ML20057D192
| ML20057D192 | |
| Person / Time | |
|---|---|
| Site: | University of Maryland |
| Issue date: | 09/23/1993 |
| From: | Caldwell J, Isaac P Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20057C999 | List: |
| References | |
| 50-166-OL-93-02, 50-166-OL-93-2, NUDOCS 9310010237 | |
| Download: ML20057D192 (26) | |
Text
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ENCLOSURE 1 U. S. NUCLEAR REGU ATORY COMMISSION l
OPERATOR LICENSING INITIAL QAMINATION. REPORT REPORT NO.:
50-166/0L-93-02 FACILITY DOCKET NO.:
50-166 l
FACIl_ITY LICENSE NO.:
R-70 i
FACILITY:
University of Maryland EXAMINATION DATES:
September 9, 1993 EXAMINER:
Patricky. Isaac, (Chief Examiner) _
9!.2J SUBMITTED BY:
M dig' 3
r Exami
/
Da't e '
l Ihieb(er M
APPROVED BY:
J,es Caldwell, Chief Dade t n-Power Reactor Section perator Licensing Branch ivision of Reactor Controls and Human Factors Office of Nuclear Reactor Regulation
SUMMARY
A retake of section C of the written examination was administered to one Reactor Operator (RO) candidate.
The R0 passed the examination.
i i
i 9310010237 930924 I
PDR ADOCK 05000166 V
ppg
REPORT DETAILS 1.
Examiner:
Patrick J. Isaac, Chief Examiner 2.
Examination Results.
i R0 SR0 TOTAL (Pass / Fail)
(Pass / Fail)
(Pass / Fail)
NRC Grading:
1/0 0/0 1/0 l
f 3.
Written Examination:
The written examination was administered on September 9, 1993 to one Reactor Operator.
He passed the written examination.
The facilities written examination comments and the NRC's resolution to those comments are found in Enclosure 2.
I 4.
Operatina Tests:
i N/A 5.
Exit Meetina:
Personnel attending:
Dr. Walter Chappas, Director Vincent Adams, Rx Supervisor l
Patrick J. Isaac, NRC i
lhe exit meeting was conducted on September 6, 1993. The facility requested that question C-6 of the written examination be deleted due to the lack of a l
correct answer.
The NRC agreed.
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i ENCLOSURE 2 U. S. NUCLEAR REGULATORY COMMISSION NON-POWER REACTOR LICENSE EXAMINATION FACILITY:
University of Maryland REACTOR TYPE:
TRIGA DATE ADMINISTERED:
1993/09/09 REGION:
I i
CANDIDATE:
INSTRUCTIONS TO CANDIDATE:
Answers are to be written on the answer sheet provided. Attach.the answer sheets to the examination.
Points for each question are indicated in paren-theses for each question. A 70% is required to pass the examination.
Examinations will be picked up one (I) hour after the examination starts.
% OF CATEGORY % OF CANDIDATE'S CATEGORY VALUE TOTAL SCORE VALUE CATEGORY 21.00 100.00 C.
PLANT AND RADIATION MONITORING SYSTEMS 21.00 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 GUIDELINES FOR LICENSE EXAMINATIONS 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 u
the examination cover sheet.
- 6. Fill in the date on the cover sheet of the examination (if necessary).
- 7. Print your name in the upper right-hand corner of the first page of each section of your answer sheets.
I
- 8. Each question is worth one (1) point.
Partial credit will NOT be given.
- 9. If the intent of a question is unclear, ask questions of the examiner only.
1 C.
PLANT AND RAD MONITORING SYSTEMS Page 4 ANSWER SHEET Multiple Choice (Circle or X your choice)
If you change your answer, write your selection in the blank.
i MULTIPLE CH0 ICE 001 a
b c
d i
002 a
b c
d 003 a
b c
d i
004 a
b c
d 1
005 a
b c
d l
006 a
b c
d f
007 a
b c
d 008 a
b c
d 009 a
b c
d 010 a
b c
d 011 a
b c
d 012 a
b c
d 013 a
b c
d 014 a
b c
d 015 a
b c
d 016 a
b c
d 017 a
b c
d 018 a
b c
d i
019 a
b c
d i
1 020 a
b c
d i
i 021' a
b c
d i
(***** END OF CATEGORY C *****)
[
(********** END OF EXAMINATION **********)
}
t
Section C Plant and Rad MonitorinaSustems Page 5 l
- QUESTION (C.1)
Which ONE of the following is a Tech. Spec. at the University of Maryland TRIGA reactor that ensures that, in the event of a coolant piping rupture, the core remains covered by at least 15 ft of water.
j a.
