2010 SRO Flashcards Preview

NRC Initial exams > 2010 SRO > Flashcards

Flashcards in 2010 SRO Deck (25):
1

Given the following:
· The Plant trips due to a loss of all offsite power
· 2400 VAC Bus 1C is de-energized due to Diesel Generator (D/G) 1-1 failing to start
· An attempt to manually start D/G 1-1 was not successful
· 2400 VAC Bus 1D is energized from D/G 1-2
· During the transient, Y10, Preferred AC Bus, de-energizes
· The Control Room team is performing actions of EOP-1.0, "Standard Post Trip Actions"
Which one of the following procedures does EOP-1.0, Attachment 1, "Event Diagnostic Flow
Chart," direct the Control Room team to use for this event?
a. EOP-2.0, "Reactor Trip Recovery."
b. EOP-3.0, "Station Blackout Recovery."
c. EOP-8.0, "Loss of Offsite Power/Forced Circulation Recovery."
d. EOP-9.0, "Functional Recovery Procedure."

c. EOP-8.0, "Loss of Offsite Power/Forced Circulation Recovery."

a. Plausible because the student may think that since at least one 2400 VAC vital bus is energized that the recovery
procedure can be used.
b. Plausible because the student may think that since Bus 1C is de-energized that EOP-3.0 is appropriate.
c. CORRECT - With all forced PCS flow lost, power available to one 2400 VAC bus and 3 of 4 preferred AC buses,
EOP-8.0 is the correct procedure.
d. Plausible because of the loss of Y10, but two preferred AC buses must be lost before transitioning to the functional
recovery procedure.

2

Given the following with the Plant operating at full power:
• P-50A, Primary Coolant Pump (PCP) ammeter lowers to approximately 100 amps
• The reactor automatically trips approximately two seconds later
• All other PCPs remain operating normally
Which one of the following describes the cause of the P-50A failure and the procedure the
Control Room team will transition to after EOP-1.0, "Standard Post Trip Actions," are
complete?
a. P-50A shaft seized. EOP-8.0, "Loss of Offsite Power/Forced Circulation Recovery."
b. P-50A shaft seized. EOP-2.0, "Reactor Trip Recovery."
c. P-50A shaft sheared. EOP-8.0, "Loss of Offsite Power/Forced Circulation Recovery."
d. P-50A shaft sheared. EOP-2.0, "Reactor Trip Recovery."

d. P-50A shaft sheared. EOP-2.0, "Reactor Trip Recovery."

a. Plausible because amps are abnormal but amps will be higher than normal operating amps if the pump shaft seized.
b. Plausible because amps are abnormal but amps will be higher than normal operating amps if the pump shaft seized.
c. Plausible because one PCP is lost but EOP-8.0 entry is not required unless all 4 PCPs are not running.
d. CORRECT - PCP amps indicate the shaft sheared and since 3 other PCPs are in service, EOP-2.0 is the correct
procedure.

3

Given the following during a Plant heatup in MODE 3:
• The PCS is at normal operating pressure with TAVE at 500°F
• PIC-0101A, ‘A’ Pressurizer Pressure Controller, is out of service due to a controller
failure
• EK-0754, "PRESSURIZER PRESSURE OFF NORMAL HI-LO," annunciates
• The Reactor Operator observes the following for PIC-0101B, 'B' Pressurizer Pressure
Controller:

Shows PIC-0101B process and output failed low.
Which one of the following procedures will the Control Room team use to control Pressurizer
pressure for this event?
a. ONP-24.4, "Loss of Preferred AC Bus Y40."
b. ONP-18, "Pressurizer Pressure Control Malfunctions."
c. ONP-2.3, "Loss of DC Power."
d. SOP-1C, "Primary Coolant System - Heatup."

a. Plausible if the student believes that the affected controller is powered from Y40 - actually powered from Y20.
b. CORRECT - ONP-18 contains directs for manually controlling pressure because there are no controllers
available.
c. Plausible if the student believes that the controller is powered from a DC bus.
d. Plausible because this is the in use procedure but there is no direction for this condition.

