Nuclear instruments

Question 1

Which ONE of the following describes the purpose of the Excore Nuclear
Instrumentation System?
A Provides instrumentation to monitor the neutron flux of the reactor core.
B. Measure data used to evaluate the neutron flux distribution in the reactor core.
C. Measures data used to monitor the thermal margin of the reactor core.
D. Provides instrumentation to measure radial peaking factors

Answer 1

A Provides instrumentation to monitor the neutron flux of the reactor core.

Question 2

Which ONE of the following describes the purpose of the physical interface between
the Nuclear Instrumentation System and the Reactor Protection System?
A. Wide Range instruments provide input for the Variable High Power Trip, and
Source Range logarithmic instruments provide input for High Rate-of-Change Trip.
B.Power Range instruments provide input for the Variable High Power Trip, and Wide
Range logarithmic instruments provide input for High Rate-of-Change Trip.
C. Power Range instruments provide input for the Variable High Power Trip, and
Source Range logarithmic instruments provide input for High Rate-of-Change Trip.
D Wide Range instruments provide input for the Variable High Power Trip and provide
input for High Rate-of-Change Trip

Answer 2

B.Power Range instruments provide input for the Variable High Power Trip, and Wide
Range logarithmic instruments provide input for High Rate-of-Change Trip

Question 3

Which of the following lists the preferred power supplies for the indicated Nuclear Instruments?
NI-1 NI-2 NI-3 NI-4 NI-5 NI-6 NI-7 NI-8
A.Y10 Y20 Y30 Y40 Y30 Y40 Y30 Y40
B. Y40 Y30 Y40 Y30 Y10 Y20 Y10 Y20
C. Y30 Y40 Y30 Y40 Y10 Y20 Y30 Y40
D. Y10 Y20 Y30 Y40 Y10 Y20 Y30 Y40

Answer 3

C. Y30 Y40 Y30 Y40 Y10 Y20 Y30 Y40

Question 4

The plant is at 50% power.
Preferred AC Bus V-30 has de-energized due to a fault on the bus.
Which of the following describes the effect of the power loss on Reactor Protection
System?
A. Wide Range NI-3 and NI-4 and Power Range NI-5 are de-energized
B. Source Range NI-1 and NI-2 and Power Range NI-7 are de-energized
C. Source/Wide Range NI-1/3A and Power Range NI-7 are de-energized
D. Source/Wide Range NI-2/4A and Power Range NI-5 are de-energized

Answer 4

C. Source/Wide Range NI-1/3A and Power Range NI-7 are de-energized

Question 5

Which ONE of the following describes the indications for the Nuclear Instrumentation
System outside the Control Room?
A. NI 1, 2, 3, and 4 log indications are provided on C-33.
B. NI 1 and NI 3 log and rate indications are provided on C-33.
C. NI 2 and NI 4 log and rate indications are provided on C-150A.
D. NI 1 and NI 3 log and rate indications are provided on C-150A

Answer 5

D. NI 1 and NI 3 log and rate indications are provided on C-150A

Question 6

Which of the following describes the Rod Withdrawal Prohibit design feature?
CRDM withdrawal is prohibited on:
A 1/4 High Power Rate-of-Change Pre-trip or 2/4 Variable High Power Pre-trip.
B. 2/4 High Power Rate-of-Change Pre-trip or 1/4 Variable High Power Pre-trip.
C. 1/4 High Power Rate-of-Change Pre-trip or 1/4 Variable High Power Pre-trip.
D. 2/4 High Power Rate-of-Change Pre-trip or 2/4 Variable High Power Pre-trip.

Answer 6

A 1/4 High Power Rate-of-Change Pre-trip or 2/4 Variable High Power Pre-trip.

Question 7

While operating with reactor power above 15%, the power range safety channels:
A. enable the loss of load reactor trip signals.
B. enable the high power rate reactor trip signals.
C. generate loss of load reactor trip signals.
D. generate high power rate reactor trip signals.

Answer 7

A. enable the loss of load reactor trip signals.

Question 8

The plant is at 25% power.
Power is being raised at 3% per hour.
Which of the following conditions will result in the receipt of a Rod Withdrawal Prohibit
and its associated alarm, EK0917, Rod Withdrawal Prohibit?
A. One High Power Rate Pre-trip alarm
B. Two High Power Rate Pre-trip alarms
C. One Variable High Power Pre-trip alarm
D. Two Variable High Power Pre-trip alarms

Answer 8

D. Two Variable High Power Pre-trip alarms
A. Incorrect. Rate trips not active above 15 power.
B. Incorrect. Rate trips not active above 15 power.
C. Incorrect. Requires 2 of 4 logic. This distractor has only one.
D. Correct. Requires 2 of 4 logic.

