY OPERA TION OF THE RE4 CTOR, PROVIDE THE SPECITICS UNDER ITEM #6, FOR EXPERIMEN75 JNVOL11NG IRRADIA TION OF MA TERIA13 (INCLUDING DETECTORS OR DEYlCES PLA CED IN NEUTRON TLUX), COMPLETE ITEMS 97 THROUGH #1.1.
6.
Specify reactor operating conditions ter;uested:
7.
Target material description:
8.
Encapsulation description:
9.
Destination ofirradiated materials:
On NCSU Campus Buildina Room No.
Off NCSU Campus 1 Irr'adiation detalls:
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- 11. Sample decay time for Estimated Dose Rote noted in #10 above:
- 12. Estimated irradiation container dose rate (mR/hr at 1 ft) at unloading:
- 13. Additional PRECAUTIONS:
l PULSTAR STAFF APPROVALS 14, Associate Director / Reactor Operations Manager approval:
Date:
- 15. Experiment classification: Not Applicable Routine Hi Wonh-Unknown
- 16. Reactor Health Physics approval:
Date:
y RADIOACTIVE MATERIAL RELEASE DETAILS
- 17. Minimum authority level required to release irradiated material (specified by HP):
- 18. Signature of individual receiving irradiated material:
Date:
- 19. Signature of StVI acknowledging irradiated material transfer:
Date:
PULSTAR REACTOR RUN STATISTICS (completed by licensed staff as required)
Erperiment Number:.
Date:
Ston/Stop:
z.
Operating Hours:
TullPower Hours:
Total Uses:
Use:
Control #:
Scheduled:
Reactor Operator (s):
Status:
.I INSTRUCTIONS J.
rrnedmonter Name/Acenev. Person requesting me of the PULSTAR Reacttr (responsible facuhy, studelt,or staff memter.) Enter NE course number,off. campus ageney, etc. m neccuary, 2.
Resurrred dare of ameriment/Resuested time. Desired date and time erperiment or irradiation is to begin. If bour of the any is not crucial, Indicate AM or FM in the Reguested 7ime blank.
<i 3.
rsnedment rirle. Name and description of experiment, for cumple, NAA, Isotope Production, f(
Control Rod Calibration, Heat Balance, etc.
d.
PULSTAR Nirer #. Experimental project approval number malgned by the Radiation Protection Council (RPC) authorizing the experiment requemd.
3 Sicnature of Nirer Ann owd roeirfrv/sraw. IndMdual who signs accepts responsibility for and certifies that tbc experiment will meet all conditions and requirements detailed in the PULSTAR Project and
- REQUEST FOR REACTOR OPERA 110N' run sheet. Tbc indiddual must be samed in the PULSTAR Project as amended.
4 specify waetor onerations conditions,cau,st,d. Use this space to indicate conditions cuential to the esperiment including. but not limited to: power limitations, tpecial equipment, unusual prsaautions, auistance provided by the PULSTAR Sta!!, initial conditions for the reactor, etc.
7.
romer moredal desedprion. Ducribe material pbysical composition, state, and weight. Also specify off.ganing, fluion products, etc. as pertinent.
raconnitation d,sednrion. Ducribe container (s) and sealing proccu. See Health Physics Procedure HP 40 2 on encapsulation.
9.
Destination of inediated materials. Specify lacation, jl
- 10. Irradiation details t foiwr LewI. Specify in watts (W), kilowatts (kW), or megawatts (MW).
Durotion
!pecify how long in minutes, hours, or days.
Facility. T2 instance, REP positions W, X, Y or Z; Beam Tube (BT), Pneumatic Rabblt, etc.
Holder #. Specify number of buket, etc.
- of Samples Specify quantity of distinct target (s).
Location (for AErs)
Specify quantity of distinct target bottles for REPS only.
Errimated ReactMry (pem). Specify quantity had sign (+/.) of expected re. activity.
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Errimated Sample Dose Rate. Specify for smalt enh usuming decay time as detailed under Item #11.
i Nessured Aeactivity (pcm). As measured by PULSTAR Operator, Irrediation Start Time. As recorded by PULSTAR Operator.