4

Given the following:
• The Plant has entered EOP-7.0, ”Loss of All Feedwater Recovery”
• The Plant is also experiencing a loss of all instrument air
• P-8A and P-8B, Auxiliary Feedwater Pumps, are not available
Which one of the following procedures will the Control Room Supervisor use to feed the Steam
Generators using P-8C, Auxiliary Feedwater Pump, for the above conditions?
a. EOP Supplement 19, "Alternate Auxiliary Feedwater Methods."
b. ONP-7.1, "Loss of Instrument Air."
c. SOP-12, "Feedwater System."
d. EOP Supplement 31, "Supply AFW Pumps From Alternate Sources."

a. CORRECT - Supplement 19 contains directions for manually initiating AFW flow by manually operating AFW
control valves without air.
b. Plausible because the student may believe there is guidance in ONP-7.1 for manually operating the AFW control valves
without instrument air.
c. Plausible because the student may believe there is guidance in SOP-12 for manually operating the AFW control valves
without instrument air.
d. Plausible because the student may believe there is guidance in EOP supplement 31 for manually operating the AFW
control valves, however, this procedure is used to establish a water source if T-2 is not available

5

With the Plant in MODE 5 the following indications are received in the Control Room
simultaneously:
• CV-0510, Main Steam Isolation Valve, position indicating lights are OUT
• CV-3001, Containment Spray Valve, position indicating lights are OUT
• 25F7 and 25H9, Main Generator Breakers, position indicating lights are OUT
Based on these conditions, which one of the following describes (1) the DC Bus that is affected
and (2) the action, if taken, that will satisfy the REQUIRED ACTIONS of CONDITION A of LCO
3.8.10, "Distribution Systems - Shutdown?" Assume the affected DC bus is a required bus to
support equipment required to be OPERABLE.
a. (1) D11-1.
(2) Action A.1.
b. (1) D11-1.
(2) Action A.2.1.
c. (1) D11A.
(2) Action A.1.
d. (1) D11A.
(2) Action A.2.1.

a. CORRECT - Conditions given in the stem indicate a loss of D11-1 and action A.1 is the correct logic for
completing the action.
b. Plausible if the student believes that A.2.1 is the only action needed since it is immediately after the logical connector
'OR'.
c. Plausible if the student believes that the indications received in the control room are associated with DC bus D11A.
d. Plausible for a combination of 'b' and 'c'.

6

Given the following conditions with the Plant in MODE 3:
• P-7A, Service Water Pump, is out of service for repairs
• P-7B and P-7C, Service Water Pumps, are in service
• MO-0501 and MO-0510, Main Steam Isolation Valve Bypass Valves, are open for
warm-up of the Main Steam System
• Alarm EK-1163, "CRITICAL SERV WATER HEADER 'B' LO PRESSURE," annunciates
• Alarm EK-1347, "CONTAINMENT AIR COOLERS SERV WATER LEAK," annunciates
• The leak is isolated by closing CV-0824, Service Water from Containment, and
CV-0847, Service Water to Containment
After isolating the leak, 100% post accident cooling capability (1) provided for the
Containment Cooling System and (2) provided for the Service Water System.
a. (1) is
(2) is
b. (1) is
(2) is not
c. (1) is not
(2) is
d. (1) is not
(2) is not

a. Plausible because with 2 spray pumps and 2 spray valves 100% containment cooling is available but not with the MSIV
bypass valves open.
b. Plausible for the same reason as 'a' above and the student believes that service water cooling capability is tied to
operation of containment air coolers.
c. CORRECT - Containment cooling is not met because at least 2 CACs are required and Service Water cooling is
met because 2 pumps can supply service water if either non-critical or containment is capable of being isolated.
d. Plausible if the student believes that service water cooling capability is tied to operation of containment air coolers.