Question 9

A plant critical approach is in progress in accordance with GOP-3: MODE 3 = 525°F
To MODE 2.
Which of the following indications would validate that the Nuclear Instrumentation (Nls)
was responding as expected?
A. NI-1 and NI-2 reading approximately 30 CPS and NI-3 and NI-4 reading
approximately 10-7% power. Wide Range indication is rising by approximately two
decades to every one decade rise in the Startup Range Nls.
B. NI-1 and NI-2 reading approximately 30 CPS and NI-3 and NI-4 reading
approximately 10-8% power. Wide Range indication is rising by approximately one
decade to every one decade rise in the Startup Range Nls.
C. NI-1 and NI-2 reading approximately 300 CPS and NI-3 and NI-4 reading
approximately 10-5% power. Wide Range indication is rising by approximately one
decade to every one decade rise in the Startup Range Nls.
D. NI-1 and NI-2 reading approximately 300 CPS and NI-3 and NI-4 reading
approximately 10-6% power. Wide Range indication is rising by approximately two
decades to every one decade rise in the Startup Range Nls.

Answer 9

C. NI-1 and NI-2 reading approximately 300 CPS and NI-3 and NI-4 reading
approximately 10-5% power. Wide Range indication is rising by approximately one
decade to every one decade rise in the Startup Range Nls.
c. CORRECT. The 300 CPS Start Up NI reading is two decades higher than the
information in GOP-3. Since a 300 CPS NI Start Up reading is two decades
higher than 3 CPS, then the Wide Range Nls would be expected to be reading
approximately 1x10-5%. Step 5.2.2 states that the Nls then should each raise at
the rate of approximately 1 decade each.

Question 10

What is the purpose of the Variable High Power Trip?
A. Protect the reactor from operating above 100% reactor power.
B, Limit transients starting at reduced power levels.
C. Remove protective features below 15% reactor power.
D Prevent reactor operation following a loss of forced flow

Answer 10

B, Limit transients starting at reduced power levels

Question 11

The Nuclear Instrumentation Channels at a setpoint of
A. Source Range trip the reactor
B. Wide Range bypass the rate-of-change power trip
2.6DPM

Answer 11

B. Wide Range bypass the rate-of-change power trip

2.6DPM

Question 12

The Source Range Nuclear Instrumentation Channels at _
A. trip the reactor
B. deenergize
C. disable ZPM Bypass
D. do not deenergize
A.a setpoint of 2.6 DPM
B.a setpoint of > 0.05 % power
C.a setpoint of

Answer 12

D. Do not denergize high power

Question 13

With the reactor at full power operation, which ONE of the following describes the
effects on the Reactor Protection System of losing Power Range NI-5 channel?
In addition to the Variable High Power trip, the following “A” Channel RPS reactor trips
become INOPERABLE:
A. TM/LP, Loss of Load, High Power Rate.
B. TM/LP, Loss of Load, High Flux Delta-T.
C. TM/LP, ATWS, High Power Rate.
D. Loss of Flow, Loss of Load, High Power Rate

Answer 13

A. TM/LP, Loss of Load, High Power Rate.

Question 14

Which ONE of the following Reactor Protection System functional units is affected by a loss of
SourceIWide Range NI-01/03A?
A. Variable High Power.
B. Thermal Margin/Low Pressure
C. High Startup Rate.
D. Loss of Load

Answer 14

C. High Startup Rate

Question 15

Which of the following Reactor Protection System trip units is affected by a loss of
SourcelWide Range NI-01/03A?
A. Variable High Power.
B. Low Flow
C. High Startup Rate.
D. TM/LP

Answer 15

C. High Startup Rate.

Question 16

Pressurizer Pressure Transmitter PT-01 02B failed low and no operator actions have
been taken. Then during normal 100% power operations, Nuclear Instrumentation (NI)
Channel NI-8 failed high. All other equipment performs as designed.
What procedure should the SRO be directing actions from immediately following the NI
channel failure?
A. Reactor Protective System and Anticipated Transient without Scram (ATWS)
System
SOP-36 to bypass the affected RPS trip function
B. Reactor Protective System and Anticipated Transient without Scram (ATWS)
System
SOP-36 to place the affected RPS trip function into a Tripped Condition.
C. Alarm and Response Procedure EK-0917 for alarm “Rod Withdrawl Prohibit”
D.Standard Post-Trip Actions EOP 1.0