The pool water inlet pipe is equipped with a siphon break at the surface I
of the pool.
b.
The pool water return (outlet) pipe shall not extend more than 20 ft above the active section of 'he core.
c.
The pool water outlet pipe is equipped with a siphon break at the surface of the pool.
d.
The pool water inlet pipe shall not extend more than 20 ft above the active section of the core.
- QUESTION (C.2)
During pre-startup checkout, the reactor operator lines up the makeup water system to add water to the pool and neglects to check the level later.
Overflow from the pool will go:
into the holdup tank in the water handling room sump through the pool a.
overflow piping.
b.
directly into the water handling room sump through the pool overflow piping.
into the city sewer system through the makeup water-secondary coolant c.
system cross-connection and the secondary coolant holdup tank.
d.
directly into the sewer system through the floor drain gratings around the base of the reactor.
I
i Section C Plant and Rad MoaitorinaSystems Page 6
- QUESTION (C.3)
All liquid waste is considered and treated as low level waste. Which one of I
the following statements correctly describes the procedure used at the MUTR to dispose of liquid waste?
When the sump is full, the sump pump automaticaliy transfers the liquid a.
waste to the sanitary sewer.
b.
When the sump is full, the sump pump is manually turned on to transfer the liquid waste to the sanitary sewer.
When the sump is full, it is sampled and if the activity is below c.
10CFR20 limits the liquid can be pumped to the sanitary sewer.
{
d.
When the sump is full, its content is pumped to the holdup tank.
The holdup tank water is pumped to the sanitary sewer if the activity level is below 10CFR20 limits.
- QUESTION (C.4)
What feature of the makeup water system prevents potential contamination of the city water supply system if activity levels of the pool water are high?
i a.
the radiation monitor in the system will alarm to alert the operator.
b.
the makeup water line check valve will provent backflow into the secondary coolant system.
c.
the pressure reducer in the makeup line will lower the static head of 3
the pool water to less than the city water pressure.
d.
the makeup demineralizer and filter will remove contamination in the coolant.
l t
Section C Plant and Rad MonitorinaSystems Page 7
[
'* QUESTION (C.5)
The instrumerted fuel element:
a.
has a higher fuel loading than a standard TRIGA fuel element so that it
[
will always be the highest temperature experienced in the core.
I b.
is secured at both the top and bottom of the fuel bundle to prevent instrument errors due to vibration.
c.
has three thermocouples embedded near the vertical center line of the fuel section.
d.
is required to be positioned in the core location with the peak neutron flux to be a conservative indicator.
t a
- QUESTION (C 6)
DELETED Which ONE of following statements concerning the Pool Level Monitor is FALSE?
I a.
The detector for the Pool Level monitor is a conductivity probe.
b.
The Pool level indication consists of an analog meter which indicate state of_comparator network, c.
The Pool Monitor indicates pool level in the Nuclear Engineering Program office.
d.
The Pool Monitor will alarm when it detects a difference In reading in air as compared to reading in water
i i
Section C Plant and Rad MonitorinaSystems Page 8
- QUESTION (C.7)
While attempting to pull rods for a Rx startup, the R0 realizes that the rods are not withdrawing. Which one of the following could be the cause of the rods not moving?
a.
Beam tube interlock bypass key switch is in " BYPASSED" b.
Beam tube interlock bypass amber light on the censole is illuminated.
c.
Beam tube cover is in place with the interlock bypass key switch off.
d.
Beam tube interlock bypass amber light on the console is not illuminated and the beam tube cover is not in place.
w t
- QUESTION (C.8) t Which ONE of the following statements regarding the MUTR ventilation system is FALSE 7 a.
Two air conditioners in the west laboratory will secure upon a manual actuation from any one of the Emergency Ventilation Shutdown locations.
b.
The safety function of the ventilation system is actuated by all reactor scrams.
c.
The safety function of the ventilation system is actuated when a substantial release of radioactivity is detected by the Exhaust air radiation monitor.
d.