7

A Plant startup is in progress at 13% power. A review of post-maintenance documentation
indicates that there is no reasonable assurance that Control Rod 17 is trippable. Which one of
the following describes the Limiting Condition for Operation (LCO) that contains the actions
which are required to be performed and the reason for those actions?
a. LCO 3.1.4, "Control Rod Alignment." Plant is outside of the safety analysis because all
shutdown rods are assumed to insert on a reactor trip to achieve a 3.5% shutdown margin.
b. LCO 3.1.4, "Control Rod Alignment." Plant is outside of the safety analysis because one
additional rod is assumed to stick on a reactor trip.
c. LCO 3.1.5, "Shutdown and Part-Length Control Rod Group Insertion Limits." Plant is
outside of the safety analysis because all shutdown rods are assumed to insert on a reactor
trip to achieve a 3.5% shutdown margin.
d. LCO 3.1.5, "Shutdown and Part-Length Control Rod Group Insertion Limits." Plant is
outside of the safety analysis because one additional rod is assumed to stick on a reactor
trip.

a. Plausible because the student may believe that SDM cannot be met with a shutdown rod stuck, however, adequate
overall SDM can be obtained by adjusting boron concentration.
b. CORRECT - this question meets the K/A because the safety analyses assumes the most reactive rod will stick
on a reactor trip, and if rod 17 is stuck, this makes two rods.
c. Plausible because the rod that is stuck is a shutdown rod, however adequate overall SDM can be obtained by adjusting
boron concentration.
d. Plausible because the rod that is stuck is a shutdown rod.

8

After a Plant trip from full power, the following conditions exist:
• EOP-1.0, "Standard Post-Trip Actions," are complete
• The Control Room team is implementing EOP-9.0, "Functional Recovery Procedure"
• All full length Control Rods are fully inserted
• PCS pressure is 1400 psia and lowering slowly
Which one of the following describes the minimum in-use Success Path acceptance criteria
that must be met per EOP-9.0 for the above conditions?
a. RC-1, "CRD Insertion."
b. RC-2, "Boration using CVCS."
c. RC-3, "Boration using SIS."
d. RC-2 and RC-3.

a. Plausible because all full length control rods are inserted for this event but if SIS is actuated, RC-1 success path
acceptance criteria cannot be used.
b. Plausible because emergency boration is in progress because SIS is actuated (

9

Given the following with the Plant at full power:
• An Auxiliary Operator reports that there is a fire in MCC-7 and EC-40, "Radwaste
Panel"
• The Control Room team de-energizes MCC-7 by opening breaker 52-1103,
MCC-7 Supply Breaker, on Panel C-04
• EK-1118, "HIGH PRESSURE CONTROL AIR COMPRESSORS LO PRESS,"
annunciates on Panel C-13
• An Auxiliary Operator reports:
o T-9B, HP Control Air Compressor Receiver Tank, pressure indicates 245 psig
o There is significant damage to the MCC-7 switchgear panel and EC-33, Redundant
Safety Injection Panel
Based on the above conditions, 100% of the required Safety Injection flow (1) available
and Emergency Plan entry (2) required.
a. is
is
b. is not
is
c. is
is not
d. is not
is not

a. Plausible if the student does not realize that a loss of WESG HP Air results in a loss of operating air to both CV-3027 and
CV-3056 which causes a loss of 100% post accident ECCS flow.
b. CORRECT - With T-9B pressure , 260 psig, CV-3027 and CV-3056 are both inoperable which renders both trains of
ECCS inoperable.
c. Plausible if the student does not realize that a loss of WESG HP Air results in a loss of operating air to both CV-3027 and
CV-3056 which causes a loss of 100% post accident ECCS flow and that an emergency plan entry is required.
d. Plausible if the student does not realize that an emergency plan entry is required.