Answer 16

D.Standard Post-Trip Actions EOP 1.0

Question 17

Which of the following describes the relationship between the Nuclear Instrumentation,
and Quadrant Power Tilt Monitoring?
A. The Wide Range instruments output is used to measure QPTR in the Thermal
Margin Monitor (TMM).
B. The Wide Range and Power Range instrument outputs are compared to each other
to determine any flux tilts.
C. The Power Range detector outputs are compared to the average of the four
detectors to determine quadrant power tilts and provide channel deviation alarms.
D. The Power Range Detectors provide for the Axial Shape Index (ASI) measurement
in the TMM, which is used to monitor quadrant power tilts.

Answer 17

C. The Power Range detector outputs are compared to the average of the four
detectors to determine quadrant power tilts and provide channel deviation alarms.

Question 18

How does fuel burnup impact operation of the Nuclear Instrumentation System?
Fuel burnup resulting in indicated power being _
than actual, provided no adjustments are made.
A. raises neutron flux at the outside of the core, higher.
B. lowers neutron flux at the outside the core, lower.
C. lowers neutron flux at the top half of the core, lower.
D. raises neutron flux at the inside the core, lower

Answer 18

A. raises neutron flux at the outside of the core, higher.

Question 19

Which ONE of the following identifies the redundant indication(s) used to validate
alarm EK-06C7, “DROPPED ROD?”
A. CRDM clutch power supply status.
B. Source Range Log and SUR indications.
C. Power Range Upper and Lower Detector indications.
D. Rod Withdrawal Prohibit Alarm.

Answer 19

C. Power Range Upper and Lower Detector indications.

Question 20

An ASI alarm will be annunciating for which one of the following conditions?
A. Core Power 40%, ASI +0.10
B. Core Power 40%, ASI -0.10
C. Core Power 100%, ASI +0.10
D. Core Power 100%, ASI -0.10

Answer 20

D. Core Power 100%, ASI -0.10
This question requires that the candidate have a basic understanding of the shape of
the Local Power Density Function that is the main input to the ASI alarm. The correct
answer can be reached by recognizing the that top core is more restrictive than bottom
core and that the LPD Function is more restrictive at high power.

Question 21

The plant is at 1E-5% power. Which of the following RPS trips are bypassed by placing
Zero Power Mode Bypass Switch in “BYPASS”?
A. Low RPS Flow
B. Low Steam Generator Level
C. High Start Up Rate
D. Variable High Power

Answer 21

A. Low RPS Flow
A. CORRECT. The Low RPS Flow, TM/LP and Low S/G Pressure (S/G1 and
S/G2) are bypassed by the ZPM Bypass key at >1E-4% power

Question 22

Which of the following describes the consequences of operating Nuclear
Instrumentation with an individual channel ASI not calibrated with the total core Axial
Offset as measured by the incore detectors?
A. An individual channel not calibrated reduces the redundancy but does not impact
operation of the plant.
B. An error may be present in the ASI channel, but the channel can still be considered
OPERABLE.
C.The affected channel is considered INOPERABLE and the actions of Technical
Specifications and ORM are taken.
D. All ASI channels are considered INOPERABLE and the plant must be shut down

Answer 22

C.The affected channel is considered INOPERABLE and the actions of Technical
Specifications and ORM are taken.

Question 23

An individual channel ASI has not been calibrated with the total core Axial Offset as
measured by the incore detector.
As a result, the reactor may not be operating per the safety analysis assumptions for:
A. loss of the offsite power.
B. Departure from Nucleate Boiling (DNB).
C. loss of forced circulation.
D. Linear Heat Rate (LHR).

Answer 23

D. Linear Heat Rate (LHR).

Question 24

The following plant conditions exist:
• Mode 1 at 98% power
• ‘A’ Channel neutron-flux delta-T comparator inoperable
Given the Operating Requirements Manual (ORM), determine which of the following
describes the operational limitations if Channel ‘0’ Power Range Instrument fails.
A. Power operation at current levels may be continued provided that Quadrant Power
Tilt Ratio is manually calculated every 12 hours.
B. Power operation at current levels may be continued; however, Excore Nuclear
Instrumentation cannot be used to monitor linear heat rate.
C. Power must be reduced to less than or equal to 50% rated thermal power within 12
hours.
D. Power must be reduced to less than or equal to 70% rated thermal power within 2
hours.