An area radiation detector monitors the air exhaust from the east penthouse exhaust fan.
s
i Section C Plant and Rad MonitorinaSystems Page 9
- QUESTION (C.9)
I The fresh air supplies for the ventilation system are located:
a.
on the ground floor level on the west side of the building.
b.
at the top of the reactor room on the east side of the building.
c.
on the ground floor level beneath the control room.
d.
at the northwest and southeast corners of the penthouse walls.
L
- QUESTION (C.10)
If the diffuser was not in use what type of dose would increase?
a.
Beta b.
Alpha c.
Gamma d.
Neutron
'l
.1
Section C Plant end Rad MonitorinoSystems Page 10
- QUESTION (C.II)
Which one of the following statements does NOT decribe a control rod interlock?
a.
A low signal trip bistable on the log power level channel prevents the movement of all control rods in the down direction.
b.
In Automatic mode, a rod interlock prevents the operator from raising one other (shim) rod while the servoamplifer is raising the regulating rod.
c.
In Manual mode, activating the UP switch of any rod will prevent the other rods from being raised.
d.
An interlock is applied to the control rod switches when the log power channel test switch is turned on.
W
- QUESTION (C.12)
Which ONE of the following statements correctly describes the purpose of the PULL ROD in the control rod drive assembly?
a.
Provides rod full out position indication.
b.
Provides a means for manually adjusting rod position by pulling the rod out.
c.
Provides rod bottom indication.
d.
Automatically engages the control rod on a pull signal.
F t
b O
F
i Section C Plant and Red MonitorinaSystems Page 11 r
- QUESTION (C.13)
Which ONE of the following is NOT an input to the Regulating Rod Servo?
a.
Linear power channel b.
% demand potentiometer c.
Rod raising interlock d.
Period amplifier
[
i l
- QUESTION (C.14)
Which one of the following signals will NOT cause a Rx scram?
j a.
Exhaust Radiation monitor reads 30 mrem /hr.
b.
Bridge Radiation monitor reads 30 mrem /hr.
5 c.
High volt supply to the ion chamber is set at 70% of normal value d.
Water Room Radiation monitor reads 30 mrem /hr.
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'Section C Plant and Rad MonitorinaSystems Page 12
- QUESTION (C.15)
Which one the following statements describes the response of the reactor l
control system if the Reactor Power Range Switch were to be placed in the ZERO position with the reactor operating in the automatic mode.
P a.
The ZERO position on the range switch is not connected to any input and nothing would happen.
b.
The regulating rod will immediately begin inserting.
Reactor period will be limited to a 15 second period until the regulating rod is fully inserted.
c.
The regulating rod will withdraw which may cause a Safety Channel power scram.
i d.
The Linear Power Chart Recorder will indicate ZERO.
The Automatic
~
controller will shift control of the regulating rod to manual.
t i
- QUESTION (C.16) i Power is being raised in the automatic mode.
Desired power is 200 KW.
If the I
operator stopped ranging the Reactor Power Range Switch at 3 KW, which one of the following best describes where reactor power will level out?
a.
3 Kw i
b.
20 Kw f
c.
30 Kw d.
200 Kw t
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Section C Plant and Red MonitorinoSystems Page 13
- QUESTION (C.17)
I Which one of the following neutron detectors uses the LOG CAMPBELL TECHNIQUE l
to compensate for gammas?
l i
a.
Safety Channel I i
b.
Wide Range Log-Power Channel.
c.
Multirange Linear Channel
[
d.
Safety Channel II E
l i
l i
- QUESTION (C.18) t Which one of the following statements concerning the primary system is TRUE.
l a.
To prevent contamination of the pool water, the primary system is t
maintained at a higher pressure than the secondary system.
i b.
Twenty percent (20%) of primary flow passes through the demineralizer.
c.
The first heat exchanger has 5 times the heat removal capacity of the second heat exchanger.
d.
A temperature probe to monitor pool inlet temperature is mounted downstream of the second heat exchanger.
F Y
I I
i
.J
-Section C~ Plant and Rad MonitorinaSystems Page 14
- QUESTION' (C.19)
The reactor is at 100% power when the R0 inadvertently depresses the CONT /0N pushbutton for shim rod 1.
Five minutes later which one of the fol' awing represents the status of the indicating lights for shim 1 rod? -
-(Assume no other operator actions) a.
R0D UP LIGHT -
ON CONTACT LIGHT -
0FF DOWN LIGHT -
0FF i
MAGNET CURRENT LIGHT - ON b.