10

A manual reactor trip occurred 20 minutes ago due to a loss of D21-2, DC Bus. EOP-9.0,
"Functional Recovery Procedure," is entered. Due to this event, the NRC must be notified ...
a. after notifying the county and state but no longer than one-hour from event classification
per EI-3, "Communications and Notifications."
b. after notifying the county and state but no longer than 15 minutes from event classification
per EI-3, "Communications and Notifications."
c. of a non-emergency event within one-hour per ADMIN 4.00, "Operations Organization,
Responsibilities and Conduct."
d. within one-hour per 10CFR50.72, "Immediate notification requirements for operating
nuclear power reactors," via the Emergency Response Data System (ERDS).

a. CORRECT - Loss of D21-2 requires entry into the Emergency Plan which requires a one-hour notification to the
NRC.
b. Plausible if the student believes that the NRC must be notified in the same time frame as the local and state authorities.
c. Plausible if the student believes that this is a 1 hour reportability issue.
d. Plausible if the student believes that ERDS is an acceptable form of notification.

11

Given the following conditions:
• The Plant is in MODE 5 when a loss of Shutdown Cooling occurs
• Neither LPSI Pump can be started
• PCS temperature is 175°F
• The Reactor Vessel Head is fully tensioned
• The Pressurizer Manway is removed
Which one of the following sections of ONP-17, "Loss of Shutdown Cooling," will the Control
Room Supervisor implement to restore Primary Coolant heat removal?
a. Attachment 6, "S/G Heat Removal."
b. Attachment 5, "Option 3: PCS Boil Off and Makeup."
c. Attachment 5, "Option 2: Spent Fuel Pool Cooling."
d. Attachment 5, "Option 1: Containment Spray."

a. Plausible because the reactor head is installed but the PCS must be able to be pressurized.
b. Plausible because the PZR manway is removed but containment spray is a higher priority.
c. Plausible because the SDC system and the spent fuel pool systems have a manual cross-tie but the reactor cavity must
be full for this option.
d. CORRECT - This question matches the K/A because the candidate must understand the implications of the PZR
manway being removed. If the PZR manway were installed, damage to the spray pump suction could occur from
PCS pressure transients.

12

Given the following conditions:
• The Plant is operating at full power
• At 0800 on Monday, P-54B, Containment Spray Pump, is determined to be
INOPERABLE
• At 1500 on the same day, P-54C, Containment Spray Pump, is determined to be
INOPERABLE
• On Tuesday at 1500, P-54B is repaired, tested, and declared OPERABLE
If P-54C remains INOPERABLE, which one of the following is the latest allowable day and time
that the Plant must be in MODE 3?
a. Thursday, 1400.
b. Thursday, 2100.
c. Friday, 0800.
d. Friday, 1400.

a. CORRECT - The condition specifies one or more trains not one or more pumps. Since P-54B and P-54C are on
the same train an extension is not allowed.
b. Plausible if the student believes that an extension is allowed and utilizes 72 hours from the subsequent inoperability and
adds 6 hours to be in MODE 3.
c. Plausible if the student believes that an extension is allowed and utilizes 24 hours from the original stated completion
time but does not factor 6 hours to be in MODE 3.
d. Plausible if the student believes that an extension is allowed and utilizes 24 hours from the original stated completion
time and adds 6 hours to be in MODE 3.

13

The Plant is at 50% power with the following conditions:
• P-8C, Auxiliary Feedwater (AFW) Pump, testing is currently in progress
• FIC-0737A, P-8C AFW Pump to ‘A’ S/G, is in AUTO with it's associated valve closed
• FIC-0736A, P-8C AFW Pump to ‘B’ S/G, is in PF mode supplying 80 gpm to 'B' S/G
• Then, the Nitrogen line to CV-0727, P-8A/B AFW Pumps to 'B' S/G, develops a severe
leak and is isolated
o Instrument air to CV-0727 is still lined-up
Given these conditions, which one of the following identifies whether LCO 3.7.5, "Auxiliary
Feedwater System," is currently satisfied and, if not, also identifies the minimum actions
required to satisfy the LCO without reliance on any action statement?
a. LCO 3.7.5 is met.
No action statements are required to be entered.
b. LCO 3.7.5 is not met.
Placing FIC-0737A to CASCADE will allow all action statements to be exited.
c. LCO 3.7.5 is not met.
Repairing and testing the Nitrogen line to CV-0727 and will allow all action statements to be
exited.
d. LCO 3.7.5 is not met.
Placing FIC-0736A to CASCADE or AUTO will allow all action statements to be exited