Answer 24

D. Power must be reduced to less than or equal to 70% rated thermal power within 2
hours

Question 25

(SRO only) Which of the following describes the ORM bases for the Excore Detector
Deviation Alarm?
Operability is required above:
A. 25% Rated Thermal Power (RTP) to continuously monitor Quadrant Power Tilt (Tq).
B. 15% RTP to continuously monitor Quadrant Power Tilt (Tq).
C. 25% RTP to continuously monitor radial flux tilt.
D. 15% RTP to continuously monitor radial flux tilt.

Answer 25

A. 25% Rated Thermal Power (RTP) to continuously monitor Quadrant Power Tilt (Tq).

Question 26

One Source Range detector becomes inoperable during mode 6 refueling; Refueling is
in progress.
Which of the following describes the IMMEDIATE action(s) required by Technical
Specifications?
A. Initiate action to restore the channel to operability.
B. Suspend all core alterations and positive reactivity additions.
C. Borate to 10% above the refueling boron concentration.
D. Install a temporary Source Range detector

Answer 26

B. Suspend all core alterations and positive reactivity additions.

Question 27

Source Range Channel 1A becomes inoperable during MODE 6 with refueling in
progress. Which one of the following describes the immediate action required by
Technical Specifications?
A. Initiate action to restore channel operability.
B. Suspend all core alterations and positive reactivity additions.
C. Perform an operabilty check of Source Range Channel 2A.
D. Suspend all core alterations and perform a Shutdown Margin Verification

Answer 27

B. Suspend all core alterations and positive reactivity additions
INCORRECT - Plausible because this action would be accomplished, however, it is not required by TS to be
performed immediately.
b. CORRECT
c. INCORRECT - Plausible if the student believes that only one channel is required to be operable during
refueling
d. INCORRECT - Plausible if the student confuses the actions required for one SRNI channel inoperable with two
SRNI channels inoperable.

Question 28

Given Technical Specifications, determine which one of the following activities would
be allowable in Mode 3 with BOTH Wide Range and ONE Source Nuclear
Instrumentation Channels INOPERABLE.
A. Control rod withdrawal.
B. Primary plant cooldown.
C. Dilution of Primary System with CVCS.
D. Boration of Primary System with CVCS

Answer 28

D. Boration of Primary System with CVCS

Question 29

(SRO only) The Technical Specification DNBR Core Safety Limits ensure that the
minimum DNBR is not less than the safety analysis limit AND,
A. to prevent the formation of voids anywhere in the reactor core.
B. ensure that fuel centerline temperature remains below melting.
C. maintain quadrant power tilt less than 10%.
D. to prevent nucleate boiling from occurring in the core

Answer 29

B. ensure that fuel centerline temperature remains below melting.

Question 30

During a Reactor Start-Up and while withidrawing shutdown rods both Source Range
Nuclear Instrumentation detectors are reading approximately 500 cps and neither
Wide Range Nuclear Instrumentation detector have moved off the 10-7% reading. The
Reactor Engineer has just informed you that he believes both WR Nuclear detectors
are not working properly. Given this information, what actions are you required to take?
A. Enter Tech Spec Action 3.0.3 IMMEDIATELY
B. Immediately discontinue the Start-Up and restore one Wide Range instrument
channel to OPERABLE status prior to MODE 2
C. Maintain power less than 10-4% with High Start-Up Rate Trips bypassed
D. Immediately discontinue the Start-Up and restore both Wide Range instrument
channels to OPERABLE status prior to MODE 2

Answer 30

D. Immediately discontinue the Start-Up and restore both Wide Range instrument
channels to OPERABLE status prior to MODE 2

Question 31

SOER 90-3, Nuclear Instrument Miscalibration, describes several operating
experiences related to operating with miscalibrated Nuclear Instruments.
Which of the following should be adopted as a lesson learned from these events?
A. Operators should not believe procedures are always correctly written for every
situation, and should always base their decisions on their own instincts and
experience.
B. Maintenance activities should always be considered precursors to operating
problems caused by technicians improperly following maintenance procedures, and
operators should expect problems will occur.
C. Effects on plant indications due to changes to fuel loading patterns cannot be
accurately accounted for by analysis and engineering principles, and operators
should use their own experience to guide their belief in indications.
D. Particularly after refueling outages, operators should have a healthy skepticism of
power indications and use alternate indications of power to validate nuclear
instrument power indications.