R0D UP LIGHT -
ON T.0NTACT LIGHT -
0FF i
DOWN LIGHT -
ON MAGNET CURRENT LIGHT - ON c.
R0D UP LIGHT -
0FF l
CONTACT LIGHT -
ON t
DOWN LIGHT -
ON i
MAGNET CURRENT LIGHT - 0FF d.
R0D UP LIGHT -
0FF CONTACT LIGHT -
ON l
DOWN LIGHT -
ON MAGNET CURRENT LIGHT - ON i
f
- QUESTION (C.20)
Which one of the following events would NOT result in a Rx scram, assuming I
that the reactor is at 250 KW and the regulating rod is in automatic?
(Assume no operator actions.)
a.
The fuel temperature thermocouple leads break.
b.
A calibration signal is sent to the pre-amp of the fission chamber power range detector circuit for safety channel 1.
k c.
The linear power channel compensated ion chamber loses all compensation.
i d.
High voltage is lost on the uncompensated ion chamber for Safety Channel i
2.
l t
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Section C Plant and Rad MonitorinaSystems Page 15 1
l
- QUESTION (C.21) l Which one of the following is a violation of procedures and/or technical specifications at the MUTR.
a.
The reactor is subcritical by $1.00 with the most reactive control rod withdrawn.
b.
The reactor is operating with one of the Bay Radiation Monitors inoperative.
c.
While operating at 100% power, the fuel element temperature channel increases to 300 degrees C.
d.
A recent calculation reveals that the mos't reactive control rod has a reactivity insertion rate of 50.32 per second.
(*** End of Se' tion C ***)
~
- QUESTION (C.1)
Which ONE of the following is a Tech. Spec. at the University of Maryland TRIGA reactor that ensures that, in the event of a coolant piping rupture, the core remains covered by at least 15 ft of water.
a.
The pool water inlet pipe is equipped with a siphon break at the surface of the pool.
b.
The pool water return (outlet) pipt shall not extend more than 20 ft above the active section of the core.
i c.
The pool water outlet pipe is equipped with a siphon break at the surface of the pool.
d.
The pool water inlet pipe shall not extend more than 20 ft above the active section of the core.
t
- ANSWER a
- REFERENCE T.S.
5.1 BASIS t
L
- QUESTION (C.2)
During pre-startup checkout, the reactor operator lines up the makeup water system to add water to the pool and neglects to check the level later.
Overflow from the pool will go:
into the holdup tank in the water handling room sump through the pool a.
overflow piping.
b.
directly into the water handling room sump through the pool overflow piping.
t c.
into the city sewer system through the makeup water-secondary coolant system cross-connection and the secondary coolant holdup tank.
d.
directly into the sewer system through the floor drain gratings around the base of the reactor.
- ANSWER a
- REFERENCE ENNU 320, Vol.2, Sect. 8.1 i
i
i
- QUESTION (C.3)
All liquid waste is considered and treated as low level waste.
Which one of the following statements correctly describes the procedure used at the MUTR to dispose of liquid waste?
a.
When the sump is full, the sump pump automatically transfers the liquid waste to the sanitary sewer.
b.
When the sump is full, the sump pump is manually turned on to transfer the liquid waste to the sanitary sewer.
c.
When the sump is full, it is sampled and if the activity is below 10CFR20 limits the liquid can be pumped to the sanitary sewer.
d.
When the sump is full, its content is r._.mped to the holdup tank.
The holdup tank water is pumped to the sanitary sewer if the activity level is below 10CFR20 limits.
- ANSWER C
- REFERENCE i
MUTR FSAR pg. 8-1
- QUESTION (C.4)
What feature of the mnkeup water system prevents potential contamination of the city water supply system if activity levels of the pool water are high?
the radiation monitor in the system will alarm to alert the operator.
a.
b.
the makeup water line check valve will prevent backflow into the secondary coolant system.
c.
the pressure reducer in the makeup line will lower the static head of the pool water to less than the city water pressure.
d.
the makeup demineralizer and filter will remove contamination in the coolant.
- ANSWER b
- REFERENCE ENNU 320, Vol.
2, Sect 4.3, Figures 4-3
9 L* QUESTION- (C.5)
The instrumented fuel element:
a.-
has a higher fuel loading than a standard TRIGA fuel element so that it will always be the highest temperature experienced in the core.