a. CORRECT - P-8C flow controllers are operable in any mode except manual and nitrogen backup to CV-0727 is
for station blackout purposes not Tech Specs.
b. Plausible if student does not recall that FIC-0737A is operable in AUTO position.
c. Plausible if student believes that backup nitrogen is required for CV-0727 operability.
d. Plausible if student does not recall that FIC-0736A is operable in PF mode.

14

Given the following:
• The Plant is in MODE 5
• Bus 1C is removed from service for maintenance
• Bus 1D is being supplied by Safeguards Transformer 1-1
• Switchyard 'R' Bus is removed from service for maintenance
Which one of the following will cause LCO 3.8.2, "AC Sources - Shutdown," to be not met for
the above conditions?
a. Y20, Preferred AC Bus, de-energizes.
b. Bus 1D voltage is 2485VAC as read on temporary voltmeters installed in Panel C-04.
c. Y30, Preferred AC Bus, de-energizes.
d. 152-402, Station Power Transformer 1-2 Breaker, is racked to the DISCONNECT position.

a. CORRECT - Loss of Y20 renders the right train sequencer inoperable which renders D/G 1-2 inoperable which
causes LCO 3.8.2 to be not met since it is the required D/G.
b. Plausible because this is higher than normal but within the required range of operability of 2407 - 2518 VAC.
c. Plausible because this will make D/G 1-1 inoperable but this D/G cannot be the required D/G with 1C Bus de-energized.
d. Plausible because in MODE 5 this source can be used to power the 2400 VAC buses and to meet the LCO but since the
safeguards transformer is supplying the bus, the LCO is still met.

15

The Plant is at full power during the month of January. Then, the following occurs:
• EK-1124, "TRAVELING SCREEN HI dp" alarms due to ice buildup on the traveling
water screens
• The North Bay level has begun lowering rapidly
• The South Bay level is stable
Which one of the following will the CRS direct the crew to perform first to address these
conditions?
a. Align P-5, Warm Water Recirculation Pump for siphon operation per SOP-14, "Circulating
Water and Chlorination Systems."
b. Trip Dilution Water Pumps P-40A and P-40B per ONP-6.1, “Loss of Service Water.”
c. Trip Dilution Water Pump P-40A only per ONP-6.1, “Loss of Service Water.”
d. Lineup F-4B and F-4C, Traveling Water Screens, for continuous backwash per SOP-15,
"Service Water System."

a. Plausible, but not first action (step 8 of ONP-6.1 section 4.0)
b. Plausible if student believes ONP-6.1 requires tripping both of these pumps for the given conditions
c. CORRECT - ONP-6.1 directs this action first.
d. Plausible, but not first action (step 7 of ONP-6.1 section 4.0)

16

Given the following:
• The Plant is at full power
• At 0800 a loss of Y40, Preferred AC Bus, occurs due to a failure of ED-09, Inverter #4
• No other equipment is out of service
Based on these conditions, which one of the following identifies whether LCO 3.2.1, "Linear
Heat Rate," is currently met and, if not, also identifies the minimum action(s) required to meet
the LCO without performing any LCO 3.2.1 REQUIRED ACTIONS?
a. LCO 3.2.1 is met.
No action statements are required to be entered.
b. LCO 3.2.1 is not met.
Repair Inverter #4 and verify unloaded output voltage and frequency are within limits
by 1500.
c. LCO 3.2.1 is not met.
Repair Inverter #4 and re-energize Y40 by 2200.
d. LCO 3.2.1 is not met.
Place Y40 on the Bypass Regulator by 0900.