Answer 31

D. Particularly after refueling outages, operators should have a healthy skepticism of
power indications and use alternate indications of power to validate nuclear
instrument power indications.

Question 32

The plant is performing startup physics testing following a refueling outage with the
following conditions:
- ZPM Bypass has been established per SOP-36
Reactor power is currently at E-3% power and stable
Which ONE of the following will occur if Wide Range NI-03 loses power?
A. RPS Channels A and B ZPM Bypass will automatically enable
B. RPS Channels A and C ZPM Bypass will automatically enable
C. RPS Channels A and B ZPM Bypass will automatically clear
D. RPS Channels A and C ZPM Bypass will automatically clear

Answer 32

D. RPS Channels A and C ZPM Bypass will automatically clear

Question 33

Which one of the following describes the instrumentation that is normally used to
measure core Linear Heat Rate (LHR).
A. Excore Nuclear Instruments four Power Range Channels.
B. SPI Node in conjunction with the host computer for Palisades Plant computer.
C. Manual reading of Incore detectors.
D. Heat balance calculation of Palisades Plant Computer.

Answer 33

B. SPI Node in conjunction with the host computer for Palisades Plant computer.

Question 34

The reactor is at 98% reactor power, and both the SPI/Host computer and Excore
Nuclear Instrumentation are NOT available to monitor Linear Heat Rate (LHR).
How is LHR measured?
A. The heat balance calculation (PPC) is used to monitor LHR.
B. Manual heat balance calculation is used to monitor LHR.
C. LHR is measured by manually reading the incore detectors.
D. The Engineering Department approximates LHR using primary plant temperature
data.

Answer 34

C. LHR is measured by manually reading the incore detectors.

Question 35

Which of the following describes the operational characteristics of the Incore Rhodium
detectors for power supply, response time, and accuracy?
A. AC powered detectors, slow response time, and very accurate.
B. Self-powered detectors, fast response time, and very accurate.
C Self-powered detectors, slow response time, and very accurate.
D. DC powered detectors, slow response time, and fairly accurate

Answer 35

C Self-powered detectors, slow response time, and very accurate

Question 36

Which ONE of the following describes the operation of an Incore rhodium detector?
A. A neutron-beta reaction occurs in the self-powered rhodium detector, which
produces a current proportional to reactor power.
B. A neutron-alpha reaction occurs in the rhodium central electrode, which produces a
self-powered current proportional to reactor power.
C. Neutrons react directly with the rhodium lining of the detector to produce a current
proportional with reator power when energized with high voltage.
D. A neutron-beta reaction occurs in the rhodium lining of the detector, which produces
a self-powered current proportional to reactor power

Answer 36

A. A neutron-beta reaction occurs in the self-powered rhodium detector, which
produces a current proportional to reactor power

Question 37

A reactor start-up is in progress with reactor power increasing at a rate of 0.3 DPM.
The following instrument readings were observed.
Instruments
SR NI-1
SR NI-2
WR NI-3
WR NI-4
Readings
30CPS
35CPS
1 X 10-6% Power
2 X 10-7% Power
If 3 out 4 instruments are operating properly, based on the readings above, which of
the following statements is correct?
A. SR NI-1 indication is reading incorrectly and WR NI-3 is reading correctly.
B. SR NI-1 indication is reading correctly and WR NI-3 is reading incorrectly.
C. SR NI-2 indication is reading incorrectly and WR NI-4 is reading correctly.
D. SR NI-2 indication is reading correctly and WR NI-4 is reading incorrectly

Answer 37

D. SR NI-2 indication is reading correctly and WR NI-4 is reading incorrectly

Question 38

How is gamma and alpha discrimination accomplished in the Wide Range Nuclear
Instrumentation channels?
A. Pulse height discrimination is used throughout the entire measurement range.
B. The campbelling circuit provides for discrimination throughout the entire
measurement range.
C. Pulse height discrimination is used at low pulse rates, and campbelling is used
when the detector becomes saturated.
D. Campbelling is used at low pulse rates, and pulse height discrimination is used
when the detector becomes saturated.

Answer 38

C. Pulse height discrimination is used at low pulse rates, and campbelling is used
when the detector becomes saturated

Question 39

How are the Power Range detectors orientated radially and axially to the reactor core?
A. Radially, the detectors are about 900 apart; axially, they are aligned to center on the
centerline of the reactor core.
B. Radially, the detectors are about 900 apart; axially, they are aligned with the top of
the detectors even with the top of the reactor core.
C. Two detectors are installed at each of two locations, about 1800 apart and aligned
axially to center on the centerline of the reactor core.
D. Two detectors are installed at each of two locations, about 1800 apart and aligned
axially with the bottom of the detectors even with the bottom of the reactor core.