-b.
is secured at both the top and bottom of the fuel bundle to prevent instrument errors due to vibration.
c.
has three thermocouples embedded near the vertical center line of the-i fuel section.
t d.
is required to be positioned in the core location with the peak j
neutron flux to be a conservative indicator, f
- ANSWER i
C
- REFERENCE
{
ENNU 320, Sect. 3.1.2 and 3.1.4 1
- QUESTION (C.6)
DELETED i
Which ONE of following statements concerning the Pool Level Monitor is FALSE?
a.
The detector for the Pool Level monitor is a conductivity probe'.
b.
The Pool level indication consists of an analog meter which indicate state of comparator network.
c.
The Pool Monitor indicates pool level in the Nuclear Engineering Program office.
F d.
The Pool Monitor will alarm when it detects a difference in reading in
+
air as compared to reading in water
- ANSWER b
- REFERENCE Pre-exam visit I
t I
t I
t
oQUESTION (C.7)
While attempting to pull rods for a Rx startup, the RO realizes that the rods are not withdrawing.
Which one of the following could be the cause of f
the rods not moving?
a.
Beam tube interlock bypass key switch is in " BYPASSED" b.
Beam tube interlock bypass amber light on the console is illuminated.
c.
Beam tube cover is in place with the interlock bypass key switch off.
l d.
Beam tube interlock bypass amber light on the console is not illuminated and the beam tube cover is not in place.
CANSWER e
d oREFERENCE MUTR: FSAR p.
9-3.
i oQUESTION (C.8)
Which ONE of the following statements regarding the MUTR ventilation system is FALSE?
Two air conditioners in the west laboratory will secure upon a manual a.
actuation from any one of the Emergency Ventilation Shutdown locations.
b.
The safety function of the ventilation system is actuated by all reactor scrams.
i c.
The safety function of the ventilation system is actuated when a substantial release of radioactivity is detected by the Exhaust air radiation monitor.
d.
An area radiation detector monitors the air exhaust from the east penthouse exhaust fan.
l cANSWER I
l a
OREFERENCE i
MUTR FSAR pg. 2-2
{
e i
i h
l 4
I
i oQUESTION (C.9)
The fresh air supplies for the ventilation system are located:
i i
on the ground floor level on the west side of the building.
i a.
b.
at the top of the reactor room on the east side of the building.
c.
on the ground floor level beneath the control room.
l d.
at the northwest and southeast corners of the penthouse walls.
CANSWER a
OREFERENCE ENNU 320, VOL.
2, Sect.
2.2, Fig. 2-2
- QUESTION (C.10) i If the diffuser was not in use what type of dose would increase?
f a.
Beta b.
Alpha c.
Gamma l
d.
Neutron j
CANSWER c
CREFERENCE FSAR Sect. 7.5 pg. 7-2 i
l i
t i
^
- QUESTION (C.11)
Which one of the following statements does NOT decribe a control rod interlock?
A low signal trip bistable on the log power level channel prevents the a.
movement of all control rods in the down direction.
b.
In Automatic mode, a rod interlock prevents the operator from raising one other (shim) rod while the servoamplifer is raising the regulating rod.
In Manual mode,. activating the UP switch of any rod will prevent the c.
other rods from being raised.
i d.
An interlock is applied to the control rod. switches when the log power i
channel test switch is turned on.
I I
- ANSWER b
- REFERENCE MUTR: FSAR pg.
6-3.
- QUESTION (C.12)
Which ONE of the following statements correctly describes the purpose of the PULL ROD in the control rod drive assembly?
a.
Provides rod full out position indication, b.
Provides a means for manually adjusting rod position by pulling the
]
rod out.
c.
Provides rod bottom indication, d.
Au':omatically engages the control rod on a pull signal.
- ANSWER c
- REFERENCE FSAR pg 3-4 & Fig. 3-11B l
-1
- QUESTION (C.13)
Which ONE of the following is NOT an input to the Regulating Rod Servo?
n.
Linear power channel b.
% demand potentiometer c.
Rod raising interlock i
d.
Period amplifier
- ANSWER c
- REFERENCE MUTR: FSAR pg 6-9
- QUESTION (C.14)
Which one of the following signals will NOT cause a Rx scram?
i a.
Exhaust Radiation monitor reads 30 mrem /hr.
I b.
Bridge Radiation monitor reads 30 mrem /hr.
l l
c.
High volt supply to the ion chamber is set at 70% of normal /alue l
i d.