a. Plausible if student does not recall tie to Y40 loss and LCO 3.2.1.
b. Plausible if student believes that output voltage and frequency must be verified to meet LCO 3.8.9.B.
c. Plausible if student uses 24 hrs for Inverter LCO 3.8.7.A.
d. CORRECT - LCO 3.2.1.B would be entered which allows 2 hrs to reduce power to

17

Given the following conditions:
• The Plant is in MODE 3 with a Primary Coolant System (PCS) temperature of 532°F
and pressure of 2060 psia
• The PCS is being diluted in preparation for critical approach tomorrow
• The Wide Range flux level plasma indication for Source/Wide Range NI-1/3 on
Panel C-06 begins to act erratically and is determined to be unreliable
• The NI-1/3 analog count rates on Panel C-02 are indicating normal
• NI-1/3 indications on Panel C-02 channel check to NI-2/4 indications
Given these conditions, which one of the following identifies (1) if LCO 3.3.9, Neutron Flux
Monitoring Channels, and LCO 3.3.7, Post Accident Monitoring Instrumentation, are satisfied
and (2) identifies the minimum REQUIRED ACTIONS, if any, that are required?
a. (1) LCO 3.3.9 is met, LCO 3.3.7 is met.
(2) No actions are required.
b. (1) LCO 3.3.9 is not met, LCO 3.3.7 is met.
(2) Immediately stop dilution of the PCS and perform a SDM verification within 4 hours.
c. (1) LCO 3.3.9 is met, LCO 3.3.7 is not met.
(2) Restore NI-1/3 plasma indication to OPERABLE status within 7 days.
d. (1) LCO 3.3.9 is met, LCO 3.3.7 is not met.
(2) Restore NI-1/3 plasma indication to OPERABLE status within 30 days.

a. Plausible if the student believes that plasma indication is not a PAM instrument.
b. Plausible if the student believes that a channel of NMS is lost.
c. Plausible if the student believes that LCO action 3.3.7.C applies.
d. CORRECT - LCO 3.3.9 is not specific as to which indication must be operable to meet the LCO; LCO 3.3.7
specifically addresses the plasma indicators being required to meet the LCO

18

The Plant is in MODE 5 with the secondary system tagged out for a Turbine replacement and
the following conditions:
• Both Primary Coolant System (PCS) loops are filled
• ‘A’ Shutdown Cooling Train is OPERABLE and in operation with 3000 gpm flow through
the Reactor core
• PCS is solid and pressurized at 250 psia and 120°F
• Primary Coolant Pumps (PCPs), P-50B and P-50C, are operating
• P-8A, AFW Pump, is removed from service for repairs
• P-67B, LPSI Pump, is removed from service for repairs
For the above conditions, which one of the following events will cause LCO 3.4.7, "PCS
Loops - MODE 5, Loops Filled,” to be not met? (See excerpt from LCO 3.4.7 below)

LCO 3.4.7 One Shutdown Cooling (SDC) train shall be OPERABLE and in operation
with ≥ 2810 gpm flow through the reactor core, and either:
a. one additional SDC train shall be OPERABLE; or
b. The secondary side water level of each Steam Generator (SG)
shall be ≥ -84%

a T-58, Safety Injection Refueling Water Tank, level is lowered from 97% to 75%.
b. P-50B, Primary Coolant Pump, supply breaker trips due to overcurrent.
c. The Primary Coolant System is diluted by 50 ppm Boron.
d. P-8C, AFW Pump, motor-pump coupling separates during starting.

a. Plausible if student believes that a borated makeup flow path is required for the shutdown cooling train to be considered
operable. Swapping the suction source of the LPSI pump to the SIRWT is a very quick operation, however, the SIRWT
is only required to be operable in Modes 1-4.
b. Plausible if student believes that PCP operation is needed for the LCO to be met.
c. Plausible if student believes diluting the PCS will cause the LCO to be not met.
d. CORRECT - loss of AFW Pump P-8C results in no feedwater paths to be available.