Answer 39

A. Radially, the detectors are about 900 apart; axially, they are aligned to center on the
centerline of the reactor core.

Question 40

Which of the Choices below best describe how the following items:
a. Lowering PCS temperatures
b. Core life (Core ages)
affect the Excore Nuclear Instrumentation readings assuming NO nuclear
instrumentation calibration is performed?
PCS temp lowers Rx Core Ages
A. Reads lower Reads higher
B. Reads lower Reads lower
C. Reads higher Reads higher
D. Reads higher Reads lower

Answer 40

A. Reads lower Reads higher
Correct. Excores read leakage neutrons which are proportional to reactor
power. As temperature lowers, the PCS becomes denser, less neutron leakage,
therefore the Nis read lower than actual unless calibrated. As the core ages, flux
more outward therefore there is more leakage and Nis read higher if not
calibrated

Question 41

In preparation for reactor startup from mode 5 with all conditions normal, SOP-35
“Neutron Monitoring System” Checklist CL 35 is being completed.
Which ONE of the following describes a consequence of failing to complete all sections
of CL 35?
A. The power range instruments may be improperly calibrated, which can invalidate
the Variable High Power reactor trip.
B. The power range instruments may be left disconnected, which would invalidate the
High Startup Rate reactor trip.
C.The trip output cable of a source/wide range channel may be left disconnected.
D. The power supply breakers for all nuclear instrument channels could be left open.

Answer 41

C.The trip output cable of a source/wide range channel may be left disconnected.

Question 42

SourceIWide Range NI-01/03A must be taken out of service.
Prior to removing NI-01/03A from service, which of the following conditions regarding the High
SUR Trip RPS channels would be acceptable? (Assume all other Technical Specification
requirements are met.)
RPS A RPS B RPS C RPS D
A. NORM B/P NORM TRIP
B. B/P NORM TRIP NORM
C. TRIP NORM NORM BYPASS
D. NORM TRIP B/P NORM

Answer 42

B. B/P NORM TRIP NORM

Question 43

Power Range Channel NI-07 must be taken out of service to perform a calibration.
In addition to the Variable High Power trip, which of the following Reactor Protection trips must
ALL be either placed in the tripped condition or bypassed? 
A. Low PCS flow
    TM/LP
    Loss of Load
B.  Low PCS flow
      Loss of load
      High Power Rate
C. TM/LP
     Loss of load
     High power rate
D. Low PCS flow
    TM/LP
    High Power Rate

Answer 43

C. TM/LP
Loss of load
High power rate

Question 44

A plant critical approach is in progress in accordance with GOP-3: MODE 3 = 525°F
To MODE 2.
Which of the following indications would validate that the Nuclear Instrumentation (Nls)
was responding as expected?
A.NI-1 and NI-2 reading approximately 30 CPS and NI-3 and NI-4 reading
approximately 10-7% power. Wide Range indication is rising by approximately two
decades to everyone decade rise in the Startup Range Nls.
B. NI-1 and NI-2 reading approximately 30 CPS and NI-3 and NI-4 reading
approximately 10-8% power. Wide Range indication is rising by approximately one
decade to every one decade rise in the Startup Range Nls.
C.NI-1 and NI-2 reading approximately 300 CPS and NI-3 and NI-4 reading
approximately 10-5% power. Wide Range indication is rising by approximately one
decade to every one decade rise in the Startup Range Nls.
D. NI-1 and NI-2 reading approximately 300 CPS and NI-3 and NI-4 reading
approximately 10-6% power. Wide Range indication is rising by approximately two
decades to everyone decade rise in the Startup Range Nls

Answer 44

C.NI-1 and NI-2 reading approximately 300 CPS and NI-3 and NI-4 reading
approximately 10-5% power. Wide Range indication is rising by approximately one
decade to every one decade rise in the Startup Range Nls.

Question 45

What is the purpose of the Variable High Power Trip?
A. Protects the Rx from opeating above 100% Rx Power
B. Limit transients starting at reduced power levels
C. Remove protective features below 15% Rx Power
D. Prevent Rx operation following a loss of forced flow.

Answer 45

B. Limit transients starting at reduced power levels