Water Room Radiation monitor reads 30 mrem /hr.
- ANSWER l
b
- REFERENCE MUTR: FSAR Table 6-1.
t i
l I
i I
i I
l
OQUESTION (C.15)
Which one the following statements describes the response of the reactor control system if the Reactor Power Range Switch were to be placed in the ZERO position with the reactor operating in the automatic mode.
a.
The ZERO position on the range switch is not connected to any input and nothing would happen.
b.
The regulating rod will immediately begin inserting.
Reactor period will be limited to a 15 second period until the regulating rod is fully inserted.
c.
The regulating rod will withdraw which may cause a Safety Channel power scram.
d.
The Linear Power Chart Recorder will indicate ZERO.
The Automatic controller will shift control of the regulating rod to manual.
t CANSWER c
0 REFERENCE MUTR: OP-104 pg 2, 5.
cQUESTION (C.16) s
?
Power is being raised in the automatic mode.
Desired power is 200 KW.
If
[
the operator stopped ranging the Reactor Power Range Switch at 3 KW, which one of the following best describes where reactor power will level out?
a.
3 Ks i
b.
20 Kw c.
30 Kw d.
200 Kw f
OANSWER b
+
- REFERENCE 2
MUTR: 1987 Exam & Fig. 6-5
?
I
[
)
i eQUESTION (C.17)
Which one of the following neutron detectors uses the LOG CAMPBELL TECHNIQUE to compensate for gammas?
a.
Safety Channel I b.
Wide Range Log-Power Channel.
c.
Multirange Linear Channel d.
Safety Channel II
- ANSWER b
- REFERENCE ENNU 320 Hanual Vol. II pg. 10-3
- QUESTION (C.18)
Which one of the following statements concerning the primary system is TRUE.
a.
To prevent contamination of the pool water, the primary system is maintained at a higher pressure than the secondary system.
b.
Twenty percent (20%) of primary flow passes through the demineralizer.
c.
The first heat exchanger has 5 times the heat removal capacity of the second heat exchanger, d.
A temperature probe to nonitor pool inlet temperature is mounted downstream of the second hent exchanger.
- ANSWER c
- REFERENCE FSAR pg. 4-1 & Fig. 4-1 i
i
- QUESTION (C.19)
The reactor is at 100% power when the RO inadvertently depresses the CONT /ON pushbutton for shim rod 1.
Five minutes later which one of the following represents the status of the indicating lights for shim 1 rod?
(Assume no other operator actions) a.
ROD UP LIGHT -
ON CONTACT LIGHT -
OFF DOWN LIGHT -
OFF MAGNET CURRENT LIGHT -
ON b.
ROD UP LIGHT -
ON CONTACT LIGHT -
OFF DOWN LIGHT -
ON MAGNET CURRENT LIGHT -
ON c.
ROD UP LIGHT -
OFF CONTACT LIGHT -
ON DOWN LIGHT -
ON MAGNET CURRENT LIGHT -
OFF d.
ROD UP LIGHT -
OFF CONTACT LIGHT -
ON DOWN LIGHT -
ON MAGNET CURRENT LIGHT -
ON
- ANSWER d
- REFERENCE MUTR FSAR pg.
6-7, 6-6 and fig. 6-6
- QUESTION (C.20)
Which one of the following events would NOT result in a Rx scram, assuming that the reactor is at 250 KW and the regulating rod is in automatic?
(Assume no operator actions.)
a.
The fuel temperature thermocouple leads break.
b.
A calibration signal is sent to the pre-amp of the fission chamber power range detector circuit for safety channel 1.
c.
The linear power channel compensated ion chamber loses all compensation.
d.
High voltage is lost on the uncompensated ion chamber for Safety Channel 2.
- ANSWER c
- REFERENCE SER, p 4-7, 7-3 L
- QUESTION (C.21)
Which one of the following is a violation of procedures and/or technical specifications at the MUTR.
a.
The reactor is subcritical by $1.00 with the most reactive control rod withdrawn.
b.
The reactor is operating with one of the Bay Radiation Monitors inoperative.
c.
While operating at 100% power, the fuel element temperature channel increases to 300 degrees C.
d.
A recent calculation reveals that the most reactive control rod has a reactivity insertion rate of $0.32 per second.
- ANSWER d
- REFERENCE
'MUTR TS
(*** End of Section C ***)
e
__ _