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l Irrodiation Stop 71me. As recorded by PULSTAR Operator.
Part Irradiation Storage Specify location, e.g., SR, pool, reactor bay hood, etc.
Measured Sample Dose Aare. As measured by urJoader; recorded by unloader or PULSTAR staff.
Unloaded by. Unionder's initials entered by either the indiddual or PULSTAR staff.
' } }.
Samnfo dreav rime for Estimated Dose Rate in dio abow etc.. Specify the amount of decay time neceuary to yield the estimated dose rates as recorded under leradiation Details, item #10._
- 12. Esrimored inadiation container dose rate (mR/hr at i frL etc.
Indicate estimated dose rate at time of sample material WW for Lbc specified amount of decay time.
- 13. Additional necesurions. Specify, for cumple, *DO NOT REMOVE FROM POOL FOR $ DAYS,' etc.
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- 14. Assoelate Dierefor/ Reactor Onerations Manecer anneval. This approval documents the Anociate Director / Reactor Operations Manager asseument of experiment for safety and compliance with Projed requirements. For further details, refer to the PULSTAR Operations Manual (POM) section 9.7.
13 Isne iment crossinearion. ere.. Routine Samples: 0 to 600 pcm HiWorth samples: 600 to 1000 pcm, Unknown Samples: unknown with respect to 1000 pcm. This is specified by AD/ ROM.
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.16 ~ Reactor Realth Phvries anaronel.LThis approval documents the verification of the experimenter's radiological cornpetency (for irtadiated materia 1 experiments) and includes a review of estimated
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activities, doserates, material destination, and uhlmate irradiated material disposition. The.
y RHP review also confirms authority by the PULSTAR Project to perform the experiment as proposed.
- 17. Authority lewt reattired to releast Irradiated material. The Heahh Physics staff specifies the minimum level of authority to release the sample, e.g., RO or AD/ ROM or RHP / RSO.
- 18. Sienansre of individital rectidne irradicted materini. Upon receipt of the irradiated material the receiving person will sign item W19. Note that this signature may be delayed as reasos. ably neceuary in order to maintain safe radiation practices during unloading and transfer to another location.This individual must meet the criteria for receiving irradiated material as described by the PULSTAD Operations Manual.
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- 19. Sienantre of PULSTAR StaW acknowledeine irradiated more'ial tmnsfer. Tbc statf (either operations or Heahh Physics) verifies the authority of the individual signing line # 19 to receive irradiated material.
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NORMAL /EMERC PROCEDURES 6 RAD CON Page 27 (L,
QUESTION B,04 (1.00)
Till in the blanks with the title of the appropriate person, A radiation work permit shall be initiated by and must be signed by before the work can begin.
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FORMAL /EMERG PROCEDURES 6 RAD CON Page 30 I
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QUESTION B.07 (1.00)
An ECP is required to be calculated in which one of the following cases?
a.
prior to all reactor startups b.
only prior to the first startup of the day c.
only prior to normal reactor startups d.
only prior to startups which require a long form startup checklist b<
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NORMAL /EMERC PROCEDURES & RAD CON Page 32 6
(/-.
QUESTION B.09 (1.00)
/
If the calculated SDM on a reactor startup is 500 pem then operations may proceed normally a.
b.
the DSRO's permission is required to continue operation c.
the reactor supervisor's permission is required to continue operation d.
the reactor should be scrammed and the DSRO notified b,
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NORMAL /EMERG PROCEDURES & RAD CON Page 34 I
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QUESTION B.11 (1.00)
The reactor startup immediately following an unscheduled ret.ctor scram is classified as a
- a. normal startup
- b. key on startup
- c. high residual startup
- d. scram recovery startup c..