19

Federal law requires Operators to work within prescribed work hour control limits. If it is
desired to grant waivers for an Operator to exceed these limits, who, as a minimum,
must (1) determine that the waivers are necessary and (2) approve the waivers?
a. Shift Manager.
Operations Manager.
b. Shift Manager.
Plant Manager.
c. Assistant Operations Manager-Shift.
Operations Manager.
d. Assistant Operations Manager-Shift.
Plant Manager.

a. Correct determiner and incorrect approver.
b. CORRECT
c. Incorrect determiner and incorrect approver.
d. Incorrect determiner and correct approver.

20

Given the following conditions:
• The Plant is in MODE 6
• GCL 11.2, "Refueling Handling Operation Shift Checklist,” is in progress in preparation
for refueling operations
• NI-1/2, Source Range Nuclear Instruments, are in operation
• NI-3, Wide Range Nuclear Instrument, is in operation
• NI-4, Wide Range Nuclear Instrument, is out of service
• The Audible Count Rate Drawer at Panel C-27 is de-energized
Based on these conditions, which one of the following describes the status of conditions being
met to perform CORE ALTERATIONS and the reason?
a. Conditions are not met because both channels of Source Range and Wide Range
Instruments are required to be in operation.
b. Conditions are met because both channels of Source Range Instruments are in operation.
c. Conditions are met because both channels of Source Range are in operation and at least
one Wide Range channel is in operation.
d. Conditions are not met because the Audible Count Rate Drawer is de-energized.

a. Plausible if the student believes that both WR and SR are required for core alternations.
b. Plausible if the student believes that only SR indication is required for core alternations.
c. Plausible if student believes both SR and one WR is required for core alterations.
d. CORRECT - LCO 3.9.2 requires the Control Room to have audible count rate indication.

21

Given the following conditions:
• The Plant is in MODE 5
• A severe thunderstorm warning is in effect
• Irradiated fuel moves are in progress in the Spent Fuel Pool
• Y30, Preferred AC Bus, is planned to be removed from service on the next shift
Which one of the following procedures will be used to perform a risk assessment for removing
Y30 from service?
a. Admin 4.02, "Control of Equipment."
b. Admin 4.11, "Safety Function Determination Program."
c. GOP-14, "Shutdown Cooling Operations."
d. GOP-11, "Refueling Operations and Fuel Handling."

. Plausible since this procedure would be used with the plant in MODE 1, 2, or 3.
b. Plausible since this procedure addresses safety functions.
c. CORRECT - This procedure is used to perform a risk assessment anytime shutdown cooling is in service.
d. Plausible since this procedure is in effect and the student believes that there is a process for performing a risk
assessment during fuel moves.

22

Given the following with the Plant in MODE 1:
• On October 1st at 0815, a Limiting Condition for Operation (LCO) that is applicable in
MODES 1-3 is discovered to be not met
• All associated Conditions of the LCO are not met
• The Control Room team implements the actions required by LCO 3.0.3
Per LCO 3.0.3, if the LCO continues to be not met then the Plant must be placed, at a
minimum, in (1) by (2) on October 2nd.
a. (1) MODE 5
(2) 2115
b. (1) MODE 5
(2) 2015
c. (1) MODE 4
(2) 1515
d. (1) MODE 4
(2) 1415

a. Plausible if the student misapplies LCO 3.0.3 and believes the plant must be in MODE 5 even though the LCO is not
applicable in MODE 4.
b. Plausible if the student misapplies LCO 3.0.3 and believes the plant must be in MODE 5 even though the LCO is not
applicable in MODE 4 and does not add the hour of prep.
c. CORRECT - Since the LCO applies in MODE 1-3, the plant only needs to be taken to MODE 4 to satisfy LCO 3.0.3.
d. Plausible if the student does not add the hour of prep.