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Be %/ V l (***** CATEGORY B CONTINUED ON NEXT PAGE *****) t i s 4 L B. NORMAL /EMERC PROCEDURES 6 RAD CON Page 42 f 6, ' QUESTION B.19 '(1.00) Till in the blanks with the title of the appropriate person. When irradiatirs samples with unknown or questionable reactivity values the must supervise the loading of the san:ple and the must be present in the control room during the approach to criticality. REn COR.. S u ('d W sSc(L 65(2o i (2.6 F: () o m 9 - 19 6. %w $ ty4cm Q t o.c.X c' O G N W WT00 T A w A,mve~a * % - }g (z g w h p 'a,a('as) = % Yero 9] E * ' Y "" 79 6. I-l c. (Lv F : rec Q e d A & J ~iw p3g l l l. l l l (***** CATEGORY B CONTINUED ON NEXT PAGE *****) I 1 t C. PLANT AND RAD MONITORING SYSTEMS p,g, 47 1 0, QUESTION C 04 (1.00) Which one of the following automatic actions will occur if the secondary pump suction header temperature is low? t l a. The cooling tower blowers will secure. b. The three way mixing valve will reposition. c. The cooling tower basin heaters will energize, d. The cooling tower spray control valve will shut, b, RE F: perm 0 S-16 6.. Om c_, 6 o& c. ce ormed. S.2.3.3 (>n 3-- e, s-pem S-i5 ase [ c yvs 6-Ib b-r $. 2., 3. 3 pus t pg g-j$ ~ c M4n M w % hn+%*y & h A* o hs~9 van JMV - on (***** CATEGORY C CONTINUED ON NEXT PAGE *****) }(.. t o I-C. PIANT AND RAD MONITORING SYSTEMS p,, 39 l (1,, QUESTION C.16 (1.50) 1.ist the three conditions which must be net for the magnet power supply to be energized. l. " M@v cw ' ' d M b es ~ S u iY.frw+$*n th. L m c'Qv 2 ' fr>vm ce>3;oA' s m & J > J T Q.D. l 10 V 0$Ackp%s%& & Q R E F.' 9a m PH-s9 hhM OM ( W no w as,u A usa 4-m) y. & &, 9 5 0 "-l 5 Aso-c,~ n e n ~.w ~ r~ ) il P " # h by, & V75 ym CD f+1 f% 3 (Pom 4-6 / Y-/4) (,. &ff: h O tY) Y ~l Q CJL Yr S' E ' l $" pem 4-G /bn V -/ ') [hegn QU~Ohbr" 0*l$ 1 l l (***** CATEGORY C CONTINUED ON NEXT PAGE *****) I l f, t,. l.- NRC RESOLUTION OF FACILITY COMMENTS RO Examination t Question A.12 NRC resolution: Comment noted. The candidates expressed some confusion i regarding the use of the term " critical" in the stem of the question during the examination period. The proctors resolved their confusion by instructing them to equate it with the " reactor approximately critical" terminology used in the NCSU operations manual. Question B.01 .NRC resolution: Comment accepted. Response (e) has been added to the answer key as an additional acceptable response to part (2) of this item. Question B,04 NRC resolution: Comment accepted. Any one of the following responses will be accepted as a correct answer to the second part of this question: Reactor Supervisor (Reactor Operations Manager), Reactor Health Physicist, or the person in charge of the job. Question B.07 NRC resolution: Comment partlally accepted. Because the question, as worded, has two technically correct answers (a is not a correct choice because an ECP is not the same as a mental reactivity balance) it has been deleted from the examination. Question B.09 NRC resolution: Comment noted. Question B.11 NRC resolution: Comment accepted. Because there was not sufficient information provided in the stem of the question to arrive at one correct answer, this question has been deleted from the examination. Question B.19 k NRC resolution: Comment accepted. The answer key has been changed to T replace the title of Reactor Supervisor with Reactor Operations Manager. Question C.04 NRC resolution: Comment accepted. Because the question has more than one correct answer it has been deleted from the examination. I Question C.16 NRC resolution: Comment not accepted. A review of the facility reference material confirmed that the three conditions stated in the original answer key must be met for the magnet power supply to be energized. While it was evident from the reference material that the two additional answers proposed by the facility would interrupt the flow of current to the scram magnets, it appeared that the magnet power supply would remain energized. In the absence of additional documentation, no change to the original answer key is warranted. 1. J