23

Given the following conditions:
• A General Emergency was declared due to a LOCA with extremely high off-site
radioactive release rates.
• EOP-1.0, "Standard Post Trip Actions," are completed
• EOP-4.0, "Loss of Coolant Accident Recovery" is being implemented
• The Shift Manager is the acting Emergency Plant Manager
• An Auxiliary Operator (AO) has sustained life-threatening injuries in a high dose area
while attempting to isolate the uncontrolled release
• The estimated exposure for the rescue is 20 Rem
In accordance with EI-2.1, “Emergency Plant Manager," which one of the following describes
the minimum authorization requirements to attempt a rescue of the injured AO?
a. Any on-shift SRO may authorize the rescue.
b. The Shift Manager may authorize the rescue.
c. Site Vice President permission is required to authorize the rescue.
d. The Radiation Protection Manager and Shift Manager are required to authorize the rescue.

a. Plausible if the student misinterprets dose limit restrictions for life saving services during an emergency and believes that
any SRO can authorize exceeding these dose limits.
b. CORRECT - Since the Shift Manager is the Emergency Plant Manager, then he/she can authorize this exposure.
c. Plausible if the student believes the SVP is required to authorize exceeding these dose limits.
d. Plausible if the student believes that both SM and RP manager permission is required authorize exceeding these dose
limits.

24

Given the following with the Plant at full power:
• New fuel bundles are being placed in the Spent Fuel Pool (SFP) in preparation for a
refueling outage
• EK-1309, "SPENT FUEL POOL HI/LO LEVEL," annunciates on Panel C-13
• The Control Room team observes SFP level lowering on the remote monitor
• An Auxiliary Operator reports that Nitrogen pressure to the SFP South Tilt Pit Gate is
reading abnormally low
Which one of the following describes the procedure that the Control Room team will implement
to mitigate this event?
a. ONP-23.3, “Loss of Refueling Water Accident.”
b. ONP-23.4, “Loss of Spent Fuel Pool Cooling.”
c. SOP-27, "Fuel Pool System," Attachment 2, “Addition of Water to the Spent Fuel Pool.”
d. ONP-11.2, “Fuel Handling Accident.”

a. Plausible if the student believes that since fuel handling is occurring in the SFP that ONP-23.3 applies - this would apply
only if the fuel pool were cross connected to the reactor cavity.
b. CORRECT - Even though actual cooling has not been lost, this is the correct procedure if the fuel pool is not
cross connected to the reactor cavity or there hasn't been an actual fuel handling accident.
c. Plausible if the student believes that since SOP-27 may be used to add water to the SFP in normal situations that it can
be used in this situation, however it does not contain other mitigating actions that are necessary.
d. Plausible if student believes ONP-11.2 has actions that may help mitigate the event.

25

Given the following with the Plant initially at full power:
• A Steam Generator (S/G) Code Safety Valve on the ‘A' S/G begins to leak
• A Plant shutdown is commenced per ONP-9, “Excessive Load”
• Shortly after the Plant reaches MODE 3, a tube leak in the ‘A’ S/G is detected
Which one of the following is the lowest Primary to Secondary leak rate in the 'A' S/G that
requires the declaration of an Unusual Event for these conditions per the Emergency
Implementing Procedures?
a. 0.3 gpm.
b. 1.0 gpm.
c. 12 gpm.
d. 26 gpm.

a. Plausible if the student confuses the TS limit for this (0.1 gpm)
b. Plausible if the student confuses the Reactor Trip criteria for this (0.4 gpm).
c. CORRECT - FU1 - 10 gpm for loss of Containment barrier with an unisolable steam leak from affected S/G.
d. Plausible if the student confuses the EAL entry criteria for PCS identified leakage for this.